ML20050E032

Public Version of Revision 1 to Emergency Plan Implementing Procedure EPIP 1.1, Initial Classification.

ML20050E032
Person / Time
Site:	Point Beach
Issue date:	03/17/1982
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20050E029	List: ML20050E030 ML20050E032
References
EPIP-1.1-01, EPIP-1.1-1, NUDOCS 8204120483
Download: ML20050E032 (15)

Text

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EPIP 1.1 MINOR Revision 1 l 03-17-82 INITIAL CLASSIFICATION 1.0 GENERAL The purpose of this procedure is to provide a means o'f classify'ing an event or condition at the Point Beach Nuclear Plant into one of four emergency classifications as described in the Point Beach Nuclear Plant Emergency Plan. Each emergency classification requires emergency organization noti-fications, mobilizations, and actions to be performed in order to appropriately react to the situation and provide for the health and safety of plant and public personnel. They are listed in order of increasing severity.

1.1 Unusual Event An unusual plant condition which either has occurred or might occur.

This condition could possibly lead to a degradation in overall safety. This condition does not represent a significant radio-activity release, involves no offsite response, and may require no augmentation of plant personnel. In spite of the above, prompt notification of the counties and state is required.

1.2 Alert Plant conditions in which events are in progress or have occurred which involve an actual or potential degradation of plant safety.

Radiation releases are not likely to cause an offsite hazard. Prompt offsite notification is necessary and the plant organization may have to be augmented.

1.3 Site Emergency ,

Plant conditions in which events are in progress or have occurred which involve actual or probable major failures of plant functions.

Potential radioactive . releases may have an impact on offsite people.

Prompt notification of offsite agencies is required. The plant organization must be augmented and the technical support center, onsite operations support center, and emergency support center will be operational. An evacuation may be necessary.

1.4 General Emergency .

Plant conditions in which events are in progress or have occurred hich involve actual or imminent substantial core degradation and a potential for loss of containment integrity. Potential radioactive releases may have an impact or. 'offsite people. Prompt notification 82041204EK3 820331 PDR ADOCK 05000266 .

F PDR

EPIP 1.1 Page 2 of offsite agencies is required. The plant organization must be augmented and the technical support center, onsite operations support center, and emergency support center will be operational. An evacu-ation may be necessary. The emergency news center will be opened.

The Shift Supervisor has the responsibility and authority to take immediate action to mitigate the consequences of the emergency. He will consult with the Duty & Call Superintendent and assign the appropriate emergency classi-fication and initiate the necessary Emergency Plan implementing procedures.

2.0 REFERENCES

2.1 Nuclear Regulatory Commission NUREG-0654, Revision 1, published November, 1980.

2.2 Point Beach Nuclear Plant Emergency Plan Sections 4.1 and 5.1.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 All actions and notifications should be appropriately logged.

3.2 Emergency Plan implementing procedures are not to be used to respond

. to security threats. One hour notification of the NRC is required using the red phone for security threats.

3.3 Certain events require notification to the NRC within one hour. These items are included on Table 1-1. Those items which are noted as "NRC Only" means that there is no classification for the events and no notification other than the NRC is required. These notifications are not considered as starting the Emergency Plan.

3.4 The " Indications Used" in Table 1-1 are those which one may expect if that level of emergency occurs very quickly. For more slowly developing situations, other indications may be judged appropriate.

For example, a primary system leak rate of 40 gpm is an Unusual Event. Subsequently, charging may be lost and, in addition, the leak may worsen. One may not see charging flow 50 gpm greater than letdown flow when in fact an Alert should be declared.

4.0 INITIAL CONDITIONS None.

NOTE: APPENDIX 1 0F NUREG-0654 (PAGE 1-3) CONTAINS THIS SENTENCE: "THE TIME IS MEASURED FROM THE TIME AT WHICH OPERATORS RECOGNIZE (EMPHASIS ADDED) THAT EVENTS HAVE OCCURRED WHICH MAKE DECLARATION OF THE EMER-i GENCY CLASS APPROPRIATE.

I I

l

EPIP 1.1 Page 3 5.0 PROCEDURE 5.1 Call the Duty & Call Superintendent for consultation to establish the initial classification. If he is unavailable, the Shift Supervisor is responsible for classification.

5.2 Select affected categories related to plant events or conditions at this time. Check (l) all applicable categories.

Refer to Page Category in Table 1-1

1. Safety System Functions 1

2. Abnormal Primary Leak Rate 1

3. Abnormal Coolant Temperature /

Pressure 2

4. Abnormal Primary / Secondary Leak 2

5. Core Fuel Damage 3

6. Secondary Coolant Anomaly 4

7. Abnormal Effluent 5

8. Major Electrical Failures 5

9. Control Room Evacuation 6

10. Fire 6

11. Plant Shutdown Function 7

12. Abnormal Radiation Levels at Site Boundary 8

13. Fuel Handling Accident 8

14. Serious or Fatal Injury 9 l 15. Security Threat 9

16. Hazards to Plant Operations 9

17. Natural Events 10

18. Reactivity Transient 10 9

EPIP 1.1 Page 4 1

t *

• Refer to Page Category s in Table 1-1

19. __,

Load Transient 11

20. Other 11 5.3 Beginning at the indicated page in Table 1-1 (attached), review initiating conditions for all categories checked above.

i

5.4 Record most severe emergency classification at this time.

5.5 Record date/ time of initial classification (subsequent columns for reclassification at a later date and time are provided if reclassifi-

. cation is required).

Initial Subsequent Subsequent Date/ Time Date/ Time Date/ Time NOTE: IF THE SHIFT SUPERVISOR CANNOT COMMUNICATE WITH A DUTY &

CALL SUPERINTENDENT, THE SHIFT SUPERVISOR MUST NOTIFY THE STATE AND TWO COUNTIES WITHIN 15 MINUTES OF THE DECLARATION OF ANY CLASS OF EMERGENCY.

5.6 If events or conditions are classified as an Unusual Event, perform EPIP 2.1, " Unusual Event - Immediate Actions."

5.7 If events or conditions are classified as an Alert, perform EPIP 3.1,

" Alert - Immediate Actions."

5.8 If events or conditions are classified as a Site Emergency, i

perio'rm EPIP 4.1, " Site Emergency - Immediate Actions."

l 5.9 If events or conditions are classified as a General Emergency, perform EPIP 5.1, " General Emergency - Immediate Actions."

NOTE:

"One hour" refers to the requirement to notify NRC within one hour (10 CFR 50.72).

"One hour - Open line" refers to the requirement to notify NRC within one hour and maintain an open line for continuous communication (10 CFR 50.72).

Notes: DCS - Duty & Call Superintendent DSS - Duty Shift Steervisor TAB 12 1-1 ffDSAR - Final Facility Description &

Safety Analysis Report M&SP - Modified Amended PB8EP Security Plan EMERGENCY CtASSIFICATION Emergency Cat egor,y Initiating condition Indication Used Classification ,

1. Safety System Functions Urglanned initiation of emergency core cooling Any of the following first-out reactor trip Unusual Event with injection to the primary system panel ansrwiation with indicator confir-motion noted:

1. " Containment press hi",

[PI-945, PI-947. PI-949 (2/3 >5 psig)l

2. " Steam line loop & 10-10 press"

[PI-468, PI-469, PI-482 (2/3 <530 psig))

3. " Steam line loop B 10-10 press" lPI-478, PI-479, PI-483 (2/3 <530 psig)l

4. "Pressuriser lo press SI"

[PI-429, FI-430, PI-431 (2/3 <1735 psig)]

5. Wide range pressure <1500 psig Loss of contairment integrity requiring When shutdown commences as determined by DSS Unusual Event .

shutdown by Technical Specifications and DCS Loss of engineered safety feature requiring When shutdown casumences as determined by DSS Unusual Event shutdown by Technical Specifications and DCS Loss of fire protection system function When shutdown commences as determined by DSS Unusual Event requiring shutdown by Technical Specifi- and DCS cations (i.e., both fire ptemps inoperable)

2. Abnormal Primary Exceeding Technical Specification primary system When shutdown commences as determined by DSS Unusual Event Leak Rate leak rate (10 gn) and DCS s .

~

o EFIP 1.1 Table 1-1 Page 2 Emergency Category Initiating condition Indication Used Classification Leak rate >50 @m A of the following:

J Alert

1. " Volume control tank level hi-lo"

[LI-141 and/or L1-il2 (8%]

2. Decreasing pressurizer level lLI-426,L1-427,LI-428]

3. " Charging pump speed hia

4. Charging line flow (FI-128) >50 ge more than letdown flow (FI-134)

Leak rate in excess .of available pump Ay of the tollowing: Site Emergency capacity including charging, high head $1

• and low head SI 1. " Volume control tank level hi-lo

[LI-141 and/or LI-!!2 <8%)

2. No pressurizer level indicated lL1-426, L1-427, L1-428]

3. All available piamps running as indicated by the red light at the switch

4. Increasing core exit T/C teep as indicated by F-250 and confirmed on local readout.

3. Abnormal coolant Unexpected decrease in subcooling margin Both of the following: Unusual Event Temperature / Pressure

1. Alarm on P-250, if operable

2. Confirmation by manual calculation

. Pressure >2735 psig Pressure >2735 psig on PR-420 and NRC only

" Code, safety or PONV not closed" l-hour open line (2)

DNBR <l.30

4. Abnormal Primary /' Exceeding Technical Specification primary-secondary When shutdown commences as determined by DSS Unusual Event Secondary Leak leak rate and DCS

EPIP 1.1 Table I-I Fage 3 Emergency category Initiating Condition Indication Used Classification Gross failure of I SG tihe (>400 ga) & loss of All of the following first-out reactor panel Alert ,

offsite power (ffDSAR 14.2.4) annunciation with confirmation indication:

1. " Pressurizer Lo Press S1,"

lFI-429, F1-430, FI-431 (2/3 <!735 psig)l

2. a . " Steam generator A level hi" g.

[LI-461 LI-462, L1-463 (2/3 >70%)] or

b. " Steam generator B level hi" lLI-471, LI-472. LI-473 (2/3 >70%)l

3. a. "4.16 kv bus undervoltage"

& 0 volts on A03 & A04 voltmeters.

b. 304 to A03 ammeter on CO2 (0 amps)

c. XO4 to A04 asumeter on CD2 (0 amps)

4. SI flow >400 ga indicated by FI-924 &

FI-925 and pump discharge pressure corresponding to flow.

Rapid failure of >10 SG tubes (4000 g a) with All of the'following first-cut reactor panel Site Emergency or without offsite AC annunciation with confirming indication:

1. " Pressurizer lo press SI"

[FI-429, F1-430, FI-431 (2/3 <1735 psig)l

2. a . " Steam generator A level I.ia lLI-461, LI-462 LI-463 (2/3 >70%)l or

b. " Steam generator a level ht"

[LI-471, L1-472. LI-473 (2/3 270%)]

3. SI flow >4,000 g a indicated by F1-626 &

F1-928.

5. Core Fuel Damage Gross fuel damage in core indicated Both of the following: Unusual Event

1. Letd.wn line radiation monitor (R9) 100 m alarm setpoint.

2. Sustained offscale & chemical analysi=^ shows fission product concentration increase by 100X.

EPIP !.1 Table t-1 Page 4 Emergency Category Initiating Condition Indication used Classification Massive fuel damage 300 pC1/cc iodine-equivalent as determined by Alert

. by chemical analysis ,

1. Messive loss of fuel clad integrity Initiating condition Mos.1 & 2 exist and No. 3 General Emergency

- 2. With simultaneous loss of primary system integrity is possible:

3. With potential loss of containment integrity

l. 300 pol /cc iodine-equivalent determined by

.t chemical analysis

1

2. Primary system leak >1000 we indicated by SI flow >1000 we (F1-924 & F1-925) and pump discharge pressure corresponding to flow t

3. Minimum containment pressure suppression equipment is not available (any of the following):

' a. No fan coolers operating and <2 spray 1

Pumps.

b. No spray pumps operating and <2 fan coolers

c. <2 fan coolers running with I spray pump 4

4. " Containment press hi" lPI-945. PI-947 PI-949 (2/3 ?5 psig))

5. " containment spray" with 2/3 + 2/3 >25 psig lPI-945,PI-947,PI-949]

lPI-946,PI-948,PI-950]

6. Secondary Coolcnt Reduction in feedwater enthalpy incident 1. a. Decreasing feedwater temp indicated by Unusual Event Anomaly (FFDSAR 14.1.7) 70-418A & 70-438A on P-250 a_nd

b. confirmed by local temperature indicator on outlet of No. 5 feedwater heater.

2. Unexpected increasing power on excore nuclear instrumentation -

Steam line break with primary-to-secondary leak All of the following first-out reactor trip Alest rate in excess of to we panel annunciation with confirmation (FFDSAR 14.2.5)

- 1. Either:

a. " Steam line loop A Lo-l.o press"

[PI-468, PI-469, PI-482 (2/3 <530 psig)l or

b. " Steam line loop B Lo-Lo press"

[PI-478, PI-479, PI-483 (2/3 <530 psig))

^

. N EPIP !.1 Table 1-1 Page 5 Esergency

, Category Initiating Condition Indication Used Classification

2. Confirmed primary-to-secondary leak rate of at least 10 g o.

3. Either:

. a. " Steam line loop A isol channel alert" l [FI-464, FI-465 (1/2 >3.9mlos Ib/hr))

l or

, b. " Steam line loop B isol channel alert" lFI-474, FI-475 (1/2 >3.9 108 lb/hr)]

i i secondary Coolant Transient initiated by loss of feedwater, followed M of the following: General Emergency i Anomaly by loss of auxiliary feedwater for >l hour

! (FFDSAR 34.1.11) 1. Decreasing SG levels -

"A" SG [LI-461,LI-462,LI-463)

"B" SG [LI-471. LI-472, LI-473]

2. No auxiliary feedwater flow -

lFI-4002, FI-4007 F1-4014)

[F1-4036,FI-4037l

' 7. Abnormal Effluent Radiological effluent Technical Specification limits Airborne effluents only Unusual Event

,; exceeded but <10 times the limit (FFDSAR 14.2.3)

Radiological effluent Technical Specification limits Liquid effluents only unusual Event exceeded (FFDSAR 14.2.2)

Radiological ef fluents >10 times Technical Airborne effluents only , Alert Specification instantaneous limits. (An instan-taneous rate which, if continued for >2 hours, would result in a dose of about 1 mR at the site boundary under average meteorological conditions.)

8. Major Electrical Sustained loss of offsite power >l5 minutes All of the following: Unusual Event Failures (FFDSAR 14.1.2)

1. "4.16 kw bus undervoltage"

& 0 volts on A03 & A04 voltmeters.

2. XO4 to A03 ammeter on~CO2 (0 amps).

3. XO4 to A04 ammeter on C02 (0 amps)

EPIP 1.1 Table 1-1 Page 6 Emergency Category Initiating Condition Indication Used Classification Sustained loss of onsite AC power capability Both of the following: Unusual Event

(>l5 minutes)

1. "4.16 kv bus undervoltage" &

0 volts on A05 and A06 voltmeters and

, " Emergency Diesel Starting System Disabled

• for both Diesels Loss of all vital onsite DC power >l5 minutes Both of the following: Site Emergency ,

1. " Annunciator power failure" on 001, CO2, C03, and C04

2. <100 volts on the voltmeters for all batteries t .

Loss of offsite power and loss of all onsite AC @ of the following: Site Emergency power for >l5 minutes i

1. "4.16 kv bus undervoltage" 0 volts on A03, A04, 105. A06 & "Emerg Diesel starting system disabled" for both Diesels

. 2. XO4 to A03 ammeter on CO2 (0 amps)

3. XO4 to A04 ammeter on CO2 (0 amps)

Loss of offsite and all onsite AC power with loss of M of the folicwing: General Emergency all auxiliary feedwee r for >2 hours

1. Unit aux W meter 'XO2 on CO2 (019f)

2. Station aux lef meter XO4 on CO2 (0 lef)

3. XO4 to A03 ammeter on CO2 (0 amps)

4. XO4 to A04 amater on CO2 (0 amps)

6. XO2 to A01 ammeter on C02 (0 amps)

J 7. a. No auxiliary feedwater flow lFI-4036, FI-4037]

b. Decreasing SG level -

"A" SG lLI-461, LI-462, LI-463)

"B" SG (L1-471, LI-472, LI-473)

9. Control Room Evacuation Evacuation of control room >15 minutes & As required by DSS Site Emergency no control at remote shutdown station ,

10. Fire Fire in vital ar'ea or on the controlled side of plant As reported by Fire Brigade Chief Unusual Event lasting >IOminptesafterinitialuseoffire extinguishing equipment.

EPIP 1.1 '

Table 1-1 Page 7 Energency category Initiating condition Indication used classification Fire affecting I train of safety systems. As reported by Fire Brigade Chief Alert Fire affecting 2 trains of safety systems As reported by Fire Brigade Chief Site Emergency

11. Plant Shutdown Function Nonfunctioaal indications or alarms in the control Both of the following: Unusual Event room on primary system parameters requiring plant

1. " Annunciator power failure" on C04.

2. Failed indication as detesmined by DSS.

Turbine mechanical failure with consequences 1. Annunciator " Turbine supervisory." Unusual Event

2. Indication on TR-6019 of bearing vibration

>1 mils.

. 3. Bearing vibration alarm on back of C03.

I

4. Visual confirmation of turbine housing 4

penetration by a b'ade or disc.

Significant loss of effluent monitoring capability' & l. Loss of LW16 during a release Unusual Event meteorological instsuments which lapairs ability to or perform emergency assessment. Loss of effluent 2. Loss of R18 during a release monitoring may/may not require plant shutdown. or

3. a. Loss of wind speed indication or wind direction indication and *

b. Loss of R14 and RMS II Channel 1 or

c. Loss of RIS and CR9 and RMS II channel 5 or

d. Loss of R21 and RMS II channel 2 or

e. Loss of CWil2 and RMS II channel 6 Failure of reactor protection system to A of the following:

J Alert complete a trip which brings reactor subcritical Unplanned first out annunciator on C04 with confirmation from associated indicator and ,

intermediate range detector output not +

decaying and >l RCC RPI indicates fully i

withdrawn l

l

EPIP 1.1 Table 1-1 Page 8 Emergency category Initiating condition Indication used classification All alarms (annunciators) lost >15 minutes while unit 1. "Annucciator power failurt* on C01, CO2 & Alert is not in cold shutdown 1(2)C03, 1(2)C04 Loss of functions needed for cold shutdown for >4 g of the following: Alert hours while at cold shutdown

• 1. Loss of service water Unit ! = south & west header .

Unit 2 = north & west header

2. Loss of both trains of RHR

3. Loss of component cooling

12. Abnormal Radiation a. Effluent monitors detect levels corresponding to Airborne effluents only Site Emergency Levels at Site any of the following: ,

i (1) >50 mR/hr for \ hour Q (2) >250 mR/hr for \ hour for the thyroid (3) >500 mR/hr whole body for 2 minutes (4) >2500 mR/hr to the thyroid for 2 minutes l

! at the site boundary for adverse meteorology

b. Any of the above doses measured in the environs As reported to DSS by HP Supervisor

c. Any of the dose rates projected, based on plant parameters

a. Effluent monitors detect levels corresponding to Airborne effluents only General Emergency either:

(1) ! R/hr whole body (2) 5 R/hr thyroid at the site boundary under actual meteorological conditions

b. Either of the above doses measured in environs As reported to DSS by HP Supervisor

c. Either of above dose rates projected based on other plant parameters

13. Fuel ifrdling Accident Major damage to irradiated fuel in containment Both of the following: Alert

1. As reported to DSS by Core Loading Supvr.

2. Alarm on Victoreen on manipulator & alarm on R11

_ _ _ _ m ___________ _________

EPIP 1.1 Table 1-1 Page 10 Emergency Category gitiating Condition Indication Used classification

17. Natural Events Any earthquake Activation of >2 accelerographs Unusual Event

., Any tornado visible from site Verification by Operations Supervisor Unusual Event Low Lake Michigan water level With no CW pumps running, water level is 3.9' Unusual Event below O' on surge chamber level & confirmed by measuring forebay level at 10.9' below pumpImuse floor (7' level)

Earthquake greater than operating basis earthquake Earthquake with attendant structural damage of Alert containment or spent fuel pit any tornado striking the facility visual observation by operations Supervisor Alert Seiche near desi p level >6" of water in turbine hall Alert Winds in excess of desip levels Wind speed indicated as >100 mph Alert Wind with damage Structural damage to containment Site Emergency e

Failt.re of protection for vital equipment at low A_ny n of the following: Site Emergency leviels (i.e., caused by seiche > design levels)

1. >3' water in both EDG rooms.

2. >2' water in vital switchgear room.

3. >2' water in auxiliary feed pump room.

18. Reactivity Transient Uncontrolled rod withdrawal (FFDSAR 14.1.1 & 14.1.2) Unusual Event CVCS Malfunction (FFDSAR 14.1.5) Unusual Event Accidental criticality NRC Only (3)

P EPIP 1'.!

Table 1-1 Page 9 Emergency category Initiating condition Indication used Classification Fuel damage accident with release of radioactivity Both of the following: Alert to auxiliary building (FFDSAR 14.2.1)

1. As reported to DSS by Supvr in charge of fuel handling & drumming area vent (R21) 2.' Alarm on Victoreen on spent fuel pit bridge.

\ __

14. Serious or Fatal Injury Transportation of seriously or fatally injured Reported as judged by DSS Unusual Event individual from site to hospital (expect hospitalization for at least (Reference EPIP !!.1) 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />)

15. Security Threat Security threat or attempted sabotage Per MASP Per MASP & Appendices or I-Hour Red Phone only

• Ongoing security compromise (Open Line) (4)

16. Hazards to Plant Unusual aircraft activity over facility Visual observation of Operations Supervisor or Unusual Event operation security force

. Near or onsite exploalon or flammable or toxic gas As reported to DSS by plant personnel making Unusual Event release visual observation Missile impacts from any source on facility Visual observation by Operations Supervisor Alert Missile impact causing damage to two trains of safety systems Visual observation by Operations Supervisor Site Emergency A'ircraft crash in protected area (within the fence) Visual observation by Operations Supervisor Alert Known explosion damage to facility affecting plant Visual observation by Operations Supervisor Alert operation. Toxic or flammable gases in facility environment excluding normal process gases Toxic or flammable gases entering into vital areas visual observation by Operations Supervisor Site Emergency (control room, auxiliary building, etc.) excluding normal process gases 9

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