ML20079L813

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Ei 1300.01 Re Emergency Plan Activation,Ei 1300.04 Re Site Area Emergency & Ei 1300.05 Re General Emergency

ML20079L813
Person / Time
Site:	Davis Besse
Issue date:	12/02/1983
From:	Beyer B, Reed G, Wells C TOLEDO EDISON CO.
To:
Shared Package
ML20079L808	List: ML20079L810 ML20079L813
References
PROC-831202-01, NUDOCS 8401260384
Download: ML20079L813 (112)

Text

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., THE TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES REVISION INDEI PAGE REVISION PROCEDURES REVISION TEMPORARY MODIPICATIONS i 0 EI 1300.00 5 11 35 iii 3 EI 1300.01 6 EI 1300.02 5 EI 1300.03 5 EI 1300.04 5 EI 1300.05 5 EI 1300.06 5 EI 1300.07 5

, EI 1300.08 7 EI 1300.09 1 EI 1300.10 2 EI 1300.11 2 EI 1300.12 3 Revision 35 December, 1983 ii 8401260394 840118 PDR ADOCK 05000346 F PDR

t EME'.GENCY PLAN IMPLEMENTING PROCEDURES

- 1. Station Response to Emergencies (EI 1300.00)

!.- 2. Emergency Plan Activation (EI 1300.01)

3. Unusual Event (EI 1300.02)

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4. Alert (EI 1300.03)

5. Site Area Emergency (EI 1300.04) *

- 6. General Emergency (EI 1300.05)

7. Operations Support Center Activation (EI 1300.b6)

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8. Technical Support Center Activation (EI 1300.07)

9. Emergency Control Center Activation (EI 1300.08) .

{ 10. Emergency Support Center Activation (EI 1300.09) i

11. Reentry (EI 1300.10)

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12. Recovery (EI 1300.11) i.

13. Mainistrative Controls (EI 1300.12) f L

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Davis-Basse Nuclear Power Station Unic No. 1 )

Emergency Plan Implementing Procedure.

EI 1300.01 Emergency Plan Activation Record of Approval and Changes Prepared by '

G. J. Reed 5/30/80 Date Submitted by C. E. Wells Section Head _

6/13/80 Date Recommended by

'We - SRB Chairn6a l] i Date QA Approved I

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Quality Assurance Manager Date Approved.by D N-

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Date Revision SRB No. QA Sta. Supt.

Recommendation Data Approved j b, L). Qu& .Aholb) Data Approved Dat N8 W WWI p f gD=~1 'IN"

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1 EI 1300.01.6

' L- 1. PURPOSE To provide guidelines for conditions at which specific emergency l classifications must be declared.

2. REFERENCES 2.1 The Davis-Besse Nuclear Power Station Emergency Plan 2.2 Final Safety Analysis Report, DBNPS 2.3 Technical Specifications, DBNPS Unit No. 1, Appendix A and B to License No. NPF3

3. DEFINITIONS 3.1 Unusual Event - Event (s) are in progress or which have occurred that indicate a potential degradation of the level of safety of DBNPS.

3.2 Alert - Events are in progress or have occurred which involve an actual or substantial degradation of the level of safety of DBNPS.

3.3 Site Area Emergency - Events are in progress or have occurred which involve actual or likely major failures of DBNPS functiona needed for the protection of the public. There also exists a significant actual or potential release of radioactive material.

3.4 General Emergency - Events are in progress or have occurred '

which involve actual or imminent substantial core degradation or melting with the potential for loss of containment integrity, and/or involve the potential for a release of radioactive particulates or f,ases offsite of a magnitude to exceed regulatory i limits.

3.5 Emergency Action Levels (EAL's) - 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 initiat-

! ing such specific emergency measures as designating a particular classification of emergency, initiating a notification procedure, or initiating a particular protective action.

6 4. RESPONSIBILITIES .

4.1 The Shift Supervisor shall be responsible for the beplementation of this procedure.

4.2 The Emergency Duty Officer (EDO) shall be responsible for the

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continued use of this procedure once the Shift Supervisor is relieved of the EDO function.

5. INITIATING CONDITIONS 5.1 An off-normal event has occurred or is in progress.

5.2 A supplementary action step in a plant procedure (e.g. , Emergency Procedure, Alarm Procedure, etc.) refers to this procedure for classification of the indicated plant conditions.

53 Station personnel report siting an abnormal or unusual situation

. to the Operating Shift Crew.

6. PROCEDURAL STEPS 6.1 Verify the indications of the off-normal event or reported siting to ensure that the event is real. -

6.2 Ensure that the immediate actions (e.g. , use of Emergency Procedures) are taken for the safe and proper operation of the plant.

6.3 Match the plant conditions of the off-normal event or reported siting with the Conditions listed in the EAL Index, Attachment 1.

NOTE: If the event or siting does not appear to match the listed pre-determined Conditions, refer to the " Hazards to Station Operations" tab for a " Miscellaneous" Condition, which, using judgment, can be used to determine an appropriate classification of the event -

or siting.

6.4 Turn to the appropriate tab in Attachment 2, which corresponds .

to the Condition picked from the EAL Index in Step 6.3 above.

. 6.5 Assess the information available from valid indication or reports and initially classify the situation.

NOTE: 1. The specific emergency action levels described in Attachment 2 are not all inclusive. The Shift ,

Supervisor or Emergency Duty Officer shall declare an appropriate emergency classification whenever, using judgment, the station status warrants such a declaration. (Refer to the Hazards to Station Operations tab, in Miscellaneous

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for guidance.)

2. Some of the emergency action levels described are not, by their very nature, intended to be l

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EI 1300.01.6 3

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used during maintenance and/or testing situa-tions where abnormal temperature, pressure, equipment status, etc. is expected.

3. The event may not necessarily be classifiable, however, if it is, the Shift Supervisor should assume the role of EDO until the designated EDO relieves him of this responsibility.

6.6 Use the appropriate checklist from either the Unusual Event (EI 1300.02), Alert (EI 1300.03), Site Area Emergency (EI 1300.04),

or General Emergency (EI 1300.05) procedure to ensure that immediate notification requirements are met and the proper Emergency Plan response is taken.

NOTE: If it appears that several emergencies of different classes have occurred at the same time, the highest classification indicated should be declared.

6.7 Perform additional emergency actions as time and conditions permit.

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

Examples:

1. For an abnormally high lake level, operator judgment should '

take into consideration the lake level, wind direction, weather conditions, etc., before announcing a flood warning -

and initiating personnel evacuation.

2. For localized incidents that may affect only small areas,

! operator judgment should take into consideration that an alarm, when sounded, could be followed by some amplifying instructions to aid personnel response.

6.8 Continually evaluate the plant conditions to ensure the proper emergency classification is being utilized and the classification is upgraded or downgraded by the Emergency Duty Officer as

! conditions dictate per Steps 6.3, 6.4 and 6.5 above.

7. FINAL CONDITIONS 7.1 Abnormal plant conditions have been terminated and decreased below the Unusual Event Level, and an Emergency Duty Officer is no longer required.

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8. ATTAC} DENTS The following are attachments for use with this procedure:

1. Index of Emergency Action Level Conditions (EAL Index).

2. Table of Emergency Action Levels.

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.s INDEX OF EMERGENCY ACTION LEVEL CONDITIONS (EAL INDEX)

Condition Page No(s).

• Safety System Functions . 6-7 Plant Shutdown Functions 8 Coolant Pump Seizure 9 Loss of Assessment Functions 10 Control Room Evacuation 11

• Abnormal Coolant Temperatures 12 ,

• Abnormal Primary Leak Rate 13-14

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Abnormal to Primary / Secondary Leak Rate 15-16

• Core Fuel Damage 17-18 Loss of Fission Product Barriers 19

• Fuel Handling Accident 20 .

Abnormal Containment Atmosphere 21-23

• Abnormal Effluent Release 24 ,

• High Radiation Levels in Plant 25

• Abnormal Radiation Levels at Site Boundary 26-28

• Contaminated Personnel 29 Major Steam Leak 30-31 Major Electrical Failures 32

• Fire 33

• Security Threat 34

• Hazards to Station Operation 35-38 i

• Natural Events (Within Ottawa County) 39-41

• NOTE: When evaluating the EAL's in Attachment 2, the plant must be in

Mode 1 or had been in Mode 1 operating at a high power level

! when the event initiated, except for those annotated conditions.

Attachment 1 Page 1 of 1

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6 EI 1300.01.6 6 TABLE OF EMERGENCY ACTION LEVELS f

SAFETY SYSTEM FUNCTIONS Emergency Condition Indication (s) Classification Unplanned Initiation Any three of the four fol- Unusual Event

• of ECCS with Flow into loving with flow indicated: (EI 1300.02)

Core Indicated 1. HPI low flow alarm and/or LPI low flow alaon (on then off)

2. HPI and/or LPI pump status lights indicate pump (s) running

3. HPI and/or LPI pump

. current meters indicate pump (s) running

4. HPI and/or LPI pump discharge valves indicate open l

l Loss of Containment Any One of the four following Unusual Event -

Integrity requiring plant shutdown per (EI 1300.02)

T.S. 3.6.1.1:

1. Any penetrations required to be closed during accident conditions that are not: .

A. Capable of being closed by the Safety Features Actuation System, OR B. Closed by manual valves, blind flanges, or de-activated automatic valves secured in their closed position except as provided in T.S.

3.6.3.1 Ta' ale 3.6-2

2. An equipment hatch is not closed and sealed

3. An airlock is not operable

• l per T.S. 3.6.1.3 4 A sealing mechanism assoc-isted with a genetration (e.g., welds, bellows, or 0-rings) becomes inoperable NOTE: For the above asterisked (*) classification (s) the plant can be in any Mode for the listed EAL's to be applicable.

Attachment 2 Page 1 of 36

7 EI 1300.01.6 m, I 6 TABLE OF EMERGENCY ACTION LEVELS SAFETY SYSTEM FUNCTIONS (Con't)

Emergency Condition Indication (s) Classification -

4 Loss of Engineered 1. A Safety Featdres Unusual Event Safety Feature Actuation System (SFAS) (EI 1300.02) functional unit shown in T.S. Table 3.3-3 becomes inoperable per T.S.

3.3.2.1 and requires plant shutdown OR

2. The Boron Injection Flow Path (operatir.3) or ,

Borated Water Sources (operating) become in-operable and require plant shutdown per T.S. 3.1.2.2 and 3.1.2.9 Failure of Safety 1. Reactor Coolant System: Unusual Event Related Safety or Relief A. Indication of flow (EI 1300.02)

Valve to Close through Pressurizer Reliefs (red light on Panel C5798 or

• C5799)

AND B. RCS Pressure drop to <1600 psig

2. Main Steam System:

(any 2 of 3)

A. Rapid and continuing decrease in Steam Gen-erator pressure to <500 psig B. Rapid RCS cooldown rate C. Audible steam relief noise in the Control Room lasting >10 minutes Loss of Steam Feed 1. A Steam Feed Rupture Con- Unusual Event Ruptura Control System trol System (SFRCS) Fune- (EI 1300.02) tional Unit as shown in T.S. Table 3.3-11 becomes inoperable per T.S. 3.3.2.2 and requires plant shutdown N.

Attachment 2 Page 2 of 36

. o 8 EI 1300.01.6 6 TABLE r EMERGENCY ACTION LEVELS PLANT SHUTDOWN FUNCTION Emergency Condition Indication (s) Classification Loss of any system 1. Any of the following Alert which precludes placing systems become inoperable: (EI 1300.03) the plant in cold shut- A. Service Water System down (both trains)

B. Decay Heat System

. (both trains)

C. Component Cooling Water (both trains) 6l Less of any system 1. The following systems Site Area Emer-which precludes placing become inoperable: gency the plant in hot shut- A. Makeup System and HPI (EI 1300.04) down System OR B. Main Feedwater System and Auxiliary Feed-water System Failure of Reactor 1. Any time plant parameters Alert Protection System to meet conditions requiring (EI,1300.03) '

initiate and complete a a trip and RPS fails to trip initiate and complete a trip which brings the reactor suberitical

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Attachment 2 Page 3 of 36

e 9 EI 1300.01.6

.6 TABLE OF EHERGENCY ACTION LEVELS COOLANT PUMP SEIZURE Emergency Cndition Indication (s) Classification Coolant pusp seizure 1. Reactor Coolant System Alert with fuel damage indi- flow indication decreases (EI 1300.03) cated by Iodine cample rapidly

> T.S. 3.4.8 AND

2. Confirmed Primary Coolant sample results indicate

>1.0 pCi/Gran dose equiv-alent I-131 r' ',

Attachment 2 Page 4 of 36

10 EI 1300.01.6 c.

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'6 TABLE OF EMERGENCY ACTION LEVELS LOSS OF ASSESSMENT FUNCTIONS Emergency Condition Indication (s) Classification Control Room Indications Any of the Followins: Unusual Event or Alarms on Process or 1. Radiation monitoring (EI 1300.02)

Effluent Pa . meters instrumentation < min-NOT functional to an imum channels operable extent requiring plant requiring shutdown per T.S.

shutdown or other signi- requirements

, ficant loss of assess- OR ment of communication 2. RE2024A, B & C, RE2025A ,B capability & C and Backup Grab Sample capability become in-operable OR

3. Meteorological monitoring instrumentation < min-imum necessary to perform offsite dose calculations (i.e. wind speed, wind direction, and stability class)

OR

4. Post-accident instrument-ation < minimum channels

• oparable requiring plant shutdown per T.S.

requirements (T.S. 3.3.3.6)

OR

5. Complete failure of the plant telephone system and Gai-tronics system All annunciator alarms 1. Any simultaneous loss Alert and station computer of all annunciator (EI 1300.03) lost alarms and the station computer All annunciator alarms 1. Complete loss of all Site Area Emer-6l annunciator alarms sency and station computer lost >15 minutes during and station colsputer (EI 1300.04) plant transient lasting more than 15

> minutes AND.

2. Plant transient initiated or in progress i .

Attachment 2 Page 5 of 36-

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'6 TABLE OF EMERGENCY ACTION LEVELS

, CONTROL ROOM EVACUATION

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Emergency Condition Indication (s) Classification Evacuation of Control 1. Any evacuation of the Alert Room required Control Room with shut- (EI 1300.03) down control established locally within 15 minutes 6 Evacuation of Control 1. Any evacuation of the Site Area Emer-Room and Control NOT Control Room with shut- gency

• establishedlocalF down control NE estab- (EI 1300.04) within 15 minutes lished locally within 15 minutes ,

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Attachment 2 Page 6 of 36 I

12 EI 1300.01.6 6 TABLE OF EMERGENCY ACTION LEVELS I

ABNORMAL COOLANT TEMPERATURES Emergency

,- Condition Indication (s) Classification Core Subcooling is 1. As determined by Sub- Unusual Event

• Determined to be less Cooling graph or T sat (EI 1300.02) than normal (10') Meter Indication (TD14950 or TD14951)

AND

2. As indicated by the difference between Pres-surizer Temperature and T, (use incore thermo-

, c5uples temperature if Th

"***# 1" *II~'**1*)

Coolant Temperatures 1. As determined by the Unusual Event

• and/or pressures out- combination of Reactor (EI 1300.02) side of Technical Coolant Core Outlet i Specification limits Pressure and/or Outlet .

Temperature exceeding the safety limits of T.S. 2.1.1 NOTE: For the above asterisked (*) classification (s), the plant can be in any mode for the listed EAL's to be applicable.

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13 EI 1300.01.6

^/3 TABLE OF EMERGENCY ACTION LEVELS

6l ABNORMAL PRIMARY LEAK RATE I Emergency Condition Indication (s) Classification Leak Rate Requiring 1. RCS Water Inventory Unusual Event Plant Shutdown by Balance indicates (EI 1300.02)

TS Section 3.4.6.2 >l GPM unidentified leakage or >10 GPM identified leakage OR

2. Measurement of controlled leakage from the Reactor Coolant Pump seals is >10

, GPM total OR

3. Leakage from any RCS pres-sure isolation valve >5 gym as listed in TS Table 3.4-2 Leak Rate >50 GPM but Any Two of the Four Following: Alert

• within High Pressure 1. Makeup Tank level (EI 1300.03)

Injection system decreasing approximately capacity two inches per minute while RCS temperature '

remains steady

2. Increased activity on Con-tainment Vessel Airborne Monitor (s) RE 4597AAA, AAB AAC, or RE 4597BAA, BAB, RAC

3. Increase in Normal Sump level on level instruments LI 1546 A or B

4. RCS Water Inventory Balance indicates

>50 GPM leakage Loss of Coolant 1. Pressurizer level and Site Area Emer-6l gency Accident > High Pres- pressure decreasing sure Injection rapidly without an (EI 1300.04) system capacity associated cha~nge in RCS temperature (RCS tempera-ture/ pressure reach saturation conditions)

OR t~.)9 Attachment 2 Page 8 of 36

i . l 14 EI 1300.01.6

.y 6 TABLE OF EMERGENCY ACTION LEVELS i ABNORMAL PRIMARY LEAK RATE (Con't)

Emergency Condition Indication (s) Classification _

2. Containment pressure >38.4 pois and Reactor Coolant System pressure <400 psig NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.

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Attachment 2 Page 9 of 36

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TABLE OF EMERGENCY ACTION LEVELS 6l ABNORMAL PRIMARY TO SECONDARY LEAK RATE Emergency Condition Indication (s) Classification Leak Rate Requiring RCS Water Inventory Unusual Event Plant Shutdown by Balance indicates >l (EI 1300.02)

TS 3.4.6.2 GPM total Primary to Secondary leakage And the Following:

1. Main Steam Line Radiation monitor (s) (RE 600 and/or RE 609) in the " Analyze Mode" to detect N-16 indicate increased activity OR

2. Condenser Vacuum dis-charge radiation monitor (s)

(RE 1003A (B)) indicate increased activity AND l -

3. Unexplained Makeup tank level decrease while Reactor Coolant System temperature remains constant t

Rapid failure of Steam Main Steam Line Radiation Alert Generator tubes (e.g., monitor (s) (RE 600 and/or (EI 1300.03) several hundred gym RE 609) in the " Analyze Mode" primary to secondary to detect N-16 indicate 6l leak rate) increased activity, or Con-denser Vacuum discharge radia-tion monitor (s) (RE 1003 A (B)) indicate increased activity i

And One of the Following:

1. Rapid drop in RCS pressure

2. Rapid decrease in Pres-surizer and Makeup Tank levels

3. Safety Features Actuation System (SFAS) T.evel 2 activates Attachment 2 Page 10 of 36

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s 16 EI 1300.01.6 TABLE OF EMERGENCY ACTION LEVELS

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!- ABNORMAL PRIMARY TO SECONDARY LEAK RATE (Con't)

I Emergency Condition Indication (s) Classification i i

4. Main Steam line radiation  ;

monitors in the " Gross Mode" indicating more than 15000 cpm net; background equals 1000 cpm Rapid failure of one 1. Noticable drop in Alert Steam Generator tube RCS pressure and pres- (EI 1300.03) and loss of offsite surizer level power AND

2. The 13.8 KV BUSES are deenergized AND

3. Main Steam line radia-tion monitors in the

" Gross Mode" indicating more than 15000 cpm net; background equals 1000 CPe 6l Rapid failure of Steam 1. Indications for leak Site Area Emer-Generator tubes (reveral rate of 400-700 GPM gency hundred GPM leak rate AND (EI 1300.04) indicated) and loss of 2. The 13.8 KV BUSES are offsite power deenergized i  ;

es Attachment 2 Page 11 of 36

l 17 EI 1,30,0,01.6

6l TABLE OF EMERGENCY ACTION LEVELS i CORE FUEL DAMAGE l

Emergency Condition Indication (s) Classification High Coolant activity 1. Failed Fuel Detector (RSH Unusual Event sample Requiring Plant 1998) alarm with confirmed (EI 1300.02)

Shutdown by Technical sample results indicating Specifications for >1.0 pCi/Gran Dose Equiv-Iodine (T.S. 3.4.8) alent I-131 AND

2. Plant Shutdown required Very High Coolant 1. Failed Fuel Detector (RSH Alert activity 1998) "RC Letdown Activity ~

(EI 1300.03)

High" alarm AND

2. Confirmed sample results indicate >300 pCi/ Gram I-131 6l Core damage with in- 1. Confirmed primary coolant Site Area Emer-adequate core cooling sample results indicate: gency determined A. >1.0 pCi/ Gram Dose (EI 1300.04)

, equivalent I-131, and B. >100/E pCi/ Gram

• specific activity, AND

2. Reactor Coolant System Hot Les temperature >620*F OR

3. Incore thermocouple temper-atures increasing to >700*F Core damage with other 1. Confirmed primary coolant General Emergency plant conditions making sample results indicate (EI 1300.05) a release of large >300 pCi/ Gram I-131 amounts of radioactivity AND possible 2. Incore thermocouple temper-atures indicate >2000*F AND

3. Containment radiation level is > 104 R/hr

• OR

4. Cantainment pressure is

>40 psia Attachment 2 Page 12 of 36

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. '6 TABLE CF EMERGENCY ACTION LEVELS CORE FUEL DAMAGE (Con't)

Emergency Condition Indication (s) Classification Core melt situations Any one of the following General Emergency sequences occurs with a (EI 1300.05) concurrent likely failure of containment imminent:

1. Either a small or large LOCA occurs with a con-current failure of the ECCS to perform leading to severe core degradation or melting

2. A transient is initiated by a loss of the main feedwater system followed by a failure of the emer-gency feedwater system for an extended period with core melting resulting

3. A transient occurs requiring operation 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

4. A failure of offsite and onsite power along with total loss of emer-gency feedwater makeup capability occurs for several hours which leads to a core melt

5. A small LOCA occurs with initially successful ECCS, however a subsequent fail-l ure of RCS heat removal.

systems over a period of several hours leads to a core melt -

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Attachment 2 l' Page 13 of 36 l

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19 EI 1300.01.6 TABLE OF EMERGENCY ACTION LEVELS 6l LOSS OF FISSION PRODUCT BARRIERS Emergency Condition Indication (s) Classification Loss of 2 of 3 fission Any Two of the following General Emergency product barriers with a conditions exist and the (EI 1300.05) potential loss of the Third is imminent:

3rd barrier 1. Fuel clad is ruptured) as indicated by grab sample results

2. A rupture of the RCS has been confirmed

3. Containment integrity has been breached and cannot be restored NOTE: Other sections of Table I can be used for guidance in determining the above three conditions, as follows:

a. For item 1, refer to " Core Fuel Damage" at the Alert and 6l Site Area Emergency levels for sample result values and indications.

b. For item 2, refer to Abnormal Primary Leak Rate" at the 6 Alert and Site Area Emergency levels for indications of a ~

loss of primary coolant.

c. For item 3, refer to " Safety System Functions" a Loss of Containment Integrity condition at the Unusual Event level for indications of a breach in Containment integrity.

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20 EI 1300.01.6

'6 TABLE OF EMERGENCY A'CTION LEVELS FUEL HANDLING ACCIDERT Emergency Condition Indication (s) Classification Fuel Handling Accident 1. Direct informatior. from Alert

• which results in the fuel handling pers onnel (EI 1300.03)

' release of radioactivity indicating that av to Containment or Spent irradiated fuel assembly Fuel Pool area has been damaged and radioactive gases are escaping AND

2. Fire Detection System /

Radiation Monitoring System (FDS/RMS) alarms with high radiation monitor reading printed out on data logger OR

3. Local Radiation Monitoring

- Alarm Station alarms both audibly (born) and visually (green light goes OFF and red light comes ON) and is reported to the Control Room Fuel Handling Accident 1. Indications of fuel hand- Site Area Emer-6l gency*

which results in SFAS ling accident which results actuation in the release of radio- (EI 1300.04) activity to Containment ,

or Spent Fuel Pool area AND

2. SFAS incident level one actuation on radiation in Containment or isola-tion of ventilation in fuel handling area based on radiation NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.

Attachment 2 Page 15 of 36

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'!f EI 1300.01.6 21

. ; 6l TABLE OF EMERGENCY ACTION LEVELS ,

1 ABNORMAL CONTAINMENT ATMOSPHERE Emergency Condition Indication (s) Classification Increasing Containment Any Two of the Following: Alert 6 radiation, pressure, 1. Containment radiation (EI 1300.03) and temperature level correlates to an Alert as determined from the Containment Radiation EAL Plot of this attach-ment

2. Containment pressure (PI 2000, PI2001, PI2002, PI 2003) indicates >17 psia

3. Containment average air temperature (TI1356, TI 1357, TI1358) indicates *

>170'F 6 High Containment radia- Any Two of the Following: Site Area Emer-tion, pressure and 1. Containment level cor- gency temperature relates to a Site Area (EI 1300.04)

Emergency as determined from the Containment '

Radiation EAL Plot of this attachment

2. Containment pressure (PI 2000, PI2001, PI2002, PI 2003) indicates >20 psia

3. Containment average air temperature (TI1356, TI 1357, TI1358) indicates

>200*F

4. Safety Features Actuation System (SFAS) functions have activated Very High Containment Any Two of the Followins: General Emergency 6 radiation and pressure 1. Containment radiation level (EI 1300.05) correlates to a General Emergency as d'etermined from the Containment Radiation EAL Plot of this attachment i 2. Containment pressure (PI 2000, PI2001, PI2002, PI

- 2003) indicates >40 psia Attachment 2 Page 16 of 36

22 EI 1300.01.6

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6l TABLE OF EMERGENCY ACTION LEVELS ABNORMAL CONTAINMENT ATMOSPHERE (Con't)

Emergency Condition Indication (s) Classification

3. Safety Features Actuation System (SFAS) functions have activated and Con-tainment Spray is operating l

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Attachment 2 Page 17 of 36

23 EI 1300.01.6

. CONTAINMENT RADIATION EAL PLOT I

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, TDE (trl 1 .t tale I I I i i 4 l 4 e s,3, 3 , I , ,i , a a = a m CONTA!)RST RADIATION f.AL MOT INSTRUCTIONS -

N ctarves represset readings for seestors RE 45944 and B. Caetainment Nigh Reage Radiaties Detector. The precedure for their see le as fellowes

1. Determine the time after reactor shutdown.

2. Deterstae the RE &S94 Chaamel A er B rediettee reedias.

3. Ttad the point es the figure where these two numbers Latersect.

Reed the classificaties level of the line Lamediately below this 4

potat. This le the classification to use la correlation to the Attachment 2 Ah.orest Caetatement Atmosphere

• can Condistene ta EI 1300.o1, Page 18 of 36 Tatte of taergency Actice Levels.

( ._ _ . --

24 EI 1300.01.6

• 0{ TABLE OF EMERGENCY ACTION LEVELS ABNORMAL EFFLUENT RELEASE Emergency Condition Indication (s) Classification Efflueu+. Release > Confirmed analysis results Unusual Event

• limits allowed by for a gaseous or liquid (EI 1300.02)

E.T.S. 2.4.1 or release indicates > the E.T.S. 2.4.3 ILaits given in the Environ-mental Technical Specifica-tions Effluent release >10 Confirmed analysis results Alert times ".nstantaneous for a gaseous or liquid (EI 1300.03) limits allowed by release indicates >10 E.T.S. 2.4.1 or E.T.S. times the instantaneous 2.4.3 limits given in the Environ-mental Technical Specifica-tions NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.

i Attachment 2 Page 19 of 36

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l 25 EI 1300.01.6

+

' 6l TABLE OF EMERGENCY ACTION LEVELS HIGH RADIATION LEVELS IN PLAN _T Emergency Condition Indication (s) Classification General area radiation 1. Fire Detection' System / Alert

• levels or high airborne Radiation Monitoring (EI 1300.03) radioactivity >1000 times System (FDS/RMS) Console normal from an unidenti- Alarm with high radiation fied source, lasting more monitor reading displayed than 30 minutes on CRT and printed out on data logger OR

2. Local Radiation Monitoring Alarm Station alarms both audibly (Horn) and visually (green light goes off and red light comes on) and is reported to the Control Room AND

3. An area radiation survey or airborne radioactivity sample indicates activity levels >1000 times normal NOTE: For the above asterisked (*) classification (s) the plint can be in any Mode for the listed EAL's to be applicable.

I Attachment 2

Page 20 of 36

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l 26 EI 1300.01.6 TABLE OF EMERGENCY ACTION LEVELS I

!6l ABNORMAL RADIATION LEVELS AT SITE BOUNDARY Emergency Condition Indication (s) Classification 6 Projected or actual Any One of the Following:

radiation readings that 1. Station Vent Monitor Alert

• indicate a potential dose (RE2024C or 2025C) read- (EI 1300.03) of 100 mR Whole Body or ing >0.1 pCi/cc Xe-133**

500 mR Child Thyroid at for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or readings NOTE: '(These

,the Site Boundary using which will give an equiv- the apppli-adverse meteorology. valent dose in <2 hours cable con-

2. Station Vent Monitor

• centrations, (RE2024B or 2025B) read- however they ing >7.2 x 10-s pCi/cc I-131 can not be for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or readings obtained which will give an equivalent from the dose in <2 hours presently 6l ** NOTE: This concen- 3. Radiation Monitoring Team installed tration is reports radiation levels at instrumenta-based on a Site Boundary >50 mR/hr for tion. They stability class an incident projected to last are to be of F and wind 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reports of read- used when the speed of 2 mph; ings which will give an Kamen High if actual mete- equivalent dose in <2 hours range non-orology is 4. Radiation Monitoring Team itors are used, this con- reports I-131 concentrations installed.) '

centration may >1.1 x 10-7 pCi/cc at Site '

be higher Bounda ry 6l Projected or actual Any One of the Followins: Site Area Emer- .

radiation readings that 1. Grab sample, or Station gency*

indicate a potential Vent Monitor (RE2024C or (EI 1300.04) dose of 1 ren Whole 2025C) reading >1.0 pCi/cc Body or 5 rea Child Ke-133** for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or NOTE: (These are Thyroid at the Site readings whi'ch will give an the appli-Boundary using adverse equivalent dose in <2 hours cable con-meteorology. 2. Station Vent Monitor centrations, (RE2024B or 2025B) > 7.2 however they x 10~5 pC1/cc I-131 for can not be 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or readings which obtained will give an equivalent from the dose in <2 hours presently 6l ** NOTE: This concen- 3. Radiation Monitoring Team installed tration is reports radiation levels instrumenta-based on a >500 mR/hr at the site tion. They stability class boundary for an incident are to be of F and wind projected to last 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> used when

Attachment 2 Page 21 of 36

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4 27 EI 1300.01.6 6l TABLE OF EMERGENCY ACTION LEVELS ABNORMAL RADIATION LEVELS AT SITE BOUNDARY (Con't)

Emergency Ccadition Indication (s) Classification speed of 2 aph; or which will give an equiv- the Kamen if actual mete- alent dose in <2 hours High range orology is 4. Radiation Monitoring Team monitors used this con- reports I-131 concentrations are in-centration may >1.1 x 10-s pCi/cc at the stalled.)

higher. Site Boundary 6l Projected or actual A radiological puff release Site Area Emer-site boundary radiation (short instantaneous release gency*

readings corresponding from a non-continuous source) (EI 1300.04) to a while body dose occurs with:

of 50 ar/hr for 1/2 1. Station vent monitor l hour or 500 ar/hr for RE 2024C or 2025C readings 2 minutes using adverse and analysis indicating meteorology or five 9.6.x 10-2 pCi/cc** for 1/2 6 times these levels for hour or .96 pCi/cc** for 2 .

a thyroid dose. min.

OR

• • NOTE: These are the 2. Station vent monitor RE applicable con- 2024B or 2025B readings -

t centrations, and analysis indicating however they 7.2 x 10-s pCi/cc** for cannot be ob- for 1/2 hour or 7.2 x 6 tained from the 10-5 pCi/cc** for 2 min.

presently in-stalled instru-mentation. They are to be used when the Kamen High range non-itors are in-stalled in the '

near future.

Projected or actual A radiological release General Emergency

• site boundary radia- occurs with: -

(EI 1300.05) tion reading corres- 1. Projected doses at the ponding to a whole site boundary equate to I body dose of 1 R/hr 1 R/hr whole body or 5 or a thyorid dose of R/hr thyroid (or higher) l 5 R/hr using actual using actual meteorologi-I ' g; meteorology. cal data.

[ * ,-

Attachment 2 l, Page 22 of 36 4

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28 EI 1300.01.6 TABLE OF EMERGENCY ACTION LEVELS 6l ABNORMAL RADIATION LEVELS AT SITE BOUNDARY (Con't)

Emergency Condition Indication (s) Classification OR

2. A Radiation Monitoring Team at the site boundary reports radiation levels at 1 R/hr or 2.27 x 10-s pCi/cc I-131 (or o higher).

NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.

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Attachment 2 Page 23 of 36

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.i 29 EI 1300.01.6

..~

TABLE OF EMERGENCY ACTION LEVELS 6l

, CONTAMINATED PERSONNEL Emergency Condition Indication (s) Classification Transportation of con- 1. Any event which requires Unusual Event

• taminated injured in- transportation of a con- (EI 1300.02) dividual(s) offsite taminated injured indi-vidual to an offsite medical facility NOTE: For the above asterisked (*) classification (s), the plant can be ,

in any Mode for the listed EAL's to be applicable.

)

l I

l Attachment 2 l Page 24 of 36 i

l

. - - . ~ . - -

30 EI 1300.01.6 n l 6 TABLE OF EMERGENCY ACTION LEVELS MAJOR STEAM LEAK Emergency Condition Indication (s) Classification Major Steam Leak with Increasing Containment pres- Unusual Event I NO, Primary to Secondary sure (if leak is inside Con- (EI 1300.02)  ;

leakage tainment) or unusually loud noise outside Containment And One of the Following:

1. Steam and Feedwater Rupture Control System (SFRCS) initiates

2. Main Steam Pressure (s)

, and/or Steam Generator Pressure (s) drop to <300 PSIG Major Steam Leak with 1. Indication of a Major Alert

>10 GPM Primary to Steam Leak (EI 1300.03)

Secondary Leak Rate AND -

2. Main Steam Line Radiation Monitor (s) (RE 600 and/or RE 609) in the " Analyze Mode" to detect N-16 indicate increased '

activity, AND

3. RCS Water Inventory Balance indicates >10 GPM Primary to Secondary leakage 6 AND

4. Main Steam line radiation monitors in the " Gross Mode" indicating more than 15000 cpm net; background equals 1000 cpm Major Steam Leak with 1. Indication of a Major Site Area Emer-6l >50 GPM Primary to Steam Leak gency Secondary leak rate and AND (EI 1300.04) fuel damage indicated 2. Main Steam Line radiation monitor (s) (Rf 600 and/or RE 609) in the " Analyze Mode" to detect N-16 indicate increased activity AND Attachment 2 Page 25 of 36

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a 31 EI 1300.01.6

,/ 6l TABLE OF EMERGENCY ACTION LEVELS MAJOR STEAM LEAK (Con't)

Emergency Condition Indication (s) Classification

3. RCS Water Inventory Balance indicates >50 GPM Primary to Secondary Leak rate AND

4. Confirmed Primary Coolant sample results indicate Dose Equivalent I-131 above acceptable limits of T.S. Figure 3.4-1

. AND

5. Main steam line radiation monitors in the " Gross Mode" indicating more than 150,000 cpm net; background equals 1,000 cpm.

i

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Attachment 2 Page 26 of 36 f

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32 EI 1300.01.6 3

6l TABLE OF EMERGENCY ACTION LEVELS MAJOR ELECTRICAL FAILURES Emergency Condition Indication (s) Classification Loss of offsite power 1. Both Emergeu g Diesel Unusual Event or of onsite AC power Generators and the Main (EI 1300.02) capability Generator out of service simultaneously OR

2. Loss of all three 345 KV transmission lines 6l Loss of offsite power 1. All AC buses deenergized Site Area Emer-and all onsite AC power more than 15 minutes gency for more than 15 minutes (EA 1300.04) o Loss of all onsite 1. All DC buses deen- Alert DC power ergized as determined (EI 1300.03) by breaker positions, and line voltage or amperage meters 6l Loss of all onsite DC 1. All DC buses deenergized Site Area Emer-gency '

power for more than 15 for more than 15 minutes minutes (EI 1300.04)

Attachment 2 Page 27 of 36 l

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EI 1300.01.6 6l TABLE OF EMERGENCY ACTION LEVELS FIRE Emergency Condition Indication (s) Classification Uncontrolled fire NOT 1. Any fire at the Station Unusual Event

• involving a safety that requires offsite (EI 1300.02) system, but requiring rupport offsite support Uncontrolled fire 1. Any fire at the Station Alert potentially affecting that requires offsite (EI 1300.03) safety systems and support requiring offsite AND support 2. Has the potential to damage or degrade a safety system 6 Fire resulting in the 1. Observation of a major Site Area Emer-lo,ss of redundant fire that defeats the gency safety system trains capability of redundant (EI 1300.04) or functions safety system trains which includes both trains or functions NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable, i

Attachment 2 l Page 28 of 36

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. e 34 EI 1300.01.6 6l TABLE OF EMERGENCY ACTION LEVELS SECURITY THREAT Emergency Condition Indication (s) Classification Security Threat, At- 1. Report by a senior Unusual Event

• tempted Entry, or member of the Security (EI 1300.02)

Attempted Sabotage Force of an Attempted Entry, Attempted Sabotage, or a Security Threat

? --

Ongoing Security 1. Report by a senior Alert *

• Compromise member of the Security (EI 1300.03)

Force that a Security Emergency is in progress 6l Imminent loss of 1. Physical attack on the Site Area Emer-physical control of the plant involving imminent gency*

plant occupancy of the Control (EI 1300.04)

Room or local shutdown stations Loss of physical control 1. Physical attack on the General Emergency

• of the facility plant which has resulted (EI'1300.05) in occupation of the Control Room or loca1 shutdown stations by unauthorized personnel NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.

't .,

Attachment 2 Page 29 of 36

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35 EI 130,0.01.6  :

- l

$l6 TABI.E OF EMERGENCY ACTION I.EVELS

,, HAZARDS TO STATION OPERATIONS Emergency  ;

Condition Indication (s) Classification Aircraft crash onsite or 1.

~

Control Room informed by Unusual Event

• unusual aircraft activity Station personnel who have (EI 1300.02) over facility made a visual siting Aircraft crash affect- 1. Control Room informed Alert ing plant structures by Station personnel who (EI 1300.05) have made a visual siting ,

6l Aircraft crash damaging 1. Control Room informed by ,

-Site Area Emer-vital plant systems Station personnel who have gency made a visual siting (EI 1300.04)

AND

2. Instrumentation readings on vital systems indicate equipment problems Train derailment onsite 1. Control Room informed by Unesual Event

• Station personnel who have (EI 1300.02) made a visual siting '

AND

2. Station Structures have been damaged

) OR

3. Danger or potential danger to Station personnel exists Onsite explosion Control Room informed by Unusual Event

• Station personnci who have (EI 1300.02) made a visual siting Onsite explosion 1. Control Room informed by Alert affecting plant opera- Station personnel who have (EI 1300.03) tions made a visual siting AND

2. Instrumentatio'n readings on plant systems indicate

- equipment problems NOTE: For the above asterisked (*) classification (s), the plant can be

( ', in any Mode for the listed EAL!s to be applicable.

Attachment 2 Page 30 of 36 l ..

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36 EI 1300.01.6

~6 TABLE OF EMERGENCY ACTION LEVELS HAZARDS TO STATION OPERATIONS (Con't)

- Emergency Condition Indication (s) Classification 6l Explosion causing 1. Explosion causing either Site Area Emer-severe damage to hot of the following combina- gency shutdown equipment tions of systems to become (EI 1300.04) inoperable:

A. Makeup System and HPI System OR B. Main Feedwater System and Auxiliary Feed

. water System Toxic or flammable gas 1. Control Room informed by Unusual Event

• release from its con- Station personnel who (EI 1300.02) tainer to atmosphere at have discovered it life threatening levels near or onsite Uncontrolled toxic or 1. Control Room informed by Alert flammable gas release Station personnel who have (EI 1300.03) at life threatening levels made a visual siting ,

within plant facilities OR

2. Chlorination System Trouble Alarm initiates and Station personnel verify a signifi-cant release 6l Uncontrolled toxic or 1. Control Room informed by Site Area Emer-flammable gas release Station personnel who have gency at life threatening made a visual siting (EI 1300.04) levels within plant- AND vital areas 2. Chlorination System Trouble Alarm initiates and Station personnel verify a signifi-cant release

• OR

3. The Control Room Ventila-tion System automatically shuts dowa NOTE: For the above asterisked (*) classification (s), the plant can be

- , in any McJe for the listed EAL's to be applicable.

Attachment 2 Page'31 of 36

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l 37 EI 1300.01.6 '

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[ 6l TABI.E OF EMERGENCY ACTION LEVELS I

HAZARDS TO STATION OPERATIONS (Con't)

Emergency Condition Indication (s) Classification i

Turbine damage causing Control Room informed by Alert casing penetration Station personnel who have (EI 1300.03) made a visual inspection of turbine casing Missile impact on plant Control Room informed by Alert structures Station personnel of any (EI 1300.03) missile 6l Missile impact causing 1. Control Room informed by Site Area Emer-severe damage to Hot Station personnel of any gency Shutdown equipment missile impact on Hot Shut- (EI 1300.04) down equipment AND i 2. Instrumentation readings on Hot Shutdown equipment indicate equipment problems 6 Miscellaneous Other plant conditions exist Unusual Event ,

that warrant increased aware- (EI 1300.02) ness on the part of the plant operations staff or State and/

or local offsite authorities which are not covered under any other existing station procedures.

Miscellaneous Other plant conditions exist Alert that warrant precautionary (EI 1300.03) activation of the Technical Support Center and Eaergency Control Center and placing other key emergency personnel on standby.

Site Area Emer-Miscellaneous Other plant conditions exist that warrant activation of gency emergency centers and monitor- (EI 1300.04) t

. .m

.7 3

, Attachment 2 Page 32 of 36 4* "-NW8"' 'P ' " * - " ' ****

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38 EI 1300.01.6

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'6 TABLE OF EMERGENCY ACTION LEVELS HAZARDS TO STATION OPERATIONS (Con't) 4 Emergency Condition Indication (s) Classification ing teams or a precautionary notification to the public near the site.

6 Miscellaneous Other plant conditions exist, General Emergency from whatever source, that (EI 1300.05) make release of large amounts of radioactivity in a short time period possible, e.g.,

any core melt situation.

l l-G' i x;

Attachment 2 Page 33 of 36

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39 ,

EI 1300.01.6 6l TABLE OF EMERGENCY ACTION LEVELS NATURAL EVENTS (WITHIN OTTAWA COUNTY).

Emergency Condition Indication (s) Classification Any earthquake 1. Confirmed Station Seismic Unusual Event

• Instrumentation Alarm (EI 1300.02)

Earthquake > Operating 1. Procedure for Earthquake Alert Basis Earthquake (OBE) Evaluation (SP 1105.17) (EI 1300.03) levels indicates earthquake >.08 g 6l Earthquake > Safe 1. Procedure for Earthquake Site Area Emer-Shutdown Earthquake Evaluation (SP 1105.17) gency (SSE) levels indicates earthquake (EI 1300.04)

>.15 g Any Tornado onsite 1. Control Room informed by Unusual Event

• Station personnel who have (EI 1300.02) made a visual siting of a Tornado crossing the site boundary Tornado striking 1. Control Room informed by Alert facility Station personnel who have (EI 1300.03) made a visual siting Hurricane 1. Control Room informed Unusual Event

• by Load Dispatcher of (EI 1300.02)

Hurricane Watch for Ottawa County Hurricane force winds 1. Control Room informed by Alert up to Design Basis Load Dispatcher of (EI 1300.03),

Levels Hurricane striking Ottawa County AND

2. Wind speed indication from the station meteorological tower is of sustained winds approaching 90 mph i

NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable. ,

Attachment 2 Page 34 of 36 y -

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9 8 l

I 40 EI 1300.01.6 i-%

[ 6l TABLE OF EMERGENCY ACTION LEVELS NATURAL EVENTS (WITHIN OTTAWA COUNTY)(Con't)

Emergency Condition Indication (s) Classification Hurricane force winds 1. Control Room informed by Site Area Emer-6l > Design Basis Levels Load Dispatcher of gency Harricane striking Ottawa (EI 1300.04)

County AND

2. Wind speed indication from

. the station meteorological tower of sustained winds above 90 mph 50 year flood or low 1. Control Room informed by, Unusual Event

• water, surge or Load Dispatcher (EI 1300.02) seiche OR

2. Control Room informed by Station personnel who have made visual siting AND

3. High Forebay level alans or lake level indication oscillating with readings high (>580 feet I.G.L.D.) '

or low (<565 Feet I.G.L.D.)

Flood, low water, surge 1. Control Room informed by Alert or seiche at Design Load Dispatcher (EI 1300.03)

Levels OR

2. Control Room informed by Station personnel who have made visual siting AND

3. High Forebay level alarm or lake level ogcillating with readings at Design Levels high (584 feet I.G.L.D.) or low 562.1 feet I.G.L.D.)

NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAL's to be applicable.

.I Attachment 2 Page 35 of 36 1

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41 EI 130,0.01.6 6l TABLE OF E11ERGENCY ACTION LEVELS NATURAL EVENTS (WITHIN OTTAWA COUNTY)(Con't)

. Emergency Condition Indication (s) Classification Flood, low water, surge 1. Control Room informed Site Area Emer-6l by Load Dispatcher gency or seiche > Design Levels OR (EI 1300.04)

2. Control Room informed by Station personnel who have made a visual siting AND

3. High Forebay level alarm

• or lake level indication oscillating with readings

> Design Levels high (>584 '

feet I.G.L.D.) or low

(<S62.1 feet I.G.L.D.)

)

l l

l Attachment 2 END Page 36 of 36

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EI 1300.04.0 Davis-Basse Nuclear Power Station Unit No. 1 i

Emergency Plan Implementing Procedure EI 1300.04 Site Area- W '

Record of Approval and Changes Prepared by C. J. Reed 5/30/80 Date Submitted by C. E. Wells 6/13/80 Section Head Data Recommended by bWs.j_ ___

{

, SRB Chaired 6 'Date QA Approved //

Qual'itj Assurance Manager Date Approved.by T / 8/b Station Superintendent (/ Date Revision SRB QA Sta. Supt.

No. Recommendation Data Approved Data Approved D l Msg r#c #ff r o " y ~ pte%'

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1 EI 1300.04.5

1. PURPOSE ,

To outline the course of action and protective measures required to mitigate the consequences of a Station emergency at the Site Emergency level in order to safeguard Station personnel and the general public.

2. REFERENCES 2.1 Davis-Besse Nuclear Power Station Emergency Plan 2.2 EI 1300.01, Emergency Plan Activation

3. DEFINITIONS Site Area Emergency - Events are in progress or have occurred which involve actual or likely major failures of DBNPS functions needed for the protection of the public. There also exists a significant actual or potential release of radioactive material.

4. RESPONSIBILITIES The Emergency Duty Officer shall be responsible for the implementation of this procedure.

NOTE: For a Site Area Emergnecy, the Shift Supervisor shall assume the role of the Emergency Duty Officer until the on-call Emergency Duty Officer relieves him of this function.

5. INITIATING CONDITIONS 5.1 Whenever a Site Area Emergency has been recognized and classified per EI 1300.01, Emergency Plan Activation. >

5.2 At the direction of the Emergency Duty Officer.

6. PROCEDURAL STEPS NOTE: Attachment 2 should be used to ensure that none of the following steps are overlooked.

6.1 Ensure the appecpriate alarm is sounded as necessary:

6.1.1 Fire ,

6.1.2 Containment Evacuation .

6.1.3 Initiate Emergency Procedures NOTE: The station alarm need not be sounded when downgrading from a higher classification.

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2 EI 1300.04.5 6.2 Make the following announcement (s), not necessarily in this o, rder:

6.2.1 " Attention all personnel; attention all personnel: a Site Area Emergency has been declared. All members of the onsite emergency organization report to your designated emergency response facilities. All other personnel assemble at your designated assembly areas and await further instructions.

NOTE: 1. If the situation is radiological in nature, also announce that there is to be no eating, smoking or drinking in

- the plant until further notice.

2. If a General Emergency had previously existed, disregard the above announcement and announce the following:

" Attention all personnel. The emergency condition has been downgraded to a Site Area Emergency. I repeat, the emergency condition has been downgraded to a Site Area Emergency."

6.2.2 If there is a localized emergency (e.g., fire), y announce its type and location and instruct personnel ...

to stand clear of this area.

6.3 Notify the following individuals:

6.3.1 Nuclear Security Supervisor 6.3.2 SAS Operator, if offsite support is needed for fires or medical emergencies.

6.3.3 Station Superintendent NOTE: If upgrading or downgrading from a prior emergency classification, the Station Superintendent and Key Emergency Response Personnel should be contacted via the communications channels between the emergency response facilities. In which case, the following methodology can be disregarded.

~

1. During normal working hours, the Station Superintendent should be reached over the Station gai-tronics or telephone or by utilizing his " beeper" o

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l 3 EI 1300.04.5 pager in accordance with AD 1827.17, Emergency Call System. During off normal working hours, manually telephone his office and home using the numbers listed in Administrative Memorandum No.

37. If there is no answer, then attempt a page.

2. Upon being notified, the Station Superintendent shall then confer with the Shift Supervisor and ascertain the degree of response that may be necessitated by the plant event.

'. NOTE: If the Station Superintendent does NOT respond within five minutes, re-initiate the page. If a second page fails, the Assistant Station Super-intendent, Operations, should be contacted. In the event that neither can be contacted, the Shift Supervisor should exercise his own judgement in dealing with the situation.

3. The Station Superintendent can then authorize the Shift Supervisor to tape an announcement on the Telephone Pager located in the Shift Supervisor's office.

NOTE: The announcement should include: 1) the Emergency Classification, 2) the level of response required, and 3) a brief description of plant conditions.

6.3.4 Key Emergency Response Personnel

1. The Shift Supervisor or his designee shall then activate the pagers in accordance with AD'1827.17, Emergency Call System, of the key emergency res-ponse personnel as listed in Administrative Memorandum No. 37.

2. When paged (beeped), those individuals must telephone the Edison Operator who shall connect them with the Telephone Pager thus allowing them to hear the recorded message.

3. These individuals shall then notify additional personnel as required to provide adequate response e

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l 4 EI 1300.04.5 to the event by using Administrative Memorandum No. 37.

NOTE: The NRC resident inspector should be notified by telephone if possible.

6.4 Notify the following agencies:

NOTE: When notifying an outside agency, record the time and the name of the individual contacted using Attachment 2 and request a return telephone call from the agency to verify notification.

6.4.1 Sheriff's Department, Ottawa County This must be accomplished within 15 minutes of the emergency declaration. It can be performed by phone using either the regular number or an unlisted number provided for emergencies (both found in Admin. Memo

37) or, if necessary, by radio through CAS or SAS.

NOTE: This notification should include your identification, the type of classification, the date and time it was made, and a brief discription of the cause of the event.

6.4.2 NRC Region III, Office of Inspection and Enforcement; NRC, Emergency Incident Response Center, Bethesda, Maryland . ,

This must be accomplished by the NRC Emergency Notifica-tion System - Red Phone or commercial phone within one hour of the emergency declaration.

6.5 Activate the following emergency response facilities:

NOTE: If upgrad'ngi or downgrading from a prior emergency classification, the following facilities should already be activated. In which case, the fcllowing steps can be disregarded.

6.5.1 The Operations Support Center as per EI 1300.06. ,

6.5.2 The Technical Support Center as per EI 1300.07.

6.5.3 The Emergency Control Center as per EI 1300.08.

6. 5 . I. The Emergency Support Center as per the Corporate Radiological Emergency Response Plan.

=

. - . . . =  : . . ~ .

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j 5 EI 1300.04.5 6.6 Assess the situation by:

6.b.1 An increased amount of plant instrumentation shall be monitored, in particular, indications of core status (e.g. , incore thermocouple readings, etc.) shall be monitored.

6.6.2 If a radiological accident is occurring, monitoring efforts shall be greatly increased. Onsite and offsite monitoring teams shall be dispatched as per AD 1850.05, Radiation Monitoring Team Survey. In addition to beta-gamma field measurements, the change-out of thermoluminescent dosimeters (TLD's) at frequent intervals may be performed; air sampling and collection of other environmental media for assessment of material transport and deposition shall be performed.

6.6.3 Dose assessment activities shall be conducted as per AD 1827.10, Emergency Dose Estimate, with an increased emphasis on dose projection for use as a factor in determining the necessity for protective actions.

Radiological and meteorological instrumentation readings shall be used to project the dose rate at predetermined distances from the Station, and to determine the integrated dose received. In reporting the dose projections to the EDO or to offsite agencies, the dose rate, dose, and the basis for the time used for the dose estimate shall always be provided. Any confirmation of dose rates by offsite RMT's -shall be .

reflected in reporting and/or revising dose estimate information provided to applicable offsite agencies.

NOTE: Additional information on personnel actions can be found in Attachment 1.

6.7 Review EI 1300.01, Emergency Plan Activation, when plant conditions change to determine if the event should be reclassified.

NOTE: If reclassification is not requried but the change was somewhat significant or unusual, an update should be made and documented on the Periodic Update Record, Attachment 3.

6.8 Proceed to EI 1300.03 or EI 1300.02 if the condition is downgraded to an Alert or an Unuse41 Event respectively. Note this on Attachment 2. Steps 6.9 and 6.10 can then be omitted.

6.9 Perform the following if the emergency situation is mitigated and completely declassified:

6.9.1 Make the following notifications:

~

6 EI 1300.04.5 O;t x.

1. To Station personnel over the Station public c,9 address system:

" Attention all personnel. The emergency situation has been terminated. I repeat, the emergency situation has been terminated."

2., The Station Superintendent and Key Emergency Response Personnel should be contacted via the communications channels between the emergency response facilities.

. 3. The State and County Emergency Operations Centers should be contacted via the communications channels set up between TED and these two facilities.

NOTE: This notification should simply state your name, that you're calling from DBNPS and that the emergency condition at Davis-Besse no longer exists and why (e.g., the high radiation levels in the Containment building have subsided, etc.). Again record thi time and the name of the individual contacted on Attachment 2.

4. The NRC Incident Response Center via the NRC Emergency Notification System or commercial phone. , ,

6.9.2 Perform any necessary reentry actions as per EI 1300.10, Reentry.

6.9.3 Perform any necessary recovery actions as per EI 1300.11, Recovery.

6.10 Proceed to EI 1300.05, if the emergency classification is upgraded to a General Emergency. ,

i 7. FINAL CONDITIONS 7.1 The emergency condition has been downgraded to an Alert or an Unusual Event.

7.2 The emergency condition no longer exists and actions are being taken as per either EI 1300.10, Reentry, or EI 1300.11, Recovery.

7.3 The emergency condition has been upgraded to a General Emergency and actions are bei_g taken as per EI 1300.05, General Emergency.

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7 EI 1300.04.5 .

8. ATTACHMENTS The following attachments are for use with this procedure:

1. Personnel Actions During a Site Area Emergency

2. ED0/ Shift Supervisor Site Area Emergency Checklist 3 Periodic Update Record I

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8 EI 1300.04.5

• PERSONNEL ACTIONS DURING A SITE AREA EMERGENCY On-call Emergency Duty Officer (EDO)

The on-call Emergency Duty Officer, upon being informed that a Site Area Emergency has been declared, shall (if not previously accomplished):

1. Report to the Emergency Control Center and assume the position of Emergency Duty Officer in the onsite emergency organization, relieving the Shif t Supervisor of this duty.

2. Evaluate the information, data, and methods utilized by the Shift Supervisor in making his determination in order to ensure that the proper emergency classification has been made.

3. Determine to what extent the onsite emergency organizations shall be activated.

a. For a Site Area Emergency, the emergency teams and the entire onsite emergency organization shall be activated. A major portion, if NOT all, of the corporate emergency organization may be activated, as determined by the Emergency Director or the Corporate Radiological Emergency Response Plan.

4. Activate the ECC according to the Emergency Control Center Activation Procedure, EI 1300.08. .s

5. Continue assessment actions initiated by the Shift Supervisor.

b

6. Recommend protective actions to the Ottawa County Sheriff or the County EOC Officials as required by assessment results per AD 1827.12, Protective Action Guidelines.

7. Ensure that continuous online phone communications are maintained with the State and County Emergnecy Operations Centers.

TSC Manager The TSC Manager, upon being informed that a Site Area Emergency has been declared, shall:

1. Report to the Technical Support Center and assume the role of TSC Manager in the onsite emergency organization.

2. Perform the steps as outlined in EI 1300.07, Technical Support Center Activation. .

OSC Manager The OSC Manager, upon being informed that a Site Area Emergency has been declared, shall:

Attachment 1 ,

Page 1 of 5 l

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9 EI 1300.04.5

1. Report to the Operations Support Center and assume the position of i OSC Manager in the onsite emergency organization.

2. Perform the steps as outlined in EI 1300.06, Operations Support I Center Activation.

Plant Operations Mansaer I

The Plant Operations Manager, upon being informed that a Site Area Emergency has been declared, shall:

1. Report to the Control Room and assume the position of Plant Operations l Manager in the onsite emergency organization.

1 2. Perform the steps as outlined in EI 1300.00, Station Response to Emergencies.

Operatina Shift Crew

1. Control Room operators shall maintain safe operations on the Station and minimize the potential hazards to Station personnel and the general public as directed by the Shift Supervisor.

2. In the event that the Shift Supervisor is incapacitated, his duties and responsibilities shall be assumed by the Assistant Shift Supervisor in the Control Room until relieved by a qualified Shift Supervisor.

3. Equipment and auxiliaries operators shall maintain safe operations of the plant as directed by the Shift Supervisor. -

4. The Shift Technical Advisor (STA) shall provide technical and analytical support in the diagnosis of off-normal events. He shall also advise and assist the Shift Supervisor on matters pertaining to the safe and proper operation of the plant with regards to nuclear safety.

Shift Chemistry and Radiation Test (C&RT)

1. The shift C&RT shall report immediately to the Health Physics Monitoring Room to await instructions from the Shift Supervisor or Chemist and Health Physicist.

2. The shift C&RT shall provide radiological monitoring for the Fire Brigade in the event of a fire in RACA.

3. The shift C&RT shall monitor all injured personnel before they leave the site. An off-shift C&RT shall accompany or meet any contaminated personnel at the offsite medical facilities.

4 Attachment 1 Page 2 of 5 j i

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10 EI 1300.04.5 Fire Brigade ()

1. The Fire Brigade Captain shall respond to any announced fire, evaluate

. the situation, direct the Fire Brigade, and keep the Shift Supervisor informed of the status of the fire.

2. Personnel assigned to the Fire Brigade shall respond to any announced fire with appropriate fire figt ling and protective equipment and extinguish the fire as directed by the Fire Brigade Captain.

3. The first Fire Brigade Captain arriving on the scene should remain in charge of the fire until termination of the emergency or relieved by the Station Fire Chief or Assistant Fire Chief.

4. When local fire scpport is required within the Protected Area, local fire department personnel will function in conjunction with, and under the direction of the DBNPS Fire Brigade.

First Aid Team

1. The First Aid Team Leader shall respond to any announced personnel injuries, evaluate the situation, direct the First Aid Team and keep the Shift Supervisor informed of the status of the injured individual (s).

2. Personnel assigned to the First Aid Team shall respond to any announced personnel injury with appropriate first aid supplies and provide the ,es necessary first aid treatment. (

Nuclear Security Force - ,

1. The Nuclear Security Supervisor, upon notification by the Shift Supervisor that an Site Area Emergency exists, shall implement AD 1808.00, the Industrial Security Plan Procedure.

2. Nuclear Security Officers shall maintain security of the Station as directed by the Nuclear Security Supervisor.

Radiation Monitoring Team (RMT)

1. All qualified non-chemistry'and health physics RMT members will report to the turbine deck assembly area.

2. The OSC Manager will designate RMT members as to their assignment offsite or onsite.

a. A list of qualified RNT's is found. in Adminsitrative Memo 42.

b. Only one member of each team should be from the C&HP section.

Attachment 1 Page 3 of 5 i

11 EI 1300.04.5

3. If requested by the EDO, offsite RMT's will be dispatched to the Radiological Testing Laboratory (RTL) for further instructions.  ;

4. RNT's responding from offsite will report to the RTL for further assignment.

Onsite Personnel Personnel, who do NOT have specifically assigned duties shall proceed to areas as prescribed in AD 1827.11, Assembly, Accountability, and Subsequent Evacuation.

Offsite Station Personnel

1. Station personnel whose emergency response is at the station will be admitted upes verbal communication with security. These personnel should report to their emergency assembly area (as designated by AD 1827.11, Assembly, Accountability, and Subsequent Evacuation) for assignment.

2. Station personnel whose emergency response is in the DBAB will report to their designated location.

3. Non-badged personnel will report to the location designated by this contact according to the severity of the emergency (i.e., DBAB, PPF, or ESC) . Normal badging procedures will be utilized if it becomes necessary for these personnel to enter the station.

Offsite Agencies and Organizations .

1. The Carroll Township Ambulance Service shall provide transportation service as required for offsite medical treatment.

2. The H.B. Magruder Memorial Hospital and St. Charles Hospital shall provide offsite medical treatment for personnel as required.

3. The Carroll Township Fire Department shall provide primary response to fire alarms onsite as required.

a. The Village of Oak Harbor Fire Department shall provide alternate response to fire alarms onsite as required through mutual aid with Carroll Township.

4. The Ottawa County Sheriff's Department is experienced in providing area control, communications assistance, and direct handling of the

! local population, including evacuation,,should it become necessary.

The Sheriff's Department provides 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> radio communication coverage ]

with the Shift Supervisor at DBNPS and is the lead offsite governmental 1 agency contacted in the event of an emergency at the site. l l

7 Attachment 1 Page 4 of 5 l

1 l

I 12 EI 1300.04.5 . .

5. Engineering firms (e.g., Babcock and Wilcox, Bechtel, etc.) may be

. requested to respond to provide additional engineering assessment capabilities.

6. Mutual aid utilities may provide additional support of personnel or equipment as available.

7. Other support organizations may be contacted as identified in EI

1300.08.

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l 13 EI 1300.04.5 EDO/ SHIFT SUPERVISOR SITE AREA EMERGENCY CHECKLIST ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS -

1. Sound the appropriate alarm as per Step 6.1.

NOTE: This need not be performed if downgrading form a higher classification.

2. Notify plant personnel as per Step 6.2.

3. Notify the following personnel:

a. Nuclear Security Supervisor (Ext. 556 or 557)

b. In the event of a fire or medical emergency, notify the SAS Operator who will notify the Ottawa County Sheriff's Department, who in turn notifies the appropriate response agencies,

c. Station Superintendent (as per Step 6.3.2)

d. Key Emergency Response Personnel (as per Steps 6.3.2 and 5.3.3)

4. Notify the following agencies: ,

a. Ottawa County Sheriff's Dept.

(as per Step 6.4.1)

NOTE: The initial notification should be made within 15 minutes of declaring the emergency. The initial notification message should include:

a. Your name, , and that you are calling from the Davis-Besse Nuclear Power Station,

b. The type of classification, Site Area Emergency,

c. The date, , and time, am/pm it was made, and

d. A brief description of the event (e.g. , fire affect-ing safety systems, high containment radiation levels, etc.):

Record the name of individual contacted:

Then request a return (verification) telephone call.

Time received: am/pm

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Attachment 2 ,

Page 1 of 3 h

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l 1

l 14 EI 1300.04.5 EDO/ SHIFT SUPERVISOR SITE AREA EMERGENCY CHECKLIST (Con't)

ACTION REQUIRED DATE TIME INITIALS NOTE: If downgrading from a a General Emergency, disregard the above initial notification message and instead provide the followns information:

a. Your name, , and that you are calling from the Davis-Besse Nuclear Power Station,

b. The classification has been downgraded to a Site Area Emergency,

c. The date, , and time,_ am/pm

. it occurred, and

d. A brief description of why:

Record the name of the individual contacted:

b. Nuclear Regulatory Commission NOTE: The initial notification should be made within one hour of declaring the emergency. If the red phone is unavailable, make the call via commercial phones using the number listed in Administrative Memorandum No. 37.

Record the name of individual contacted:

5. Ensure that the TED emergency response facilities are activated as per Step 6.5 NOTE: If upgrading from an Alert or downgrading from a General Emer-gency classification, these facilities should already be activated. In which case this step need not be performed.

6. Continue to assess the situation and ensure that personnel actions are in accordance with Section -

6.6, as applicable.

7. As conditions change, check .

EI 1300.01 to determine if reclassification is appropriate.

NOTE: If reclassification is not required, but the change was somewhat significant or unusual, an update should be made

. and documented on the Periodic Update Record, Attachment 3.

Attachment 2 Page 2 of 3 l 1 l

l

l 15 EI 1300.04.5 ED0/ SHIFT SUPERVISOR SITE AREA EMERGENCY CHECKLIST (Con't)

ACTION REQUIRED DATE TIME INITIALS

8. Proceed to EI 1300.03 or EI 1300.02 if the condition is downgraded to an Unusual Event.

9. If the emergency condition no longer exists:

a. Notify plant personnel as per Step 6.9.1,a.

b. Notify the Station Superin-tendent, as per Step 6.9.1.b.

c. Notify the State and County Emergency Operations Centers as per Step 6.9.1.c.

NOTE: The follow-up notification should state your name,

, that you are calling from the Davis-Besse Nuclear Power Station, and that the emer-gency condition no longer exists, with a brief des-cription why (e.g., high radiation levels in containment have subsided, etc.):

Record the name of the individual contacted:

10. If the classification is upgraded, proceed to EI 1300.05, General Emergency.

REVIEWED BY FILED BY Station Superintendent Emergency Planning Supv.

Date Date

.s Attachment 2 Page 3 of 3 l l

16 EI 1300.04.5 PERIODIC UPDATE RECORD A periodic update was provided for:

a. TED personnel at A.M./P.M. on (time) (date) concerning:

b. NRC at A.M./P.M. on (time) (date) concerning:

Name of individual contacted:

c. Ottawa County Sheriff / County EOC at A.M./P.M. on (time) (date) concerning:

Name of individual contacted:

A periodic update was provided for:

a. TED personnel at A.M./P.M. on (time) (date) concerning:

b. NRC at A.M./P.M. on (time) (date) concerning:

Name of individual contacted:

c. Ottawa County Sheriff / County EOC at A.M./P.M. on (time) (date) concerning:

Name of individual contacted:

a Attachment 3 ,

END Page 1 of I l l

l

EI 1300.05.0 Davis-Besse Nuclear Power Station Unit No. 1

• Emergency Plan Implementing Procedure EI 1300.05 General Emergency

• Record of Approval and Changes Prepared by G. J. Reed 5/30/80 Date Submitted by C. E. Wells 6/13/80 Section Head Date Recommended by '

Me h/

, SRB Chairmai 'Da te QA Approved //[8 ,

Qua'litf Assurance Manager Date Approved.by @>> w ' 8/$(/

Station Superintendent d Date Revision SRB QA Sta. Supt.

No. Reconnnenda tion Date Approved Date Approved Date

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. 1 EI 1300.05.5

1. PURPOSE To outline the course of action and protective measures required to mitigate the consequences of a station emergency at the General Emergency level in order to safeguard Station personnel and the general public.

2. REFERENCES 2.1 Davis-Besse Nuclear Power Station Emergency Plan 2.2 EI 1300.01, Emergency Plan Activation

3. DEFINITIONS General Emergency - Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting '

with the potential for loss of centainment integrity, and/or involve the potential release of radioactive particulates or gases offsite of a magnitude to exceed regulatory limits.

4. RESPONSIBILITIES The Emergency Duty Officer shall be responsible for the implementation of this procedure.

( NOTE: For a General Emergency, the Shif t Supervisor shall assume the role of the Emergency Duty Officer until the on-call Emergency Duty Officer relieves him of this func, tion. ,

5. INITIATING CONDITIONS 5.1 Whenever a General Emergency has been recognized and classified per EI 1300.01, Emergency Plan Activation.

S .,2 At the direction of the Emergency Duty Officer.

6. PROCEDURAL STEPS NOTE: Attachment 2 should be used to ensure that none of the following steps are overlooked.

6.1 Ensure the appropriate alarm are sounded as 'necessary:

6.1.1 Fire

~

6.1.2 Containment Evacuation 6.1.3 Initiate Emergency Procedures

, 6.2 Make the following announcement (s), not necessarily in this order:

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2 EI 1300.05.5 .

6.s.1 " Attention all personnel; attention all personnel: a t U, General Emergency has been declared. No eating, C smoking or drinking until further notice. All members i of the onsite emergency organization report to your  ;

designated. emergency response facilities. -All other personnel shall assemble at your designated assembly area and await further instructions."

6.2.2 If th'ere is a localized emergency (e.g. , fire),

announce its type and location and instruct personnel to stand clear of the area.

6.3 Notify.the following individuals:

6.3.1 Nuclear Security Supervisor .

6.3.2 SAS Operator, if offsite support is needed for fires or medical emergencies. .

6.3.3 Station Superintendent NOTE: If upgrading from a prior emergency classifica-tion, the Station Superintendent and Key Emergency Response Personnel should be contacted via the comununications channels between the emergency response facilities.

In which case, the following methodology can ]

be disregarded. '

1. During normal working hours, the Station Superintendent should be reached over the Station gai-tronics or J telephone or by utilizing his " beeper" pager in accordance with AD 1827.17, Emergency Call System. During off normal working hours, manually telephone i

his office'and home using the numbers i listed in Administrative tiemorandum No.

37. If there is no answer, then attempt a page.

2. Upon being notified, the Station Superintendent shall then confer with l the Shift Supervisor and ascertain the degree of response that may be necessitated by the plant event.

l

(- NOTE:

If the Station Superintendent does NOT respond within five minutes, re-initiate the page. If a second page fails, 1

3 EI 1300.05.5 the Assistant Station Super-intendent, Operations, should be contacted. In the event that neither can be contacted, the Shift Supervisor should exercise his own judgement in

. dealing with the situation.

3. The Station Superintendent can then authorize the Shift Supervisor to tape an announcement on the Telephone Pager located in the Shift Supervisor's office.

NOTE: The announcement should include: 1) the Emergency Classification, 2) the level of response required, and 3) a brief description of plant conditions.

6.3.4 Key Emergency Response Personnel

1. The Shift Supervisor er his designee shall then activate the pagers of the key emergency response personnel as listed in Administrative Memorandum No. 37 in accordance with AD 1827.17, Emergency Call System.

( 2. When paged (beeped), those individuals must telephone the Edison Operator who shall connect them with the Telephone Pager thus allowing then ,

to hear th? recorded message.

I

3. These individuals shall then notify additional personnel as required to provide adequate response

! to the event by using Administrative Memorandum No. 37.

~

NOTE: The NRC resident inspector should be notified by telephone if possible.

6.4 Notify the following agencies:

NOTE: When notifying an outside agency, record the time and the name of the individual contacted using Attachment 2 and request .a return telephone call from the agency to verify notification.

6.4.1 Sheriff's Department, Ottawa County This must be accomplished within 15 minutes of the emergency declaration. It can be performed by phone l using either the regular number or an unlisted number 1 s ,

1

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l . O li 4 EI 1300,05.5 provided for emergencies (both found in Admin. Memo ..

37) or, if necessary, by radio through CAS or SAS. ,

. NOTE. This notification should include your I. identification, the type of classification, j the date and time it was made, and a brief discription of the cause of the event.

6.4.2 NRC Region III, Office of Inspection and Enforcement; e NRC, Emergency Incident Response Center, Bethesda, l Maryland i

l This must be accomplished by the NRC Emergency Notifica-tion System - Red Phone or cosumercial phone within one

. hour of the emergency declaration.

6.5 Activate the following emergency response facilities:

NOTE: If upgrading from a prior emergency classification, the following facilities should already be activated.

In which case, the following steps can be disregarded.

6.5.1 The Operations Support Center as per EI 1300.06.

6.5.2 The Technical Support Center as per El 1300.07.

6.5.3 The Emergency Control Center as per EI 1300.08.

]

6.5.4 The Emergency Support Center as per the Corporate Radiological Emergency Plan. . ,

6.6 Access the situation by:

6.6.1 An increased amount of plant instrumentation shall be monitored, in particular, indications of core status (e.g., incore thermocouple readings, etc.) shall be monitored.

6.6.2 If a radiological accident is occurring, surveillance of the in plant instrumentation necessary to obtain meteorological and radiological data required for calculating or estimating projected doses. This dose

. assessment act iiv ty s ah ll continue until termination of the emergency in order that the updating of initial assessments may be provided to all concerned offsite agencies and to the EDO.

6.6.3 Greater emphasis on offsite monitoring efforts and dose projection efforts extending to distances much further from the plant. Additionally, since the projected ~ doses are likely'to be much closer to the q

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. . 5 Ei 1300.05.5 EPA PAG's, grester emphasis shall be placed on the assessment of release duration.

Dose assessment shall be in accordance with the Emergency Offsite Dose Estimates Procedure, AD 1827.10.

Protective action recommendations shall be made in accordance with AD 1827.12, Protective Action Guidelines.

NOTE: Additional information on personnel actions can be found in Attachment 1.

6.7 Revice EI 1300.01, Emergency Plan Activation, when plant conditions change to determine if the event should be reclassified.

_ , NOTE: If reclassification is not required but the change was somewhat significant or unusual, an update should be made and documented on the. Periodic Update Record, Attachment 3.

6.8 Proceed to either EI 1300.04, EI 1300.03 or EI 1300.02, as applicable, if the condition is downgraded. Annotate this on Attachment 2.

NOTE: Ensure that formal discussions are held with State and local officials prior to downgrading from a

(' General Emergency, since they may have valid concerns

% that need to be addressed prior to de-classification (els., field sample verification, plume still exists at elevated concentrations offsite, etc.). . ,

7. FINAL CONDITIONS The emergency condition has been downgraded to a Site Area Emergency, Alert or Unusucl Event classification.

8. ATTACHMENTS The following are attachments for use with this procedure:

1. Personnel Actions During a General Emergency

2. ED0/Shif t Supervisor General Emergency Checklist i 3. Periodic Update Record e*

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6 . EI 1300.05.5

),

l PERSONNEL ACTIONS DURING A GENERAL EMERGENCY On-call Emergency Duty Officer (EDO) l .

The on-call Emergency Duty Officer, upon being informed that an General Emergency has been declared, shall (if not previously accomplished):

1. Report to the Emergency Control Center and assume the position of Emergency Duty Officer in the onsite emergency organization, relieving the Shif t Supervisor of this duty.

2. Evaluate the information, data, and methods utilized by the Shift i Supervisor in making his determination in order to ensure that the proper emergency classification has been made.

3. Determine to what extent the onsite emergency organizations shall be activated,

a. For a General Emergency, the emergency teams and the entire onsite emergency organization shall be activated. All of the corporate emergency organization may be activated, as determined by the Emergency Director or the Corporate Radiological Emergency

, Response Plan.

! 4. Activate the ECC according to EI 1300.08, the Emergency control j '

Center Activation procedure. ,

5. Continue assessment actions initiated by the Shift Supervisor. )

6. Confer with the Emergency Operations Manager concerning distribution of a thyroid blocking agent to those TED emergency workers involved in the Station response as specified in AD 1827.12, Protective Action Guidelines.

7. Recommend protective actions to the Ottawa County Sheriff as required by assessment results per AD 1827.12, Protective Action Guidelines.

TSC Manaser The TSC Manager, upon being informed that a General Emergency has been declared, shall:

1. Report to the Technical Support Center and assume the role of TSC Manager in the onsite emergency organization.

2. Perform the steps as outlined in EI 1300.07, Technical Support Center Activation.

OSC Manaaer j The OSC Manager, upon being informed th'at a General Emergne y has been l i

declared, shall: 3: l Q: '

Attachment 1 Page 1 of 5  ;

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7 EI 1300.05.5

\

1. R'e port to the Operations Support Center and assume the position of OSC Manager in the onsite emergency organization.

2. Perform the steps as outlined in EI 1300.06, Operations Support Center Activation.

Plant Operations Manaaer The Plant Operations Manager, upon being informed that a General Emergnecy i has been declared, shall

I.

j 1. Report to the Control Room and assume the position of Plant Operations

Manager in the onsite emergency organization.

l 2. Perform the steps as outlined in EI 1300.00, Station Response to Emergencies.

Shift Operations Personnel '

1. Control Room operators shall maintain safe operations on the Station and minimize the potential hazards to Station personnel and the general public as directed by the Shift Supervisor.

2. In the event that the Shift Supervisor i, incapacitated, his duties and responsibilities shall be assumed by the Assistant Shift Supervisor

in the Control Roos until relieved by a qualified Shift Supervisor.

3. Equipment and auxiliaries operators shall maintain safe operations of the plant as directed by the Shift Supervisor.

4. The Shift Technical Advisor (STA) shall provide technical and analytical support in the diagnosis of off-normal events. He shall also advise i and assist the Shift Supervisor on matters pertaining to the safe and proper operation of the plant with regards to nuclear safety.

Shif t Chemistry and Radiation Test (C&RT) l i

1. The shift C&RT shall report immediately to the Health Physics Monitoring Room to await instructions from the Shift Supervisor or Chemist and Health Physicist.

2. If a radiological injury is involved, the C&RT should monitor the injured personnel for contamination. Howe <er, if plant conditions are in a state where the C&RT can help prevent releases from the station or exposures to individuals in the station, the C&RT should respond to assist there. , ,

3. An off-shift C&RT should accompany or meet a contaminated person at the offsite medical facility.

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Attac'hment 1 Page 2 of 5

,,w--, - - _ _ , _ . , - . , , , . 7 _ _. . . . - _ , , . , r.--- . .

8 El 1300.05.5

4. When an accident invilves increasing radioactivity in the reactor a

. coolant system as indicated from the radiation monitoring syster, t ~5):

! the C&RT should perform the purge portion for collecting a reactor coolant sample.

Fire Briande -

1. The Fire Brigade Captain shall respond to any announded fire, evaluate the situation, direct the Fire Brigade, and keep the Shift Supervisor informed of the status of the fire.

2. Personnel assigned to the Fire Brigade shall respond to any announced fire with appropriate fire fighting and protective equipment and extinguish the fire as directed by the Fire Brigade Captain.

3. The first Fire Brigade Captain arriving on the scene should remain in charge of the fire until termination of the emergency or relieved by

the Station Fire Chief or Assistant Fire Chief.

4. When local fire support is required within the Protected Area, local fire department personnel will function in conjunction with, and under the direction of the DBNPS Fire Brigade.

First Aid Team

1. The First Aid Team Leader shall respond to any announced personnel injuries, evaluate the situation, direct the First Aid Team and keep ]

! the Shift Supervisor informed of the status of the injured individual (s). .)

2. Personnel assigned to the First Aid Team shall respond to any announced ,

personnel injury with appropriate first aid supplies and provide the necessary first aid treatment.

Nuclear Security Force

1. The Nuclear Security Supervisor, upon notification by the Shift Supervisor that a General Emergency Exists, shall implement AD 1808.00 i

the Industrial Security Plan Procedure.

2. Nuclear Security Officers shall maintain security of the Station as directed by the Nuclear Security Supervisor.

Radiation Monitorina Team (RMT)

1. All qualified non-chemistry and health physics RMT members will report to the turbine deck assembly area.

2. The OSC Manager will designate RMT members as to their assignment

- ofisite or onsite.

a. A list of qualified RMT's is found in Adminsitrative Memo 42.

?

I Attachment 1 l' Page 3 of 5 l

7 .- -

9 EI 1300.05.5 *

b. Only one member of each team should be from the C&HP section.

3. If requested by the EDO, offsite RMT's will be dispatched to the Radiological Testing Laboratory (RTL) for further instructions.

4. RMT's responding from offsite will report to the RTL for further assignment.

Onsite Personnel Personnel, who do NOT have specifically assigned duties shall proceed to areas as prescribed in AD 1827.11 Assembly, Accountability, and Subsequent Evacuation.

Offsite Station Personnel

1. Station personnel whose emergency response is at the station will be admitted upon verbal communication with security. These personnel should report to their emergency assembly area (as designated by AD 1827.11) for assignment.

2. Station personnel whose emergency response is in the DBAB will report to their designated location.

3. Non-badged personnel will report to the location designated by this

/ contact according to the severity of the emergency (ie DBAB, PPF, or

\ ESC). Normal badging procedures will be utilized if it becomes necessary for these personnel to enter the station.

Offsite Agencies and Organizations

1. The Carroll Township Ambulance Service shall provide transportation service as required for offsite medical treatment.

2. The H.B. Magruder Memorial Hospital and St. Charles Hospital shall provide offsite medical treatment for personnel as required.

3. The Carroll Township Fire Department shall provide primary response to fire alarms onsite as required.

a. The Village of Oak Harbor Fire Department shall provide alternate response to fire alarms onsite as required through mutual aid with Carroll Township.  ;

4. The Ottawa County Sheriff's Department ,is experienced in providing area control, communications assistance, and direct handling of the local population, including evacuation, should it become necessary.

The Sheriff's Department provides 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> radio communication coverage with the Shift Supervisor at DBNPS and is the lead offsite governmental agency contacted in the event of an emergency at the site.

(

l Attachment 1 i Page 4 of 5 '

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10 EI 1300.04.5

5. Engineering firms (e.g., Babcock and Wilcox, Bechtel, etc.) may be -

.l; :

requested to respond to provide additional engineering capabilities.

6. Mutual aid utilities may provide additional support of personnel or equipment as available.

7. Other support organizations may be contacted as identified in EI 1300.08.

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Attachment 1 Page 5 of 5

11 EI 1300.05.5 9

EDO/ SHIFT SUPERVISOR GENERAL EMERGENCY CHECKLIST I

ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS

1. Sound the appropriate alarm as per Step 6.1.

2. Notify plant personnel as per Step 6.2.

3. Notify the following personnel"

a. Nuclear Security Supervisor (Ext. 556 or 557) 1

b. In the event of a fire or medical emergency, notify the SAS Operator who will notify the Ottawa County Sheriff's Department, who in turn notifies the appropriate response agencies.

l 1

c. Station Superintendent l (as per Step 6.3.2) j 1

d. Key Emergency Response Personnel (as per Steps 6.3.2 and 6.3.3)

4. Notify the following agencies:

a. Ottawa County Sheriff's Dept.

(as per Step 6.4.1) t NOTE: The initial notification should be made within 15 minutes of declaring the emergency. The initial notification message should include:

a. Your name, , and that you are calling from the Davis-Besse Nuclear Power Station,

b. The type of classification, General Emergency,

c. The date, , and time, am/pm it was made, and

d. A brief description of the event (e.g., reactor core damage with a potential for a release of radiation, etc.):

Record the name of individual contacted:

Then request a return (verification) telephone call.

Time received: as/pm l Attachment 2 l Page 1 of 3 1

l 12 EI 1300.05.5 j ED0/ SHIFT SUPERVISOR GENERAL EMERGENCY CHECKLIST (Con't)

ACTION REQUIRED DATE TIME INITIALS

b. Nuclear Regulatory Commission l

(ENS-Red Phone)

NOTE: The initial notification should be made within one hour of declaring the emergency. If the red phone is unavailable, make the call via commercial phones using the number listed in Administrative Memorandum No. 37.

Record the name of individual contacted:

5. Ensure that the TED emer-gency response facilities are activated as per Step 6.5 NOTE: If upgrading from a prior emergency classification, these facilities should already be activated. In which case this .

step need not be performed.

6. Continue to assess the situation I

and ensure that personnel actions are in accordance with Section 6.5, as applicable.

7. As conditions change, check EI 1300.01 to determine if ~

reclassification is appropriate.

NOTE: If reclassification is not required, but the change was somewhat significant or unusual, an update should be made and documented on the Periodic Update Record, Attachment 3.

8. If the classification is downgraded, pr'oceed to the next Implementing Procedure checklist, as per EI 1300.01.

NOTE: Ensure that formal discussions are held with State and local officials prior to downgrading from a General Emergency, since they may have valid concerns that'need to be addressed prior to de-classification.

REVIEWED BY FILED BY Station Superintendent Emergency Planning Supv.

i Date Date

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Attachment 2 Page 2 of 2 y _.

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.. .. .-. .: ~ -. . . . .. .. - . . . . . . - . . . ~ . - - . . - - . . . - - - -

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, 13 EI 1300.05.5 l PERIODIC UPDATE RECORD .

l l A periodic update was provided for:

a. TED personnel at A.M./P.M. on (time) (date) concerning:

b. NRC a t A.M./P.M. on I

(time) (date) concerning:

Name of individual contacted:

c. Ottawa County Sheriff / County EOC at A.M./P.h. on (time) (date) concerning:

l Name of individual contacted:

A periodic update was provided for:

' t

a. TED personnel at A.M./P.M. on (time) (date) concerning:

b. NRC at A.M./P.M. on (time) (date) concerning:

Name of individual contacted:

c. Ottawa County Sheriff / County EOC at A.M./P.M. on (time) (date) concerning:

Name of individual contacted:

Attachment 3 END Page 1 of 1

. '{ ,

EI 1340.08.0 Davis-Besse Nuclear Power Station Unit No, 1 Emergency Plan Implementing Procedure EI 1300.08 Emergency Control Center Activation ,

Record of Approval and Changes Prepared by G. J. Reed 5/30/80 Date Submitted by C. E. Wells _ 6/13/80 Section Head Date Recommended by MN SR3 Chairma (

b /)

~ Da te' QA Approved [8 ,

Quality Assurance Manager Date Approved.by W / 8/N Station StTperintendent

( Date Revision SRB No.

QA Sta. Supt.

Recommendation Date Approved Date A proved Date

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1 EI 1300.08.7 ,

1. PURPOSE To outline the steps required for activation and operation of the Emergency Control Center (ECC). _. .

2. REFEIULNCES 2.1 Davis-Besse Nuclear Power Station Emergency Plan l 2.2 EI 1300.03, Alert I 2.3 EI 1300.04, Site Area Emergency 2.4 EI 1300.05, General Emergency

2. DEFINITIONS Emergency Control Center (ECC) - A specifically designated location which is equipped to facilitate the control and coordination of emergency activities and assessments.

4. RESPONSIBILITIES 4.1 The Emergency Duty Officer (EDO) shall be responsible for the implementation of this procedure.

4.2 The Emergency Operations Manager shall oversee the activities of the Emergency Control Center and provide coordination of short term community assistance activities and response to the i needs of the local government officials.

NOTE: The Emergency Operations Manager is responsible for keeping the Operations Director informed of emergency operations and community assistance matters.

S. INITIATING CONDITIONS 5.1 Any of the following emergencies has been declared; Alert, Site Area Emergency, or General Emergency. -

5.2 As determined by the Shift Supervisor or Emergency Duty Officer.

6. PROCEDURAL STEPS NOTE: Attachment 8 should be used to ensure that none of the following steps are overlooked.

6.1 Ensure the following individuals arrive at the ECC and the Radiological Testing Laboratory (RTL) as needed:

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2 EI 1300.08.7 .

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6.1.1 Communications personnel, including: ()

a. Control Room Communicator

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b. State and County Communicator

c. Corporate Management Communicator

d. Public Relations Communicator

,e. Nuclear Regulatory Commission Communicator

f. Radiation Monitoring Team Communicator and Coordinator

g. Community Assistance Communicator _

h. Radiological Testing Laboratory Communicator 6.1.2 Radiation Monitoring Teams 6.1.3 Emergency Operations Manager 6.1.4 Emergency Planning Supervisor 6.2 Set up the ECC (1st floor north end of the Davis-Besse Admiristra-tion Building) as shown in Attachment 1, including the following , -)

steps:

NOTE: This may be modified if equipment locations or work  ;

areas are found to be unsatisfactory.

6.2.1 Request to the Technical Support Center that part or all of the telephone communications loops be established.

6.2.2 Assign an individual (s) to set-up necessary emergency equipment located in the ECC and Radiological Testing Lab. ,

6.2.3 Direct that the ventilation system for the DBAB be placed in the position or incident mode if iodine levels exceed MPC (9 x 10-8 pCi/al) as recommended by the Radeon Operations Manager.

6.2.4 Establish a dose assessment team to perform dose calculations and dose assessment per AD 1827.10 , and to operate the CRT terminal for the Data Aquisition and Display System. l NOTE: Ensure that total population accumulated exposure is calculated.

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. 3 EI 1300.08.7 ,,

6.2.5 Verify that the Shift Supervisor has requested the post accident sampling procedure AD 1850.04 be put in service as per the Radeon Operations Manager.

. , . 6 6.3 Request EDO Turnover Data from the Shif t Supervisor as per Attachment 2.

NOTE

Review the turnover data with all personnel in the ECC.

6.3.1 Inform the Control Room that the ECC is manned and operational, and formally relieve the Shift Supervisor of the EDO function.

6.3.2 Inform the TSC Manager that the EDO function has shifted from the Control Room to the ECC. _

6.3.3 Perform the applicable steps of the ED0/ Shift Supervisor Checklist in either EI 1300.03 (Alert), EI 1300.04 (Site Area), or EI 1300.05 (General) depending on the action level of the event.

6.4 Determine to what extent the casite emergency organization shall be activated.

NOTE: The Corporate organization will be activated as determined by the Emergency Director or the Corporate Radiological Emergency Response Plan.

6.4.1 The Emergency Organization response to emergencies is .

shown in Attachment 3.

6.4.2 The Emergency Organization is shown in Attachments 4 and 5.

6.4.3 Direct the activation of additional personnel or groups as deemed necessary.

6.5 Recommend protective actions when necessary, for the plume exposure pathway (10 mile EPZ) to the State and County Disaster Services Agencies per AD 1827.12, Protective Action Guidelines, and: )

6.5.1 Make recommendations for protective actions for l Station personnel in coordination with and as recommended by the Shift Supervisor sad /or the TSC Manager.

6.5.2 Ensure that. reconsendations are made, when necessary, for the ingestion exposure pathway (50 mile EPZ) by the Emergency Operations Manager as per AD 1827.12 to

, the cognizant agencies of the States of Ohio and Michigan.

4 EI 1300.08.7 NOTE: Any recommendations that need to be made to Canada should be disseminated by the NRC through appropriate channels.

6.6 Inform Federal, State and Local officials of the affected areas by sector and zone designators as shown on Attachment 7.

6.7 Ensure that Attachment 6 is completed correctly and supplied to the State and County Disaster Services Agencies.

6.7.1 This shall be accomplished as soon as possible after the ECC is declared operational.

6.7.2 Updates to Attachment 6 shall be supplied on a timely basis as requested by the State and County Disaster Services Agencies. ..

6.8 Distribute potassium iodide to station personnel as per AD 1827.12 and to RMT's as per AD 1850.05.

6.9 Utilize the Emergency Planning Supervisor for coordinating ECC activities.

6.9.1 The Emergency Planning Supervisor's responsibilities and duties include, but are NOT limited to:

a. Reporting to the Emergency Operations Manager and appraising him of emergency response activities.

i

b. Consulting with and providing assistance to the EDO.

c. Providing guidance needed to coordinate the

. various emergency response activities.

d. Ensuring contact is made as required to the following agencies (phone numbers are found in Administrative Memorandum No. 37):

• 1. Institute of Nuclear Power Operations (INPO)

2. REMS Corporation

• 3. American Nuclear Insurers (ANI)

4. Federal Bureau of Investigation

5. State of Michigan

6. Department of Energy (IRAP)

7. Consumer's Power Company

8. Detroit Edison. Company

9. Cleveland Electric Illuminating Co.

10. Cincinnati Gas and Electric Co. ,

i

• May be notified at the Alert level or above as per agreement with these organizations. .

\ - - . -

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l 5 EI 1300.08.7 ,

6.9.2 Refer to Administrative Memorandum No. 37, Attachment 2, for additional ECC support personnel / communicators.

l l

6.10 Designate a Radiation Monitoring Team (RMT) Coordinator - _ .

Assigned from the pool of off-duty ED0's. This individual should:

6.10.1 Coordinate, from the ECC, the activities of the offsite RMT's.

6.10.2 Dispatches RMT's as directed by the EDO.

6.10.3 Maintains map of RNT sample points and results of samples.

6.10.4 Ensures the EDO is informed of sample results. _

6.11 Ensure the Radiation Monitoring Teams respond as follows:

6.11.1 The first RMT to arrive at the RTL shall perform the functions listed below:

a. Inform the EDO that the RTL is manned.

b. Using appropriate survey instruments, survey the immediate areas surrounding the ECC and TSC.

c. Standby with a Radiation Monitoring Team Kit and Protective Clothing Kit. Protective clothing to be used as directed.

d. Check out equipment for operability.

e. Perform surveys offsite as directed by the RMT Coordinator and in accordance with AD 1850.05.

6.11.2 Other RNI's that arrive at the RTL:

a. During normal working hours:

1. Standby with a Radiaton Monitoring Team Kit and Protective Clothing Kit to be used as directed.

2. Check out equipment for operability.

3. Perform surveys offsite as directed by the RMT Coordinator.

b. During off-normal working hours:

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'6 EI 1300.08.7 '

1. If not needed as an offsite RMT (as deter-mined by RMT Coordinator), assignment as onsite RMT's to the Radeon Operations Manager (at the Technical Support Center) or '

the Shift Supervisor (if the TSC is not as yet manned) will be made by the RMT Coordinator

after it is assured that additional aid is needed onsite.

6.12 Designate a Radiation Testing Laboratory (RTL) Coordinator 6.12.1 The RTL Coordinator is the first management individual (assigned by the Radeon Operations Manager) to arrive at the RTL, who is not part of the RMT response.

6.12.2 Ensures RNT equipment is removed from the cabinets and made ready for use. ~

6.12.3 Coordinates the overall activities of the RTL.

6.12.4 Reports all R!ff sample results to the RMT Coordinator.

l 6.13 Perform measures to activate an alternate ECC if the normal ECC l

becomes uninhibitable for any reason.

NOTE: The ECC emergency support staff will be located at a q suitable position as close to the Control Room or l" )

site as possible. Communications will be established by telephone, messenger, telecopier, etc. between ,

emergency support personnel and the Control Room.

Also, communications will be established at least by telephone or messenger between the relocated ECC and the TSC.

6.14 Maintain a record of activities of the ECC and the RTL.

NOTE: All records should be forwarded to the Emergency Planning Supervisor following deactivation of the ECC.

6.15 Deactivate the ECC and RTL when conditions warrant, including:

NOTE: A joint concurrence for deactivation by the Emergency Duty Officer, Emergency Operations Manager, an'd Shift Supervisor should be reached when the continuous dose assessment and protective action functions are no longer necessary to respond to the indicated plant

,. conditions.

L i 6.15.1 Replace all equipment and supplies to their specified j j storage locations in both the ECC and RTL.

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7 EI 1300.08.7 ,

6.15.2 De-energize electrical equipment as required.

7. FINAL CONDITIONS

^~

7.1 All records generated during the operation of the ECC and RTL have been forwarded to the Emergency Planning Supervisor.

7.2 All equipesnt and still useable supplies have been returned to their normal storage location.

7.3 The entire ECC and RTL staff have been relieved of all duties associated with the operation of the ECC and RTL.

8. ATTACHMENTS The following are attachments for use with this procedure: _

1. Emergency Control Center Floor Plan

2. EDO Turnover Data Sheet

3. Manpower, Location and Response Considerations for Emergencies

4. Onsite Emergency Organization

5. Corporate Emergency Organization

6. Essential Information Sheet ,

7. Sector and Zone Designators for Emergency Planning Zones

8. ECC Checklist b

1

1 8 EI 1300.08.7 -

. DAVIS-BESSE NUCLEAR P0hT.R STATION Emergency Control Center

.. 4 N~ '

EMERcENcr TED DUTY DOSE ASSESSMENT OFFIpER TEp Em:acENcT ,

OPERATIONS l .

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I - RMT g _ l q00RDINATOR u_ , o- - - -- J

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b.

1 Attachment 1 i Page 1 of 1 l

s e 9 EI 1300.08.7 .

EDO Turnover Data Sheet .

Emergency Classification: Unusual Event Site Area Emergency (circle one) Alert General Emergency ,,

Event

Description:

Time Event Started:

Equipment Problems:

Instrumentation Problems:

Electrical Problems:

Relesse in -

i Progress or Expected (Monitored or Unmonitored):

NOTE: For a monitored release, obtain dose assessment data from the DADS. For an unmonitored release, consider RMT survey results, C&RT grab sample results or Containment radiation levels for inputs into dose assessment calculations or as a basis for the determination of protective actions.

Sectors / Zones Involved:

Whole Body -

ar/hr at Dose (Projected Value): miles Thyroid Dose ar/hr at (Projected Value): miles Attachment 2 Page 1 of 2

_ -. --4 ,9 y

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10 EI 1300.08.7 .

EDO Turnover Data Sheet RMT's __

Activated: .. .

Protective Actions Taken Onsite:

Recommendations Made to Offsite Officials:

EI Procedure

, up to and including

• step in use:

Emergency Facilities OSC: Yes O wo _

That Have TSC: Yes No Been Activated: County EOC Yes No State 20C Yes O No NRC IRC O res O No NOTE: Place n/a (not applicable) in those spaces where no actions are being taken or no events have occurred. ..)

./

.:J Attachment 2 Page 2 of 2 l

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1 11 EI 1300.08.7

• MANPOWER, LOCATION AND RESPONSE CONSIDERATIONS FOR EMERGENCIES j

UNUSUAL EVENT ALERT PERSONNEL TIME PERSONNEL TIME CONTROL ROOM CONTROL ROOM l Shift Supervisor (1) Isssediately Shift Supervisor (1) Immediately ,_

(Interim EDO) (Interim EDO)

Asst Shift Supervisor (1) Asst Shift Supervisor (1)

Control Room Opr (1) . Control Room Opr (1)

Shift Tech Advisor (1) Shift Tech Advisor (1)

Hee:11stetsd.9er!____.121. . _ _ _ _ _ _ _ _ _ _ _ ,

ggg:lissensg_gera,____121. _____________

Plant Ops Mage (1) Alerted Plant Oprs Magr (1) Normal Hrs Opus Engr (1) Opus Engr (1) 30 min Opna Supvr/ Ops (1) Opus Supvr/ Ops (1) Off Hrs Enar Supvr Enar Supvr 60 min

. OPNS SUPPORT CENTER

• OPNS SUPPORT CENTER

• First Aid (1) As required First Aid (1) As required:

Fire Brigade (5) Immediately Fire Breigade (5) Imsediately --

C_9 Bed Is!tsr..______Ill. . . _ _ _ _ _ _ . . . . .C_g,geg_Issegr_____,__Il}_ _____________

OSC Magr (1) Alerted OSC Mngr (1) Normal Hrs 30 min; Off Hrs-60 min TECH SUPPORT CENTER TECH SUPPORT CENTER Station Ops Mngr Alerted Station Ops Magr (1) As requiredt m Technical Enge Consunicator (1) Normal Hrs h Radeon Ops Mngr Plan ~. Staff (Var) 30 min g Technical Engr (1) Off Mrs Radcon Ops Manager (1) 60 min TSC Manager (1)

I&C Sys Engr (1) 1-2 hours Nuc Sys & Anal Engr (1)

Other NRC Personnel Variable EMERG CONTROL CENTER EMERG CONTROL CENTER Emerg Ops Mngr Alerted Emerg Duty Officer (1) As required:

Emerg Duty Officer (Re1 Shift Supvr) Normal Hrs Emerg Plan Supervisor NRC Communicator (1) 30 min State Communicator (1) Off Hrs Public Relations (1) 60 min County Communicator (1)

Corporate Mgt. Comm. (1)

Emerg Plan Supervisor (1) ,

Emera Ops Mnar (1) 1-2 hours EMERG SUPPORT CENTER EMERG SUPPORT CENTER g Ops Director Alerted Ops Director As required: ,

y Emerg Director Emerg Director 1-2 hours g Public Information Public Info Director o ..___...______..____________...__......

, Staff Alerted Variable

• Includes the Health Physics Monitoring Room NOTE: All time requirements are based

• • May respond to the Davis-Besse Admin. Bldg. on optimum response conditions.

Attachment 3 Page 1 of 2

12 EI 1300.08.7' MANPOWER, LOCATION AND RESPONSE CONSIDERATIONS FOR Eh"3tGENCIES (Con't.) Q.

• SITE AREA EMERGENCY GENERAL EMERGENCY  : .3/

PERSONNEL TIME PERSONNEL TIME CONTROL ROOM CONTROL ROOM Shift Supervisor (1) Immediately Shift Supervisor (1) 'Immediately

(Interim EDO) (Interim EDO)

Asst Shift Supervisor (1) Asst Shift Supervisor (1)

Control Room Opr (1) Control Room Opr (1)

Shift Tech Advisor (1) Shift Tech Advisor (1)

Hee:listetsg_9er!.___I21. . _ _ _ _ _ _ _ _ _ _ _ .

Hee:11ssensg_9 era _____I2}, ,,,,,__,,,,,,

Plant Ops Maar (1) Normal Hrs Plant Ops Mngr (1) Normal Ers Opus Engr . (1) 30 min Opas Enge (1) 30 min Opus Supvr/ Ops (1) Off Hrs Opas Supvr/ Ops (1) Off Mrs Enar Supve 60 min Enar Super 60 min OPNS SUPPORT CENTER

• OPNS SUPPORT CENTER

• First Aid (1) As required First Aid (1)

Fire Brigade (5) Immediately Fire Brigade (5) Immediately ..

9_B_Rgg,Iggtgg,,,,,,,,{, ,,,,,,,,,,,,u g,g_ggg_ Igg tgg,,,,,,,,{} }, ,,,,,,,,,,__, OSC Mage (1) Normal Mrs OSC Magr (1) Normal Hrs 30 min; Off 30 min; Off Mrs-60 min Mrs-60 min

        -TECH SUPPORT CENTER                                           TECH SUPPORT CENTER Station Ops Magr             (1) As required Station Ops Mage                                 (1)

Communicator (1) Normal Hrs Communicator (1) Normal Hrs

     %   Plant  StaTf           (Var)           30    min               Plant  Staff                (Var)         30 min G Technical Enge                  (1) Off Mrs                      Technical Enge                 (1) Off Mrs                                    3 E Radeon Ops Magr                 (1) 60 min                       Radeon Ops Mage                (1) 60 min                                    ~
                                                                                                                                                          ;/

18C_Uteessr__________111. .___________. ISC_Useessr___________fil. _____________ I&C Sys Enge (1) 1-2 hours I&C Sys Engr - (1) 1-2 hours i

         !ss_825 B_^ eel _lest___I11. ____________.                     !ss_S!!.B_6 eel _ fear.__111. _____________

Other NRC Personnel Variable Other NRC Personnel Variable EMERG CONTROL CENTER EMERG CONTROL CENTER Emers Duty Officer (1) Emerg Duty Officer (1) (Rel Shift Supvr) Normal Hrs (Rel Shift Supvr) Normal Hrs NRC Communicator (1) 30 min NRC Communicator (1) 30 min State Communicator (1) Off Mrs State Communicator (1) Off Hrs Public Relations (1) 60 min Public Relations (1) 60 min County Communicator (1) County Communicator (1) Corporate Mgt Comm (1) Corporate Mgt Conus (1) Rffra (8) Rffrs (8) Plant Staff (Var) Plant Staff (Var)

          !=sts.Plgg,Sggy5,,_,,,{}}          _,,,,,,,,,,,,
                                                                       ,gaggg,Plgg,Sggyg,,,,,,{}},               ,,,,,,,,,,,,,

Emerg Ops Magr (1) 1-2 hours Emerg Ops Mnge (1) 1-2 hours Public Relations (1) Public Relations (1) EMERG SUPPORT CENTER EMERG SUPPORT CENTER

      $ Ops Director                              1-2 hours              Emerg Director                   (1)       1-2 hours
                                                  **                     Ops Director                      (1)     **

G Emers Director

                                                                       ,gg,jg{g,Digggtgg,,,,,{1L,_,,,,,,,,,,
      $ hh_ Isle _Digggtgg,,,,,___ _,,_,,,,,,,,,

Staff Mobilized Variable Staff Personnel 60 min

• Includes the Health Physics Monitoring Room NOTE: All time requirements are based..

   **May respond to Davis-Besse Admin. Bldg.                                          on optimum response conditions (p J

Attachment 3 Page 2 of 2

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• 13 EI 1300.08.7

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16 EI 1300.08.7 * . DAVIS-BESSE NUCLEAR POWER STATION -: Emergency Nuclear Incident Essential Information Sheet Date Time: Sheet No.: Part I: A. ,

Classification of incident B.  : Time release started or is expected to start C. to the  : Wind direction D. s/sec.: Wind speed E. Ci/sec: Noble gas release rate F. Ci/sec.: Radioiodine release rate G. _

Stability Class H.  : Expected duration of release I. ar/hr @ miles.: field monitoring reading pei/cc @ siles: I-131 field survey

i _ Location ar/hr @ miles: field monitoring reading c pei/cc @ miles: I-131 field survey Location ar/hr @ miles: field monitoring reading pci/cc @ miles: I-131 field survey Location Attachment 6 Page.1 of 2

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17 11 1300.08.7 , DAVIS-RESSE NUCLEAR POWER STATION Emersency Nuclear Incident Essential Information Sheet (con't) ,, , Part II: A. Sector (s)/ Zone (s) are involved B. ar/hr 9 miles: whole body dose (pro-jected value) er/hr @ miles: thyroid dose (projected value) NOTE: Before acting upon the above information, reverify ~ the information and ensure that all assumptions being made are known by the utility, State and local officials. C.

Facility recommendations (stay inside or evacuate / distance)

D.  : Weather conditions (precipitation) Part III: A. . l l

Plant condition B.

Cause of incident NOTE: When disseminating information during an actual event, if a space is skipped, insert "W/F" or "N/A" to indicate that there has NOT been a mis-take and that the information will be forwarded as soon as possible.

W/F = will follow N/A = not applicable

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9 Attachment 6 Page 2 of 2

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• e 18 EI 1300.08.7
• Sector and Zone Designators for .a9 Emergency Planning Zones Sector Nomenclature Zone Nomenclature ~~~ *

Sector in Degrees True 22 1/2* Miles from North from Facility Sector Facility - Zone 348.75* to 11.25* A 0-1 1 11.25' to 33.75* B 1-2 2 33.75* to 56.25' C 2-3 3 56.25' to 78.75* D' 3-4 4 78.75* to 101.25' C 4-5 5 101.25' to 123.75* F 5-6 6 123.75* to 146.25' G 6-7 7 146.25' to 168.75* H 7-8 8 168.75* to 191.25' J 8-9 9 191.25* to 213,75* K 9-10 10 213.75* to 236.25' L 10-15 15 236.25* to 258.75* M 15-20 20 258.75* to 281.25' N 20-25 25 281.25* to 303.75* P 25-30 30 303.75* to 326.25* Q 30-35 35 326.25* to 348.75* R 35-40 40 40-45 45 45-50 50 J

AREA SEGMENT - An area is identified by a Sector and zone designator. . EXAMPLE - Area F4 is that area which lies between 101.25* to 123.75* ' true north from the facility and between 3 and 4 miles o'ut from the facility. l l i 9 I s Attachment 7 Page 1 of 3 I .

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1 s 4 i e 21 EI 1300.08.7 - ECC CHECKLIST , ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS 4 l

1. Ensure that applicable individuals arrive at the ECC as per Step 6.1.

2. Set up the ECC and associated i systems as per Step 6.2.

a. As needed, request the TSC establish any or all of the emergency telephone communications

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b. Assign an individual (s) to set up necessary equipment.

c. Direct DBAB ventilation be shifted to the positive mode ,

if iodine levels exceed MPC.

d. Establish a dose assessment team. -  :

e. Verify that the Shift Super-visor has requested post accident sampling procedure -

AD 1850.04 implemented as per the Radcon Operations Manager.

3. Fill out the EDO Turnover Data )

Sheet (Attachment 2) as per Step 6.3.

a. Inform the Control Room that the ECC is manned and operational.

b. Formally relieve the Shift Supervisor of the EDO Function.

c. Inform the TSC Manager that the EDO function has shifted to the ECC.

d. Perform applicable steps of the .

ED0/S,hift Supervisor Checklist in either EI 1300.03 (Alert), EI 1300.04 (Site Area), or EI 1300.05 (General) depending on the action level of the event. l Attachment 8 Page 1 of 3 m y - e

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I ACTION COMPLETED ACTION REQUIRED DATE TIME INITIALS

4. Determite to what extent the onsite " '

emergency organization shall be activated and direct the activation of additional personnel as deemed necessary per Step 6.4

5. Evaluate what protective actions should be taken onsite and recommended offsite as per Step 6.5.

6. Ensure offsite officials are notified i of the affected sectors as per Step 6.6 ,

7. Complete the Essential Information Sheet (Attachment 6) and release to the State and County Emergency Operations Center as per Step 6.7.

8. Distribute potassium iodide as per Step 6.8 if necessary.

9. Utilize the Emergency Planning s, Supervisor for coordinating ECC activities and supplementary notifications as per Step 6.9.

10. Designate a RMT Coordinator as per Step 6.10.

11. Ensure that RMT's respond as per Step 6.11.

12. Designate an RTL Coordinator as per Step 6.12.

13. Activate an alternate ECC if required per Step 6.13. __

14. Maintain a record of activities as per Step 6.14.

15. Deactivate the ECC and RTL -

as per Step 6.15. i NOTE: Place N/A (not applicable) in those steps (e.g. , activation ) of an alternate ECC, No. 13 above), which are not necessary I for adequate response to the event situation that the ECC N ., has been activated for. y Attachment 8 , Page 2 of 3 i

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a s; a t 23 EI 1300.08.7

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'l ( REVIEW.D BY FILED BY " ' Station Superintendent Emergency Planning Sapv. i Date Date 1 1 k a k i i-1 I i i, - e f t- ,1 e i I l b 1

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             ..P Attachment 8                                      l J

END Page 3 of 3

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1 EI 1300.10.0 ) Davia-Besse Nuclear Power Station Unit No. 1 Emergency Plan Implementing Procedure EI 1300.10

                                              .                   Reentry                                          .

Record of Approval and Changes Prepared by G. J. Reed 5/30/80 Date Submitted by C. E. Wells 6/13/80 Section Head Date Recommended by /4/h P /3

                                                ' SRB Qiairmati                                             bati QA Approved Quality' Assurance Manager                                      Date                      '

Approved by s _m 7[/ 5>/cif) Station Superintendent g Date Revision SRB QA Sta. Supt. No. Recommendation Date Approved Date Approved Date l p 4l21/31 /1A $ Y , 3 n2 .pn pt M9pedW'a-i i, - 4 i i i h , 't 1

I a s 1 l l 1 EI 1300.10.2

 ,    1. PURPOSE To outline a course of action and the protective measures required for reentry into affected plant areas for the purposes of emergency repair to systems and, equipment or investigative asser.inent of abnormal plant conditions.

NOTES: 1. Guidelines for reentries necessary to locate missing personnel can be found in AD 1827.16, Search and Rescue.

2. State and local agencies will coordinate any reentry efforts required offsite following emergencies in which evacuation was bsplemented as a protective action.

2. REFERENCES 2.1 Davis-Besse Nuclear Power Statica Emergency Plan 2.2 TED Corporate Radiological Emergency Response (CRER) Plan

3. DEFINITION Affected Plant Access - Areas in the plant that had been indicated to be a source of, or had been evacuated or closed to personnel access because of an emergency situation.

4. RESPONSIBILITIES .

4.1 The OSC Hanager shall be responsible for the implementation of this. procedure. 4.2 The Station Operations Manager, under the direction of the Operations Director, shall be responsible at the site for authorizing the start of reentry activities. 4.3 The Recovery Manager, under the directica of the Engineering Support Director, shall be responsible for coordinating and managing the implementation of reentry activities with the OSC Manager.

5. INITIATING CONDITIONS 5.1 Situations exist that require entry into affected plant areas that had been evacuated or closed to personnel access during the course of the emergency.

5.2 As determined by the Station Operations Manager. __.. _ - ~ -._

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2 EI 1300.10.2 .

6. PROCEDURAL STEPS 6.1 Pre-plan reentry activiti'es through discussions with the Recovery Manager.

NOTE: The Engineering Support Director and Operations Director shall determine the priority levels of reentry tasks and assure performance of these activities through coordination with the Recovery Manager and Station Operations Manager. 6.2 Assess the need for reentry and whether the benefits to be gained offset the potential hazards to the reentry personnel. 6.2.1 Utilize all available data including area and process monitor readings, survey data, and personnel observations to determine:

1. Which plant area (s) is affected.

2. The conditions in the area, such as personnel hazards, temperature, toxic environment, and equipment condition (i.e., pipe rupture, steam leak, etc.).

3. The time schedule, based on necessity, for ~s reentry to commence. , )

6.2.2 Review available radiation surveillance data. Determine , areas potentially affected by radiation and/or contamina-tion. Ensure that entries into these areas receive an Alara review, using guidance in HP 1601.05, Alara Procedure. 6.2.3 Review the radiation exposure histories of personnel required *.o participate in reentry activities into j areas with potential radiation hazards.

1. Restrict the use of personnel who have a high t radiation exposure history.

2. Planned exposures to radiation workers for unusual oeprating or maintenance problems, shall be within the limits specified in Attachment 1 for the quarter in which the planned work falls.

3. If emergencies such a fire control, halting releases, or protection of station equipment require emergency exposure,a planned limit of 25 rem whole body is acceptable.

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l l [ , 3 EI 1300.10.2 NOTE: This value is a guide. Personnel involved in this must be volunteers. All such exposures shall be considered as exceeding the exposure limits. j l l l

4. The Recovery Manager, Emergency Duty Officer and 1

                                       .          Radeon Operations Manager shall be notified of                                 ;

any planned or accidental short term exposures in , excess of 12 rems whole body. NOTE: Individuals receiving emergency or accidental exposures may be restricted from radiation work at the discretion of the Radeon Operations Manager. Personnel receiving short term exposures in excess of 12 rems whole body should require a medical examination. 6.3 Isolate and post areas determined to be unsafe or unnecessary to be reentered with appropriate warning signs and rope barriers. 6.4 Establish reentry teams from personnel available in the Operations l Support Center (OSC), Technical Support Center (TSC), or other assembly areas. NOTE: If additional personnel or equipment is needed, a list of the type and quantity should be forwarded to the Emergency Planning Supervisor via the Recovery Manager. 6.4.1 Reentry teams shall:

1. Consist of at least two personnel, a team leader and a communicator.

2. Be authorized emergency exposure limits as necessary and be advised to frequently check direct-reading dosimeters and withdraw to a safe area if assigned exposure limits are approached.

3. Be qualified for first aid, plant operations, health physics, and/or maintenance evaluation and corrective action as necessary for the specific reentry evolution.

4. Be equipped with, or, have availab.o, appropriate emergency equipment and protection devices.

NOTE: Such equipment shall be tested for operability prior to reentry. w . , . . -. ,

         .          . - . - - - - -             - . - - . . .     . . ~ . . . .        - . - - .      . .   . _

4 EI 1300.10.2' *- 6.4.2 Btief the reentry teams on the plan of action using  :

                                                                                                                      )

Attachment 2 prior to each reentry.

                        , NOTE:          Entry into areas of high radiation or contamination should follow the guidelines of HP 1601.04, Radiation Contamination and Airborne Radioactivity Areas.

6.4.3 Ensure that any reentry to perform radiation surveys is pre-planned, including:

1. Areas to be surveyed

2. Anticipated radiation and contamination levels

3. Radiation survey equipment required

4. Shielding requirements and availability -

5. Protective clothing and equipment required

6. Access control procedures (issuance of new REP's)

7. Decontamination requirements, and

8. Communications required. s

                                                                                                                       )

6.4.4 Ensure that reentry teams maintain continuous communica-tion and a continuous status of progress is-maintained. 6.4.5 Direct reentry personnel to withdraw to a safe area if severe unanticipated or unplanned conditions are encountered, pending further evaluation of the reentry effort. 6.4.6 Coordinates the return of the reentry teams. I 1. Ensure necessary monitoring, decontaminations,

and/or first aid in performing as per appropriate procedures.

2. Debrief team members using Attachment 3.

6.4.7 Report results and status of reentry teams to the Recove;y Manager, including a copy of each debriefing sheet. . 6.5 Determine the need for additional reentries and for initiation of recovery operations per EI 1300.17, Recovery. l

w  % 5 EI 1300.10.2

7. FINAL CONDITIONS .

7.1 Reentry operations have been completed and all reentry team members have been accounted for. 7.2 Debriefing of reentry personnel has been completed and documented.

              ~

2 8. ATTACHMENTS The following are attachments for use with this procedure:

1. Rems per Calendar Quarter

2. Reentry Team Briefing Sheet

3. Reentry Team Debriefing Sheet

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j , 6 EI 1300.10.2' Rems per Calendar Quarter Dose During Area Exposed Calendar Quarter While Body, gonads, blood-forming organs, head and trunk, lens of eye 1.25 Hands, forearms, feet or ankles 18.75 Skin of whole body 7.50

 . NOTE:  Individuals may be permitted to receive a dose to the whole body up to 3 res per quarter provided:

a. A Form NRC-4 has been completed and signed by the individual which details his entire radiation work exposure history.

b. The individual's accumulated exp)sure does not exceed 5 (N-18) rem where N is his age at his last birthday.

NOTE: The limits stated above are for occupational exposures. Permissible levels of radiation in unrestricted areas are limited to 500 ares per one calendar year for any individual. s i l

n wh Attachment 1 Page 1 of 1

   . _                                                       ~- _ _ .                               . _ . _ _ . .                     . . .           ,
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{ l l h - \ n 7 EI 1300.10.2

         -           Date:                                                                                            Time:

REENTRY TEAM BRIEFING SHEET ( NOTE: A briefing on radiological precautions should be conducted, if l radiological hazards are present.

1. Purpose of Team:

Emergency Maintenance / Repair In-plant Surveys Investigative Assessment Other (specify)

       .             2. Team Members:

3. Access Route identified, emergency exit identified

(

4. Primary Communications Method Alternate.

Reporting Frequency (Time Interval)

5. Equipment issued: a. Protective Clothing ,

b. SCBA's/ Respirators

c. Fire Fighting

d. Safety Lines / Ropes

e. First Aid

f. FlashligLts

g. Other

6. Task description: .

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                                                                                                  =                                                    l l

t Attachment 2 Page 1 of 1 l

_ . - e - P 8 EI 1300.10.2* Date: Time: ., REENTRY TEAM DEBRIEFING SHEET

1. Results of Operation (s):

2. Were plant conditions different than' expected? (Circle) Yes No If yes, explain:

3. Did any injuries occur during the entry? (Circle) Yes No If yes, describe:

                                                                                                . .s
                                                                                                    }

4. Did all equipment / tools work properly? (Circle) Yes No ,

If no, explain:

5. Were safety precautions (including radiological) adequate?

(Circle) Yes No If no, explain:

6. Comments (What additional actions are necessary?):

R' Attachment 3

   -                                            END            Page 1 of 1}}