ML20023B896

Public Version of Rev 5 to Emergency Plan Implementing Procedure Ei 1300.01, Emergency Plan Activation. Rev 26 to Index Encl

ML20023B896
Person / Time
Site:	Davis Besse
Issue date:	03/28/1983
From:	Beyer B, Briden D, Murray T TOLEDO EDISON CO.
To:
Shared Package
ML20023B890	List: ML20023B894 ML20023B896
References
1300.01, NUDOCS 8305060702
Download: ML20023B896 (40)

Text

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TaiE TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION j EMERGENCY PLAN IMPLEMENTING PROCEDURES REVISION INDEX D

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PAGE RE'rISION PROCEDURES REVISION TEMPORARY MODIFICATIONS i 0 EI 1300.00 4 EI 1300.01 5 EI 1300.02 3 T-6938 EI 1300.03 3

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EI 1300.04 3 EI 1300.05 3 EI 1300.06 3 EI 1300.07 3 EI 1300.08 5- 1 i

EI 1300.09 1 I EI 1300.10 1 EI 1300.11 1 EI 1300.12 2 T-6820 Revision 26 March, 1983 D

8305060702 830425 PDR ADOCK 05000346 F PDR

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h El 1300.01.0 bs Davis-Besse Nuclear Pcwer Station Unit No. 1 Emergency Plan Implementing Procedure EI 1300.01 Emergency Plan Activation I

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1 Record of Approval and Changes Prepared by- '

G. J. Reed 5/30/80

, Date

! Submitted by L C. E. Wells Section Head _

6/13/80 -

Date Recoc: mended by_

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QA Approved / Date

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Qualitp t.asurance 1:anager _

Approved by_ Date N Y~) N " ~ (

Sta'tionSuperintendeQ

/kN Date

{ Revision SRB No. QA Recommendation Date Approved Sta. Supt.

j b, p. W .Ahol6) Date Approved

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i 3 1 EI 1300.01.3

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1. PURPOSE To provide guidelines for conditions at which specific emergency j 3 classifications must be declared. ,

I 2. SCOPE 3 To specify emergency action levels and personnel judgments that l are consistent with the emergency classification scheme depicted in Appendix 1 of NUREG-0654, Rev. 1.

l 3. REFERENCES 3.1 The Davis-Besse Nuclear Power Station Emergency Plan f

3.2 Final Safety Analysis Report, DBNPS 3.3 Technical Specifications, DBNPS Unit No. 1, Appendix A l and B to License No. NPF3 3.4 Station Response to Emergencies, EI 1300.00

4. DEFINITION 3 4.1 Unusual Event - Event (s) are in progress or which have .

,) occurred that indicate a potential degradation of the l level of safety of DBNPS.

l 4.2 Alert - Events are in progress or have occurred which involve an actual or substantial degradation of the level f of safety of DBNPS.

4.3 _ Site 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 als.o exists a significant actual or potential release of radioactive material.

4.4 General Emergency - Events are in progress or have occurred which involve actual or imminent substantial core degrada-tion or melting with the potential for loss of containment integrity, and/or involve the potential for a r21 ease of radioactive particulates or gases offsite of a magnitude to exceed regulatory limits.

4.5 Emergency Actics Levels (EAL's) - Kadiological dose rates, specific contamination levels of airborne, waterborne, or

( surface-deposited concentrations of radioactive materials; or specific instrument readings and indications (including their rate of change) that may be used as thresholds for initiating such specific emergency measures as designating

4 2 EI 1300.01.3 a particular classification of emergency, initiating a notification procedure, or initiating a particular protec-tive action.

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5. EMERGENCY MEASURES I

L 5.1 The Shift Suprvisoc, when informed that abnormal or emer-gency conditions (real or potential) have arisen, shall r 3 perform the necessary actions in the priority listed

[ below:

5.1.1 Ensure that the immediate actions (e.g., use of Emergency Procedures) are taken for the safe

( and proper operation of the plant.

5.1.2 Assess the information available from valid

( indication and using Table 1, initially classify the situation with the following considerations:

3 f a. The specific emergency action levels described i in Table 1 are not all inclusive. The Shift l

' Supervisor or Emergency Duty Officer shall declare an appropriate emergency classification whenever, in his judgment, the station status

] warrants such a declaration. (Refer to Step

) 5.2.2 for guidance.)

b. Reaching these levels over a period of days l

rather than hours is not sufficient to declare the appropriate classification.

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c. Some of the emergency action levels described l are not, by their very nature, intended to be l used during maintenance and/or testing situa-tions where abnormal temperature, pressure, equipment status, etc. is expected.

l d. All of the emergency action levels shall be considered if the plant is, or was (immediately I prior to the ecergency condition) in Mode 1 l operating at a high power level; except for those conditions noted in the Index of Emer-I gency Action Level Conditions, Page 4.

I 5.1.3 Use the appropriate checklist from either the Unusual Event (EI 1300.02), Alert (EI 1300.03),

I Site Emergency (EI 1300.04), or General Emergency l 3 (EI 1300.05) procedure to ensure that immediate notification requirements are met and the proper I Emergency Plan response is taken.

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t u s 3 EI 1300.01.3 3 5.1.4 Perform additional emergency actions as time and conditions permit.

5.2 Operator judgment plays an important role in ensuring ,

that during any specific event the appropriate actions i

are performed.

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5.2.1 Examples

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a. For an abnormally high lake level, operator judgment should take into consideration the lake level, wind directicc3 weather con-

[ ditions, etc., before announcing a flood L warning and initiating personnel evacuation.

During a previous incident, personnel were evacuated during flood warning conditions, husever it was found that this was unnecessary since the weather then cleared and no flood or hazardous situation occurred.

b. 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 instruc-

% tions to aid personnel response. During a

) previous incident, an individual was injured requiring erdical assistance. The Initiate Emergency 1rocedures alarm was sounded, however verbal instructions via the gai-tronics {'

system could have been used to prevent unneeded I l personnel involvement and asserbly. )

3 5.2.2 For abnormal plant conditions that are not l speclfically covered in the Table 1 emergency action levels, the following criteria shall be I used to assist the Shift Supervisor or Emergency Duty Officer in classifying the event based on their judgment.

a. Unusual Event - Other plant conditions exist l that warrant increased awareness on the part of the plant operations staff or State and/or  !

I local offsite authorities which are not covered under any other existing station l

procedure.

b. Alert - Other plant conditions exist that l warrant precautionary activation of the Technical Support Center and Emergency Control I Center and placing other key emergency per-sonnel on sta2dby.

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4 EI 1300.01.3 s.

c. Site Emergency - Other plant conditions exist c that warrant activation of emergency centers and monitoring teams or a precautionary notification to the public near the site. -

( d. General Emergency - Other plant conditions i

exist, from whatever source, that make release of large amounts of radioactivity in a short

( time period possible, e.g., any core melt l

situation, i

5.3 Plant conditions should be continually evaluated to ensure the proper emergency classification is being utilized and the classification upgraded or downgraded by the Shift Supervisor and Emergency Duty Officer as conditions dictate 3 per Table 1 and Steps 5.1.2 and 5.2.2 above.

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4 5 EI 1300.01.3 INDEX OF EMERGENCY ACTION LEVEL CONDITIONS I Condition Page No(s).

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• Safety Systen Functions 6-7 I

L Plant Shutdown Functions 8 Coolant Pump Seizure 9 Loss of Assessment Functions 10 p Control Room Evacuation 11 L

• Abnormal Coolant Temperatures 12

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• Abnormal Primary Leak Rate 13-14 Abnormal to Primary / Secondary Leak Rate 15-16 3l

• Core Fuel Damage 17-18

- Loss of Fission Product Barriers 19

• Fuel Handling Accident 20 Abnormal Containment Atmosphere 21

• Abnormal Effluent Release 22

[ *High Radiation Levels in Plant 23

• Abnormal Radiation Levels at Site Boundary 24-26

• Contaminated Personcel 27 Major Steam Leak 28-29 Major Electrical Failures 30

[

• Fire 31

• Security Threat 32

• Hazards to Station Operation 33-35

• Natural Events (Within Ottawa County) 36-38

• NOTE: When evaluating the EAL's in Table 1. the plant must be in Mode 1 I3 j

or had been in Mode 1 operating at a high power level when the event initiated, except for those annotated conditions above which have been broken down and noted, as applicable, in their respective sections of Table 1.

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6 EI 1300.01.3 TABLE 1 SAFETY SYSTEM FUNCTIONS Emergency

[ Condition Indication (s) Classification L

3l Unplanned Initiation Any three of the four fol-. Unusual Event

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

Core Indicated

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

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

3. HPI and/or LPI pump current meters indicate l pump (s) running

4. HPI and/or LPI pump discharge valves indicate

{ open Loss of Containment Any One of the four followinz Unusual Event

.^T #

Integrity requiring plant shutdown per (EI 1300.02) l v T.S. 3.6.1.1:

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

A. Capable of being closed l by the Safety Features Actuation System, OR l 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 Table 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-iated with a penetration (e.g., welds, bellows, or 0-rings) becomes inoperable 3 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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TABLE 1 t

SAFE'iY SYSTEM ITNCTIONS (Con't)

Emergency r Condition Indication (s) Classification L

Loss of Engineered 1. A Safety Features Unusual Event c Safety Feature Actuation System (SFAS) (EI 1300.02)

L 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 h Path (operating) or Borated Water Sources (operating) become in-

[ operable and require plant shutdown per T.S. 3.1.2.2 I and 3.1.2.9 h 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 i I

Reliefs (red light on Panel C5798 or C5799)

I AND B RCS Pressure drop l' to <1600 psig l 2. Main Steam System:

(any 2 of 3)

I A. Rapid and continuing decrease in Steam Gen-erator pressure to <500 I

l B.

C.

psig Rapid RCS cooldown rate Audible steam relief I noise in the Control Room lasting >10 minutes I4 Loss of Steam Feed Rupture Control System

1. A Steam Feed' Rupture Con-trol System (SFRCS) Func-Unusual Event (EI 1300.02) l ticr.al Unit as shown in T.S. Table 3.3-11 becomes inoperable per T.S. 3.3.2.2 and requires plant shutdevn l

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8 EI 1300.01.1 TABLE I PLANT SHUTDOWN FUNCTION Emergency Condition Indication (s) Classificatioo k Loss of any system which 1. Any of the following Alert J precludes placing the systems become inoperable: (EI 1300.03)

, I plant in cold shutdown A. Service Water System L

(both trains)

B. Decay IIeat System (both trains)

C. Component Cooling Water (both trains)

Loss of any system which 1. The following systems Site Emergency precludes placing the become inoperable: (EI 1300.04) plant in hot shutdown A. Makeup Systea and EP!

System OR B. Main Feedwater System and Auxiliary Feed-t water System Failure of Reactor Pro- 1. Any time plant parameters Alert tection System to initiate meet conditions requiring (EI 1300.03) and complete a trip a trip and RPS fails to initiate and complete a trip which brings the reactor suberitical

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9 EI 1300.01.0 TABI.E 1 l COOLANT PUMP SEIZURE

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Emergency Condition Indication (s) Classification Coolant pump seizure with 1. Reactor Coolant System Alert

, fuel damage indicated flow indication decreases (EI 1300.03) by Iodine sample > *t.S. rapidly 3.4.8 AND

2. Confirmed Primary Coolant sample results indicate

>1.0 pCi/ Gram dose equiv-alent I-131 i

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10 EI 1300.01.3 TABLE 1 LOSS OF ASSESSMENT FUNCTIONS Emergency Condition Indication (s) Classification l

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Control Room Indications Any of the Following: Unusual Event or Alarms on Process or 1. Radiation monitoring (EI 1300,02)

Effluent Parameters NOT instrumentation < mit.- ,

functional to an extent imum channels operable i I requiring plant shutdown requiring shutdown per T.S.

or other significant loss requirements 3 of assessment or communica- OR tion capability 2. RE2024A, B & C, RE2025A ,B

& C and Backup Grab Sample l capability become in-operable I OR

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

OR

4. Post-accident instrument-ation < minimum channels

operable requiring plant f shutdown per T.S.

requirements (T.S. 3.3.3.6)

I OR

5. Complete failure of the plant telephone system and Gai-tronics system l

l All annunciator alarr.s 1. Any simultaneous loss Alert I and station computer of all annunciator (EI 1300.03) l lost alarms and the station computer l

All annunciator alarms 1. Complete loss of all Site Emergency and station computer lost annunciator alarms (EI 1300.04) l >15 minutes during plant and station computer i transient lasting more than 15 minutes I AND l 2. Plant transient initiated or in progress l

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4 11 EI 1300.01.0 TABLE 1 COI. TROL ROOM EVACUATION

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Emergency Condition Indication (s) Classificatio7 _

Evacuation of Control Room 1. Any evacuation of the Alert required Control Room with shut- (EI 1300.03) down control established

{ locally within 15 minutes Evacuation of Control Room 1. Any evacuation of the Site Emergency and Control NOT estab- Control Room with shot- (EI 1300.04) lished locally within down control NOT estab-15 minutes lished locally within 15 minutes i

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12 EI 1300.01.3 TABLE 1 ABNORMAL COOLANT TEMPERATURES

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Emergency Conditio_n . Indication (s) Classification 3 Core Subcooling is 1. As determined by Sub- Unusual Event

• Determined to be less Cooling grapn or T,, (EI 1300.02) than normal (10 ) Meter Indication (TD14950 or TD14951)

AND

2. As indicated by the

{ difference between Pres-surizer Temperature and 3

l Th (use incore couples temperature thermo-if Th meter is orf-scale) l 3 Ceolant Temperatures 1. As determined by the Unusual Event

• and/or pressures outside combination of Reactor (EI 1300.02) i of Technical Specification Coolant Core Outlet limits Pressure and/or Outlet Temperature exceeding the safety limits of T.S. 2.1.1 -

1 3 NOTE: For the above asterisked (*) classification (s), the plant can be in any mode for the listed FAL's to be applicable, l

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13 EI 1300.01.3 TABLE 1

( ABNORMAL PRIMARY LEAK RATE 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 f GPM total l

B 3 3.

OR Leakage from any RCS pres-t l

l sure isolation valve >5 gpm as listed in TS Table l 1

l 3.4-2 l l

Leak Rate >50 GPM but Any Two of the Four Following: Alert

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

Injection' system decreasing approximately  !

capacity two inches per minute I 1 while RCS temperature remains steady l

1

2. Increased activity en Con-l B

tainment Vessel Airborne Monitor (s) RE 4597AAA, AAB l AAC, or RE 4597BAA, BAB, BAC

3. Increase in Normal Sump level on level instruments LI 1546 A or B u 4. RCS Water Inventory Balance indicates I >$0 GPM leakage 1.

l Loss of Coolant Accident 1. Pressurizer level and Site Emergency

> High Pressure Injection pressure decreasing (EI 1300.04) system capacity , rapidly without an associated change in RCS temperature (RCS tempera-p ture/ pressure reach saturation conditions)

OR l

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TABLE 1 ABNORMAL PRIMARY I1AK RATE s

Emergency Condition Indication (s) Classification _,

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2. Containment pressure >38.4 psia end Reactor Coolant System pressure <400 peig 3 NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for tte listed EAL's to be applicable.

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g 15 EI 1300.01.3 TABLE 1 ABNORMAL PRU1ARY TO SECONDARY LEAK RATE Emergency Condition Indication (s) Classification Leak Rate Requiring RCS Water Inventory Unusual Event I Plant Shutdown by Balance indicates >1 (EI 1300.02)

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

1. Main Steam Line Radiation monits.r(s) (RE 600 and/or 3 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

3. Unexplained Makeup tank level decrease while Reactor Coolant System temperature remains constant 3 Rapid failure of Steam Main Steam Line Radiation Alert Generator tubes (e.g., monitor (s) (RE 600 and/or (EI 1300.03) several hundred gpm RE 609) in the " Analyze Mode" primary to secondary to detect N-16 indicate leak rate!) increased activity, or Coa-denser Vacuum discharge radia-tion monitor (s) (RE 1003 A (B)) indicate increased activity 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) Level 2 activates

16 EI 1300.01.3 TABLE 1 ABNORMAL PRIMAhY TO SECONDARY LEAK RATE 5 _

Emergency F Condition Indication (s) Classificction 3 4. 'uin Steam line radiation monitors in the " Gross Mode" i L indicating more than 15000 cpm net; background equals 1000 cpm Rapid failure of one Steam 1. Noticable drop in Alert Generator tube and loss of RCS pressure and pres- (EI 1300.03) offsite power surizer level AND

2. The 13.S KV BUSES are deenergized AND 3 3. Main Steam line radia-tion monitors in the

" Gross Mode" indicating more than 15000 cpm net; background equals 1000 cpm 3 Rapid failure of Steam 1. Indications for leak Site Emergency Generator tubes (r.everal rate of 400-700 GPM (EI 1300.04) hundred GPM leak rate AND indicated) and loss of 2. The 13.8 KV BUSES are offsite power deenergized i

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17 EI 1300.01.3 TIJE 1 CORE FUEL DAMAGE

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Emergency j Condition Indication (s) Classification 3 High Coolant activity 1. Failed Fuel Detector (RSH Unusual Event sample Requiring Plant 1998) alarm with confirmed (EI 1300.02) t Shutdown by Technical sample results indicating Specifications for Iodine >1.0 pCi/ Gram Dose Equiv-(T.S. 3.4.8) alent I-131

, AND

2. Plant Shutdown required

(

3 Very High Coolant 1. Failed Fuel Detector (RSH Alert I activity 1998) "RC Letdown Activity (EI 1300.03)

High" alarm AND

2. Confirmed sample results indicate >300 pCi/ Gram I-131 Core damage with in- 1. Confirmed primary coolant Site Emergency

- adequate core cooling sample results indicate: (EI 1300.04) detemined A. >1.0 pCi/ Gram Dose equiva, lent I-131, and B. >100/E pCi/ Gram specific activity, AND

2. Reactor Coolant System Hot Leg 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) 3l a release of large >300 pCi/ Gram I-131 amounts of radioactivity AND possible 2. Incore thermocouple temper-atures indicate >2000*F l AND

3. Containment radiation level 3 is > 104 R/hr OR

4. Containment pressure is

>40 psia D

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TABLE 1 l

l CORE FUEL DAMAGE I .

Emergency Condition Indication (s) Classification 3 Core melt situations Any one of the following General Etergency l sequences occurs with a I coccurrent likely failure of (EI 1300.05) 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 f 2. A transient is initiated l by a loss of the main feedwater system followed by a failure of the emer-gency feedwater system j for an extended period with core melting resulting

3. A transient occurs requiring operation of shutdown systems with failure to trip Caich 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-ure of RCS heat removal systems over a period of several hours leads to a core melt

19 EI 1300.01.3 TABLE 1 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 3 NOTE: Other sect. ions 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

) Site Emergency levels for sample result values and indi-

-d cations.

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

c. For item .), reter 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 1300.01.3 TABLE 1 i

l FUEL HANDLING ACCIDENT Emergency Condition Indication (c) Classification Fuel Handling Accident 1. Direct infctmation from Alert

• which results in the fuel handling personnel (EI 1300.03) release of radioactivity indicating that an to Containment or Spent irradiated fuel assembly Fuel Pool area has been damaged and

! radioactive gases are escaping AND l 3 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 0") and is reported to the Cantrol Room .-

Fuel Handling Accident 1. Indications of fuel hand- Site Emergency

• which results in SFAS ling accident which results (EI 1300.04) actuation in the release of radio-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 3 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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21 EI 1300.01.5 TABLE 1 l ABNORMAL CONTAINMENT ATMOSPHERE

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Emergen;y Condi' ion Indication (s) Classification l

I Increasing Containment radiation, pressure, and Any Two of the Following:

1. Containment high range Alert (EI 1300.03) l 5 temperature monitor (s) (RE 4596A or B I 2.

indicate greater than 50 R/hr)

Containment pressure (Il l

2000, PI2001, PI2002, PI I

i 2003) indicates >17 psia 1 3. Containment average air temperature (TI1356, TI 1

1357, TI1358) indicates

>170*F High Containment radia- Any Two of the Following: Site Emergency tion, pressure and 1. Containment high range (EI 1300.04) temperature radiation monitor (s) 5 (RE 4596A or B indicate greater than 50 R/hr)

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 Cantainment Any Two of the Following: General Emergency radiation and pressure 1. Containment high range (EI 1300.05) radiation monitor (s) 5 (RE 4596A or B indicate greater than 10,000 R/hr)

2. Ceutainment pressure (PI 2000, PI2001, PI2002, PI 2003) indicates >40 psia

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

22 EI 1300.01.3 TABLE 1

)

ABNORMAL EFFLUENT RFLEASE l

Emergency -

Condition Indication (s) Classification l

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3; Effluent Release > limits Confirmed analysis results Unusual Event

• allowed by E.T.S. 2.4.1 or for a gaseous or liquid (EI 1300.02) l E.T.S. 2.4.3 release indicates > the limits given in the Environ-mental Technical Specifica-t tions l

Effluent release >10 Confirmed analysis results Alert

( times instantaneous for a gaseous or liquid (EI 1300.03) limits all wed by E.T.S. release indicates >10 2.4.1 or E.T.S. 2.4.3 times the instantaneous

( limits given in the Environ-I mental Technical Specifica-tions 3 NOTE: For the above asterisked (*) classification (s), the plant can be in j any Mode for the listed EAL's to be applicable.

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b 23 E! 1300.01.3 TME 1 HIGH RADIATION LEVELS IN PLANT

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Emergency Condition Indication (s) Classification I General area radiation levels or high airborne radioactivity >1000 times

1. Fire Detection System /

Radiation !!onitcring System (FDS/RMS) Console-Alert *

(EI 1300.03) normal from an unidentified Alarm with high radiation 3 sourec, lasting more than 30 monitor reading displayed

minutes on CRT'and printed out on data logger

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OR Local Radiation Monitoring Alarm Station alarms both audibly (Horn) and visually I (green light goes off and red light comes on) and is reported to the Control I ,

3.

Room AND An area radiation survey B or airborne radioactivity sample indicaten; activity levels >1000 times normal 3 NOTE: For the above asterisked (*) classification (s) the plaat can be in ,

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

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24 EI 1300.01.3 TABLE 1 ABNORMAL RADIATION LEVELS AT SITE BOUNDARY

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Emergency Condition Indication (s) Classification L

Projacted or actual 1. Station Vent Monitor Alert

• r radiation readings that (RE2024C or 202SC) read- (EI 1300.03)

L indicate a potential dose ing >0.1 pCi/cc Xe-133*

of 100 mR Whole Body or 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 are 500 mR Child Thyroid at which will give an equiv- the appli-E 3 the Site Boundary using valent dose in <2 hours cable con-L adverse meteorology. 2. Station Vent Monitor centrations, (RE2024B or 2025B) read- however they ing >7.2 x 10-6 pCi/cc I-131 can not be h 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

• NOTE: This concentra- 3. Radiation Monitoring Team installed tion is based on reprts radiation levels at instrumenta-a stability class Site Boundary <50 mR/hr for tion. They of F and wind speed an incident projected to last are to be (a of 2 mph; if actual meteorology is used, 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-ings which will give an used when the Kamen High

) this concentration equivalent dose in <2 hours range mon-l may be higher 4. Radiation Monitoring Team itors are reports I-131 concentrations installed.

I >1.1 x 10-7 pCi/cc at Site Boundary Projected or actual radia- 1. Grab sample, or Station Site Emergency * '

f tion readings that indi- Vent Monitor (RE2024C or (EI 1300.04) cate a potential dose of 2025C) reading >1.0 pCi/cc I 1 rem Whole Body or 5 rem Child Thyroid at the Site Xe-133* for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or readings which will give an NOTE: (These are the appli-l 3 Boundary using adverse equivalent dose in <2 hours cable con-I meteorology. 2. Station Vent Monitor (RE2024B or 2025B) > 7.2 x 10-5 pCi/cc I-131 for centrations, however they can not be l

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 I

l will give an equivalent dose in <2 hours from the presently

• NOTE: This concentra- 3. Radiation Monitoring Team installed tion is based on reports radiation levels instrumenta-a stability class >500 mR/hr at the site tion. They l of F and wind speed boundary for an incident are to be of 2 mph; if actual 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 meteorology is used, or which will give an equiv- the Kamen this concentration alent dose in <2 hours High range l

I 4 25 EI 1300.01.3 TABLE I ABNORMAL RADIATION LEVELS AT SITE BOUNDARY Emergency Condition Indication (s) Classification l

I may be higher 4. Radiation Monitoring Team reports I-131 concentrations

>1.1 x 10-8 pCi/cc at the monitors are in-stalled.

Site Boundary i

3 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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26 EI 1300.01.3 TABLE 1 h ABNORMAL RADIATION LEVELS AT SITE BOUNDARY

~

Emergency l Condition Indication (s) Classification Projected or actual site A radiological puff release Site Emergency

• boundary radiation readings (short instantaneous relesse (EI 1300.04) 3 corresponding to a whole from a non-continuous source) bcdy dose of 50 mr/hr for occurs with:

l 1/2 hour or 500 mr/hr for 1. Station vent monitor l 2 minutes using adverce RE 2024C or 2025C readings meteorology or five times and analysis indicating these levels for a thyroid 9.6 x 10-2 pCi/cc* for 1/2 dose. hour or .96 pCi/cc* for 2 mic.

• NOTE: These are the ap- OR plicable concen- 2. Station vent monitor RE trations, however 2024B or 2025B readings they cannot be ob- and analysis indicate tained from the pre- 7.2 x 10-8 pCi/cc* for sently installed in- for 1/2 hour or 7.2 x stalled instrumenta- 7.2 x 10-5 pCi/cc* for tion. They are to 2 ein.

used when the Kamen High range monitors are installed in the near future.

Projected or actual site A radiological release General Emergancy*

boundary radiation read- occurs with: (EI 1300.5) ing corresponding to a 1. Projected doses at the whole body dose of 1 R/hr site boundary equat.e to or a thyroid dose of 5 1 R/hr whole body or 5 R/br using actual R/hr thyroid (or higher) meteorology. using actual meteoroligi-cal data.

OR

2. A Radiation Monitoring Team at the site boundarf reports radiation levels at 1 R/hr or 2.27 x 10-8 pCi/cc I-131 (or 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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27 EI 1300.01.3 TABLE 1

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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 1

L 3 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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28 EI 1300.01.3 TABLE 1 MAJOR STEAM LEAK

'l Condition Indication (s)

Emergency Classification I Major Steam Leak with NO Primary to Secondary leakage Increasing Containment pres-sure (if leak is inside Con-tainment) or unusually loud Unusual Event (EI 1300.02) noise outside Containment

.I And One of tpe Following:

1. Steam and Feedwater Rupture Control System I 2.

(SFRCS) initiates 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 W Monitor (s) (RE 600 and/or RE 609) in the " Analyze lg Mode" to detect N-16

E 'adic*te i"=r**'ed activity, AND

'g 3. RCS Water Inventory Balance g indicates >10 GPM Primary l to Secondary leakage 3 4. Main Steam line radiation monitors in the " Gross Mode"

5- indicating more than 15000 cpm net; background equals 1000 cpm Major Steam Leak with 1. Indication of a Major Site Emergency

^

>50 GPM Primary to Steam Leak (EI 1300.04)

Secondary leak rate and AND fuel damage indicated 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 e

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29 EI 1300.01.3

.. TABLE 1 MAJOR STEAM LEAK

[

Emergency Condition

{ Indication (s) Classification I 3. RCS Water Inventory Balance indicates '>50 GPM Primary to Secondary Leak rate

{

AND I

j

4. Confirmed Primary Ccclant sample results indicate ,

Dose Equivalent I-131 above acceptable limits 1 of T.S. Figure 3.4-1 AND 3 5. Main steam line radiatimi monitors in the " Gross Mode" indicating more than 150,000 cpm net; tackground equals 1,000 cpm.

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L 30 EI 1300.01.3 ,

TABLE 1 L MAJOR ELECTRICAL FAILURES y

Emergency

[ Condition Indication (s) Classification 3l Loss of offsite power 1. Both Emergency Diesel Unusual Event F or cf 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 E

L 3l Loss of offsite power 1. All AC buses deenergized Site Emergency and all onsite AC power more than 15 minutes (EI 1300.04) p for more than 15 minutes 3( Loss of all onsite 1. All DC buses deen- Alert DC power ergized as determined (EI 1300.03) by breaker positions, and w') line voltage or amperage meters Loss of all onsite DC 1. All DC buses deenergized Site Emergency power for more than 15 for more than 15 minutes (EI 1300.04)

[ minutes

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1 1

1 1

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g 31 EI 1300.01.3 TABLE 1 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 support 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 3 Fire resulting in the 1. Observation of a major Site Emergency loss of redandant fire that defeats the (EI 1300.04)

safety system trains capability of redundant

_,/ or functions safety system trains which includes both trains or functions 3 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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32 6I 1000.01.3 l TABLE 1 l SECURITY THREAT g Emergency l

Condition Indication (s) Classification ,

Security Threat, Attempted 1. Report by a senior Unusual Event

• Entry, or Attempted member of the Security (EI 1300.02) l Sabotage Force of an Attempted Eritry, Attempted i 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 Imminent loss of physical 1. Physical attack on the Site Emergency

• control of the plant plant involving imminent (EI 1300.04) occupancy of the Control 3l Room or local shutdown stations Lors of physical control 1. Physical attack on the General Emergency

• of the facility plant which has resulted (EI 1300.05) in occupation of the 3l Control Room or local shutdown stations by unauthorized personnel l l

3 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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33 EI 1300.01.3 TABLE 1 HAZARDS TO STATION OPERATIONS t

Emergency

- Condition Indication (s) Classification i

Aircraft crash onsite or 1. Control Room informed by Unasual Event

• unusual aircraft activity Station personnel who have (EI 1300.02) over facility made a visual siting 5

r Aircraft crash affect- 1. Control Room informed Alert

[ ing plant structures by Station personnel who (EI 1300.03) have made a visual siting f

L Aircraft crash damaging 1. Control Room informed by Site Emergency vital plant systems Station personnel who have (EI 1300.04) made a visual siting

[

AND

2. Instrumentation readings on vital systems indicate equipment problems j

Train derailment onsite 1. Control Room informed by Unusual Event *

- Station personnel who have (FI 1300.02) made a visual siting l AND

( 3 2. Station Structures have been damaged OR

3. Danger or potential danger

( to Station personnel exists

( Onsite explosion Control Room informed by Station personnel who have Unusual Event *

(EI 1300.02) made a visual siting Onsite explosion affect- 1. Control Room informed by Alert ing plant operations Station personnel who have (EI 1300.03)

[ made a visual siting AND

2. Instrumentation readings on plant systems indicate equipment problems 3 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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34 EI 1300.01.3 TME 1 )

(

HAZARDS TO STATION OPERATIONS (Con't) I Emergency Condition Indication (s) Classification j L

Explosion causing severe 1. Explosion causing either Site Emergency y damage to hot shutdown of the following combina- (EI 1300,04) l equipment tions of systems to become inoperable:

A. Makeup Syste:a and HPI r System i L OR l B. Main Feedwater Ey: stem  !

and Auxiliary Feed L water System r 3 Toxic or flammable gas 1. Ccatrol Room informed by Unusual Event

• h release from its con- Station personnel who (EI 1300.02) tainer to atmosphere at have discovered it life threatening levels

! near or onsite m,

Uncontrolled toxic or 1. Control Roem infor.ned by Alert flammable gas release Station personnel who have (EI 1300.03) at life threatening levels made a visual siting within plant facilities OR h 2. Chlorination System Trouble Alarm initiates and Station I personnel verify a signifi-cant release l

Uncontrolled toxic or 1. Control Room informed by Site Energency l flammable gas release at Station personnel who have (EI 13C0.04) life threatening levels made a visual siting I. within plant vital areas AND l 2. Chlorination System Trouble ,

Alarm initiates and Station

, personnel ~ verify a signifi-

, cant release OR

3. The Control Roon Ventila-tion System automatically l shuts down 3 NOTE: For the above asterisked (*) classification (s), the plant can be in any Mode for the listed EAI.'s to be applicable.

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35 El 1300.01.0 TABIE 1 HAZARDS TO STATION OPERATIONS (Con't)

~

Emergency Condition Indication (s) Classification Tur$1ne damage causing Control Room int'ormed by Alert c u ing penetration Station personnel who have (EI 1300.03)

' made a visual inspection of turbine casing I

l. Missile impact on plant Control Room informed by Alert structures Station personnel of any (EI 1300.03)

, missile

(

Missile impact causing 1. Control Room informed by Site Emergency severe damage to Hot Staticn personnel of any (EI 1300.04)

Shutdown equipment missile impact on Hot Shut-down equipment AND f 2. Instrumentation readings on

'm-Hot Shutdown equipment

) indicate equipment problems r_-

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.- _ - _ -._ _ _ - _ - - - - - _ _ . _ _ _ _ - - - . - - _ - _ _ _ _ - _ . - - - _ - _ _ _ - - _ _ _ - - __.-________-_--_.a

o 36 EI 1300.01.3 TABLE 1 NATURAL EVENTS (WITHIN OTTAWA COUNT'Q Emergency Condition Indication (s) Classification Any earthquake 1. Confirmed Station Seismic Unusual Event

• Instrumentation Alarm (EI 1300.02) 3 Earthquake > Cperating 1. Procedure for Earthquake Alert Basis Earthquake (CBE) Evaluation (SP 1105.17) (EI 1300.03) levels indicates earthquake >.08 g Earthquake > Safe 1. Procedure for Earthquake Site Emergency I Shutdown Earthquake Evaluation (SP 1105.17) (EI 1300.04) 1 (SSE) levels indicates earthquake

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

• _ Statiort personnel who have (EI 1300.02)

') made a visual siting of a l

_/ Tornado crossing the '

site boundary Tornado striking 1. Coatrol Rooo 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 3l Hurricane force winds up 1. Control Room informed by Alert to Design Basis Levels Load Dispatcher of (EI 1300.03)

Hurricane striking Ottawa l County AND

2. Wind speed indication from t

the station meteorological I

tower is of sustained winds approaching 90 mph 3 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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o 37 EI 1300.01.4 TABLE 1 l

NATURAL EVENTS (WITHIN OTTAVA COUNTY) (Lon't)

Emergency 'l Condition Indication (s) Classification l i

' 3l Hurricane force winds 1. Control Room informed by Site Emergency l

> Design Basis Levels Load Dispatcher of (EI 1300.04)

Hurricane striking Ottawa 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

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

2. Control Room informed by Station personnel who have made visual siting D 3.

AND High Forebay level alarm or lake level indication oscillating with readings high (>560 feet I.G.L.D.)

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

3 Flood, low w:ter, 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 oscillating with readings at. Design Levels high (584 feet I.G.L.D.) or low 562.1 feet I.G.L.D.)

_m 3 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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,~ o 38 EI 1300,01.3 f TME 1 l

NATURAL EVENTS (WITHIN OTTAWA COUNTY) (Con't) i Emergency Condition Indication (s) Classification i

3 Flood, low water, surge 1. Contrcl Room informed Site Emergency or seiche > Design Levels by Load Dispatcher (EI 1300.04)

OR

2. Control Room informed by Station personnel who have made a visual siting l AND j 3. High Forebay level alarm or lake level indication oscillating with readings

> Design Levels high (>584 feet I.G.L.D.) or low

(<562.1 feet I.G.L.D.)

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