ML20039B965

From kanterella
Jump to navigation Jump to search
Public Version of Revised Emergency Plan Implementing Procedures 1004.11, Offsite Radiological Monitoring & 1004.2, Alert.
ML20039B965
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 12/02/1981
From:
METROPOLITAN EDISON CO.
To:
Shared Package
ML20039B961 List:
References
PROC-811202-01, NUDOCS 8112280121
Download: ML20039B965 (40)
v • d • e


Text

g _ ___ _ _ .

~

FOR:USE IN UNIT I ONLY 1004.11 Revision 2 IMPORTANT TO SAFETY NON-ENVIRONENTAL IMPACT RELATED CONTROLLED COPY FOR USE IN UNIT I ONLY THREE MILE ISLAND NUCLEAR STATION .

UNIT NO.1 EERGENCY PLAN IMPLEMENTING PROCEDURE 1004.11 M- T M-0FFSITE RADIOLOGICAL MONITORING Bq ,

Table of Effective Pages ,

Page Revision Page Revision Page Revision Page Revision 1.0 2 2.0 2 3.0 2 4.0 2 5.0 2 Unit i Staff Recomends Approval Approval Date Cognizant Dept. Head Unit 1 PORC Recomends Approval e a$ fw Chainnan of PORG Date // D /

4 Manager TMI I Approval

. Date /

f/

i V .

QA Modifications / Operations Mgr

. Date

~~ ~

m Document ID: 0002W paA22881Paaa8!!d USE IN UNIT l' ONLY = ;-

F PDR ,

. ~1

FOR.USE IN UNIT I ONLY 1004.11

._ Revision 2 12/02/81 N RONE MPACT RELATED CONTROLLED COPY FOR USE IN UNIT I ONLY THREE MILE ISLAND NUCLEAR STATION ghig h UNIT NO.1 EERGENCY PLAN IMPLEMENTING PROCEDURE 1004.11 W o 0FFSITE RADIOLOGICAL MONITORING Mb&

Table of Effective Pages Page Revision Page Revision Page Revision Page Revision 1.0 2 2.0 2 3.0 2 4.0 2 5.0 2 Unit 1 Staff Recomends Approval Approval Date Cognizant Dept. Head Unit 1 PORC Recomends Approval A 9 11 YLPtG Date // O /

Chaiman of PORC Manager TMI I Approval Date /

f/ '

v QA Modifications / Operations Mgr Date Document ID: 0002W i FORiUSE IN UNITI ONLY

6 l'OR.USE IN UNIT I ONLY 1004.11 Revision 2

^ THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EMERGENCY PLAN IMPLENENTING PROCEDURE 1004.11 0FFSITE RADIOLOGICAL MONITORING j 1.0 PURPOSE The purpose of this procedure is to provide guidance to radiation moni-toring teams for adequate offsite monitoring of radiation levels, follow-ing the accidental release of radioactive materials to the environment.

This procedure establishes monitoring team actions in order to supplement nonnal Health Physics procedures. The Radiation Monitoring Team is msponsible for implementation of the pmcedure.

2. 0 ATTACfNENTS 2.1 Attachment I, Radiation Survey Log 2.2 Attactinent II, Dosimeter Log 3.0 EMERGENCY ACTION LEVELS 3.1 This procedure is to be initiated upon any of the following condi-tions:
a. Alert (as determined by Alert procedure 1004.2).
b. Site Emergency (as determined by Site Emergency pmcedum 10 04.3).
c. General Emergency (as determined by General Emergency proce-dure 1004.4).
d. As directed by the Emergency Director.

4.0 _ EMERGENCY ACTIONS Initials 4.1 Proceed to the Processing Center and obtain an emergency kit, instrument kit, portable radio, and pager.

O FOR USE IN Lilt I ONLY

} FOR USE IN UNIT I ONLY 1004.11 Revision 2 4.2 Verify seals on the emergency kit and then operationally check radiation meters (Battery Check, Visual Inspection).

4.3 If seals am bruken, conduct a brief inventory of equipment.

4.4 Prior to leaving the Processing Center, conduct a radio check with the Radiological Asessment Coonfinator (RAC), in the Control Room, using Channel 3. Inform the RAC of your tele-phone pager number.

4.5 Obtain a designated emergency vehicle at the Processing Center.

4.6 Ensure your dose rate meter is turned on from the time you leave the Processing Center.

4.7 Proceed to the designated offsite monitoring location as directed by the RAC. (See offsite map or written directions to monitoring points in emergency kit, for specifically designated monitoring point locations).

4.8 Perfonn radiological surveys (as dimeted by the RAC) at the designated offsite monitoring location.

4.8.1 To perfonn dose rate surveys with the R0-2( A):

First take an open wiredow reading at waist level, then take a closed window mading at waist level. Enter these readings and duration of meter readings on the Attachment I. Calculate true Beta dose rate and enter this on Attachment I. Report closed window reading and true Beta dose rate to the RAC.

l l

l

' 2. 0 FOR USE IN .U. NIT 'I ONLY

F'OR 'USE IN UNIT I ONLY 1004.11

, Revision 2

4. 8. 2 Perfonn contamination surveys if dimeted by the RAC as

)

follows:

Obtain smears and coin envelopes from emergency kit, label envelope with date, time and location. Wipe the smear over a 100 cm2 (4 in. x 4 in.) ama. Count the smear with RM-14/HP210 if available and background is less than 300 CPM. If backgound is too high, move to an ama of acceptable background in onfer to count smears.

Enter gmss CPM and BKG CPM on Attachnent I. Subtract background from gross CPM to obtain net CPM. Report net CPM for each smear to the RAC. Save smears in coin envelopes for later analysis as directed by the RAC.

4.8.3 Perfonn air samples in accordance with Airborne Radioact-ivity Sampling and Analysis, Procedure 1004.31.

4.9 Call in sampling msults to the RAC and await further instnJc-tions.

4.10 If radio comunications am lost and the pager is activated, attempt to re-establish radio comunichtfons with the RAC. If radio communications cannot be re-estolished, attempt to contact another monitoring team to miay infonnation. If contact cannot be established, drive to the nearest telephone and cal; the RAC t. [ortheEACC (if transfer has been made) at _

. __/

4.11 Minimize personnel exposums by moving out of areas of high radiation when recording data or awaiting further instructions by the RAC.

)

3.0 FOR USE IN UNIT I ONLY l

FOR.USE IN UNIT I ONLY 1004.11 Revision 2 4.12 Ensum all team members keep track of their exposum on Attachment II.

4.13 Maintain all completed Attachment I for permanent records.

Request dimetion fmm the RAC as to the disposition of these completed fonns.

4.14 When the Environmental Assessment Comand Center (EACC) is

activated and takes control of offsite monitoring, begin reporting offsite surveys to the E^CC.

4 4.15 Ensum that all samples am mturned to the EACCfor further JAk analysis and retention.

I 4.16 Notify the RAC/EACC when approaching 300 mREN. Recommend to the RAC/EACC that your team be relieved if possible. Relief

, should be conducted in a low radiation ama.

O s o et"^' co"ot'to"s 5.1 Offsite radiation monitoring established, being maintained and contmiled by the EACC.

O 4.0 FOR USE IN UNIT I ONLY

~ N , ..

(J J

~

1004.11 .

Revision 2 T-ATTACHENT I Q

U

: :Open  : Duration : Closed : Duration :  :  :  :  :

~

Location:  :  : Window : of Meter : Window : of Meter :True s*:  :  :  : Activity b Number : Date : Time :8vmR/hr: Reading : ymR/hr : Reading :mR/hr. : CPM (gross): CPM (bkgd):Vol (f3 t ):(uCi/cc) @

T  :  :  :  :  :  :  :  :  :  :  : m Q  :

~

2  :  :  :  :  :  :  :  :  :  :  : 2 C  :  :  :  :  :  :  :

C

@  :  :  :  :  :  :  :  :  :  :  : Z m  :  :  :  :  :  :  :  :  :  :  : -

H 2  :  :  :  :  :  :  :  :  :  :  :

~

(2  :  :  :  :

Q Z  :  :  :  :  :  :  :  :  :  :  : 2

__  :  :  :  :  :  :  :  :  :  :  : i H'

:  : g

~~  :  :  :

O  :

23  :  :  :  :  :  :  :  :  :  :  :

[--  :  :  :  :  :  :  :  :  :  :  :

4  :

  • (sy-y) x CF = mrad /hr (true 8-)

Radiac Inst. S/N and Type Cal. Due Beta Correction Factor CF Air' Sampler S/N Flow Rate (CFM) Counting Inst. Used S/N Cal. Due Date Tech S.0

5: )

FOR USE IN UNIT l ONLY l

- 1004.2 Revision 6 12/02/81 ps IMPORTANT TO SAFETY CONTROLLED COPY FOR V NON-ENVIRONENTAL IMPACT RELATED USE IN UNIT I ONLY THREE MILE ISLAND NUCLEAR STATION UNIT NO.1 EMERGENCY PLAN IMPLEENTING PROCEDURE 1004.2 O//p g M mg ALERT Q() d Table of Effective Pages Page Revision Page Revision Page Revi sion Page Revision 1.0 0 21.0 6 2.0 6 22.0 6 3.0 6 23.0 0 4.0 6 24.0 0 5.0 6 25.0 2

, 6.0 6 26.0 0 7.0 6 27.0 0 8.0 6 28.0 0 9.0 6 29.0 0 10.0 6 30.0 6 11.0 6 31.0 6 12.0 6 32.0 6 13.0 0 33.0 6 14.0 6 15.0 0

( 16.0 0 17.0 3 18.0 3 19.0 6 20.0 3 Unit 1 Staff Recommends Approval Approval Date Cognizant Dept. Head Unit 1 PORC Recomends Approval e nu Date // o /

I Chairman of PORC Manager TMI I Approval D,.,, .

h Date /8 [

V QA Modifications / Operations Mgr

/ Date D 0024W FO R U SE IN U NIT I ON Liument ID:

FOR USE IN UNIT I ONLY 1004.2

, Revision 0

. THREE MILE ISLAND NUCLEAR STATION UNIT 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.2

-(q~j ALERT 1.0 PURPOSE The purpose of this procedure is to define the conditions that shall be regarded as an Alert for Three Mile Island Nuclear Station (Unit I) and to:

a. Ensure necessary actions are taken to protect the health and safety of the public.
b. Ensure necessary actions are taken to notify GPU-Nuclear management and offsite emergency response organizations.
c. Mobilize the appropriate portions of the emergency response organization to initiate appropriate emergency actions.

The Emergency Director is responsible for implementing this procedure.

NOTE: Emergency Director responsibilities that may not be delegated include:

a. Decision to notify offsite emergency management agencies.
b. Making protective action recommendations as necessary to offsite i

emergency management agencies.

c. Classification of Emergency Event.
d. Determining the necessity for onsite evacuation.
e. Authorization for emergency workers to exceed 10 CFR 20 radiation exposure limits.

2.0 ATTACHMENTS 2.1 Attachment I, Alert Notifications 2.2 Attachment II, Emergency Status Report O

FOR USE IN' UNIT I ONLY

w FOR USE IN UNIT I ONLY 1004.2 Revision 6 p 2.3 Attachment III, Checklist for Notification of Significant Events V ,

'Made In Accordance with 10 CFR 50.72.

3.0 Emergency Action Levels INITIATING CONDITION INDICATION 3.1 l' '1 cladding failure As indicated by any one of the following.

a. Reactor coolant activity

> 130 uCi/ml but < 300 iici /ml as sampled and analyzed.*

b. RM-L1 (High) reading >

2.9 x 103 cpm but <

6.66 x 103 cpm.

c. RM-L1 (Low) reading >

1.65 x 105 cpm but <

3.81 x 105 cpm.

3.2 Primary to secondary leakage As indicated by valid high

> Igpm but <50 gpm. alarms on RM-A5 and/or the Steam Line Monitor

  • in conjunction with reactor f%

U /

coolant loss not otherwise identifiable as determined by daily leak rate test.

3.3 Primary coolant leak rate of As indicated by increased greater than 50 gpm. makeup flow in excess of letdown flow by 50 gpm or makeup tank level decreasing at approximately 2 inches per minute.

3.4 Radiation levels or radioactive As indicated by either:

contamination which indicate a a. Valid, unanticipated high severe degradation in the control alarms on any two area of radioactive materials. and/or process radiation monitors (RMA, RML or RMG monitors) at the same time,

b. Receipt of a validated report of airborne or waterborne contaminants as determined by sample and analysis or general radiation readings as determined by periodic survey to have increased by a factor of 1000 above normal.

I FOR USE ilV UNIT l ONLY l

FOR USE IN UNIT I ONLY 1004.2 Revision 6 3.5 Loss of all offsite power As indicated by a reactor trip f's c incident with a loss of caused by loss of power and J Diesel Generators for less trouble alarms on both Diesel that 15 minutes. Generators neither of which energizes the ID or IE 4 kV busses.

3.6 Loss of all onsite DC power All Battery Voltmeters read for less than 15 minutes. zero and there is no light or control p'wer available.

3.7 Reactor coolant pump locked As indicai.ed by both of the rotor at power leading to fuel following:

failure. a. Receipt of a valid RCP Stator Temp High alarm (150*C) and decreasing flow in the affected loop.

b. Reactor Coolant specific activity as determined by sample and analysis is >

50 uCi/ml but <130 uCi/iiil.

3.8 Complete loss of any function As indicated by a total loss needed for plant cold shutdown, of any of the following:

a. Source and intermediate N

range nuclear instrumen-tation.

b. A loss of forced reactor coolant system flow (includes Deca Removal Pumps,y Heat Reactor-Coolant Pumps, etc.)

coincident with total loss of ability to feed 0TSG's.

3.9 Failure of the reactor protection Any reactor trip setpoint system to initiate and complete a being exceeded with no rod trip when required. in limit lights.

3.10 Fuel damage accident with release An accident occurs while of radioactivity to the contain- handling spent fuel during ment of fuel building. refueling or while moving objects over the spent fuel pool which causes any one of the following:

a. A valid High alarm on RM-A2.
b. A valid Alert ' alarm on RM-A4.
c. A valid Alert alarm on RM-A8.

A 3.0 FOR USE IN UNIT I ONLY m . - - - .....-.. ., - ..- - -- .-

FOR USE IN UNIT I ONLY

, 1004.2 Revision 6

d. A valid High alarm on RM-A13.
e. A valid High alarm on RM-G7.
f. A valid High alarm on RM-G9.
g. A valid increase by a factor of 100 of atmos-pheric activity as determined by sample and analysis.

3.11 Any fire jeopardizing the As judged by the Shift operability of any safety system Supervisor.

3.12 Most or all annunciators lost As' judged by the Shift which may involve an actual or Supervisor, potential substantial degradation of the level of safety of the plant.

3.13 Radiological effluent activity As indicated by any of the exceea the Environmental technical following validated by sample specification instantaneous limits. and analysis:

a. RM-A8 (gas) > 2.0 x 104 g cpm (High alarm) but <

Q 1.0 x 105 cpm.

b. RM-A9 (gas) > 4.5 x 104 cpm {highalarm)but<3.0 x 10 cpm.
c. RM-A5 > 1.0 x 106 cpm.*
d. RM-A8 Ti dine) increase >-

8.5 x 10 cpm / min but <

4.5 x 10 cpm / min.*

e. RM-A9 (i dine) increase >-

2.5 x 10 cpm / min but <

1.2 x 10 cpm / min.*

f. Offsite Radiological Monitoring Team report >

10 mR/hr (gama) but <5U mR/hr at any offsite location.

g. RM-L7 > 4.8 x 105 cpm (high alarm).
h. RM-G8 > 6.0 x 103 mR/hr.

3.14 Ongoing security compromise. Shift Supervisors judgement, based on advice of Security Duty Sergeant.

J FOR USE IN'fJNIT I ONLY

FOR USE IN UNIT I ONLY

, 1004.2 Revision 6

, 3.15 Severe natural phenomenon As indicated by any one of the

) being experienced. following:

a. Valid alarm on PRF 1-3,

" Operating Basis Earth-quake".

b. Actual river stage > 302 feet but < 307 feet at the River Water Intake Structure.
c. Any tornado striking facility.
d. Hurricane winds > 75 mph as indicated on the Wind Speed Recorder (NDS-501).

3.16 Other hazards being experienced. As indicated by any one of the following:

a. Aircraft crash or other missile impact within the protected area or onto an permanent plant structure.
b. Know explosion damage to any permanent plant structure.
c. Release of toxic or s, flammable gasses into the

,) plant which, in the judgement ,of the Shift Supervisor, affects the safe operation of the plant.

d. Turbine failure resulting in casing penetration.
e. Any fire in a permanent plant structure which requires offsite fire-fighting capability.

3.17 Non-isolable steam leak that As indicated by a Steam Line results in a rapid depressuri- Rupture System actuation (<600 zation of the steam system, psig) on the affected 0TSG.

3.18 Evacuation of control room antici- Shift Supervisor's judgement.

pated or required with control of shutdown systems established from local stations within 15 minutes.

3.19 Reactor Coolant System hot leg As read on Reactor Coolant temperature is > 620*F in either Outlet Temperature indication.

loop.

n v

FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY 1004.2 Revision 6 3.20 Reactor Power to Flow to Imbalance Any condition whereby the

(')

V outside of the Technical Specifi-cation Limit curves.

Technical Specification Safety Settings set forth in Figure 2.1-2 are exceeded without a reactor trip and confirmed by engineering analysis.

3.21 Reactor Building Pressure Reactor trip and ECCS

-> 4.0 psig, but <30 psig. initiation due to high Reactor Building pressure.

3.22 More than one control rod Stuck- As indicated by a loss of the Out, Stuck-In or Dropped ability to meet any of the requiring shutdown by Technical conditions of Technical Specifications. Specification Limiting Condition for Operation 3.5.2.2 for more than one control rod.

3.23 Secondary system activity As indicated by sample and

> 1.0 uCi/ml (1-131 equivalent). analysis.

3.24 Control Rod Ejection. As indicated by a Reactor Trip due to high neutron flux in coincidence with loss of coolant indications.

I,)

V 3.25 Other plant conditions exist Whenever plant conditions that warrant precautionary warrant it, as judged by the activation of Technical Support Shift Supervisor / Emergency Center and placing near-site Director.

Emergency Operations Facility and other key emergency personnel on standby.

These indications may be determined via instrumentation that will be installed or expanded as required by NUREG 0578 prior to restart.

4.0 EMERGENCY ACTIONS Initials 4.1 Upon recognition that any of the above action levels have been reached or exceeded, the Shift Supervisor / Duty Section Superintendent assume the duties of the Emergency Director.

(Event should be assessed and declared within 10 minutes of its occurrence.)

/m

./

6.0 FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY

' 1004.2 Revision 6 4.2 Announce to Control Room personnel that has

(^')

v (name) assumed the duties of Emergency Director.

4.3 Announce, or have announced, the following message over the public address system (merged):

NOTE: Turn on Whelen siren switch.  :

" ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL: AN ALERT HAS BEEN DECLARED IN UNIT 1. ALL MEMBERS OF THE ONSITE EMERGENCY ORGANIZATION REPORT TO YOUR STATIONS. ALL OTHER PERSONNEL AWAIT FURTHER INSTRUCTIONS." (If emergency is radiation-oriented add: "There will be No Smoking, Orinking, or Eating until further notice.") (Give a brief description of the event and repeat the announcement).

4.4 If emergency is radiation-oriented, direct that the Radiation

[a)

Emergency Alarm be sounded.

NOTE: Turn off Whelen siren switch after alarm has been  :
sounded.  : .

4.5 Assign a Communications Assistant to make notifications to persons and/or agencies per Attachment I,Section I.

4.6 Contact the Duty Section Superintendent and discuss: l (a) Plant status (b) Which members of the Duty Section are required to augment the Onsite/0ffsite Emergency Orgari2aticn.

4.7 Assign a Communications Asr.istant and direct him to perform l

all applicable steps of 1004.8.

3 (J

l FOR USE IN'tJNIT l ONLY

n - -.

FOR USE IN UNIT I ONLY

, 1004.2 Revision 6 4.8 Depending on the emergency action level which was reached or exceeded, ensure that the appropriate Emergency Operating Procedures have been implemented and/or the following Emer-gency Plan Implementing Procedures as required:

(a) Contaminated Injuries and Radiation Overexposure (1004.16).

(b) High Winds - Tornado /High Winds (1004.22) 4.9 If local services (fire, ambulance, police) are required, l direct the Comunicator to notify Dauphin County Emergency Operations Center and request the appropriate assistance.

Notify Security (N/S Gate) to begin preparations to expedite entry of responding emergency personnel (Police / Fire /

Ambulance). Security should be advised to implement procedure 1004.19 Emergency Security /Dosimetiry Badge Issuance.

NOTE: If the Emergency Response personnel ire required to  :
respond outside the protected area affected by a  :
radioactive plume the Emergency Director or his  :
designee will direct the issuance of TLD's from the  :
North or South gate.  :

4.10 If changes in onsite or offsite radiation levels are expected, direct the Radiological Assessment Coordinator to:

(a) Dispatch offsite and/or onsite radiation monitoring teams in accordance with EPIP's 1004.10 and 1004.11.

(b) Implement Offsite Dose Projections procedure (1004.7).

4.11 Activate the Technical Support Center, procedure (1004.28), l and the Operations Support Center, procedure (1004.29).

O FOR USE IN*dJNIT I ONLY

FOR USE IN UNIT I ONLY

  • 1004.2 Revision 6 4.12 If additional resources or notifications are required, refer Os to additional Assistance and Notifications procedure (1004.6).

4.13 If the emergency involves in-plant health physics problems, direct the Radiological Assessment Coordinator to implement In-Plant Radiological Controls During Emergencies (1004.9).

4.14 Assign an individual to complete Attachment II,Section I and give it to the Radiological Assessment Coordinator to transmit to the Bureau of Radiation Protection.

4.15 Direct the Radiological Assessment Coordinator to complete l Attachment II,Section II to transmit to the Bureau of Radia-tion Protection if a radioactive release has occurred or is occurring.

4.16 Verify that communications and documentation are maintained l per procedure Communications and Recordkeeping (1004.5).

4.17 If applicable, direct the Operations Coordinator to dispatch l Emergency Repair /0perations personnel to investigate the identified problem area in accordance with Emergency Repair /

Operations procedure 1004.21.

4.18 After 30 minutes, confirm that BRP verification has been made. If no verification, instruct the communicator to proceed to Attachment I, Section 1.2 (d).

4.19 Instruct the Radiological Assessment Coordinator to provide ongoing dose estimates for actual releases to the Bureau of Radiation Protection.

O FOR USE IN'DNIT I ONLY

~

FOR USE IN UNIT I ONLY 1004.2 Revision 6 4.20 Evaluate dose projections and estimates and if necessary, l reconnend protective actions to the BRP consistent with the guidelines in Attachment I,Section IV.

4.21 Based upon assessment of plant conditions, either close out the Alert, escalate to a higher class of emergency or down-grade to a lower class.

(a) If Recovery Phase criteria have been met (see Recovery Procedure 1004.24), close out the Alert by performing the notifications in Attachment I,Section III. Implement the Recovery Procedure (1004.24).

(b) If Recovery Phase criteria have not been met, but Alert emergency action levels are no longer being exceeded, de-escalate to an Unusual Event by notify-ing BRP on the Radiological Line and perform the remaining notifications in accordance with the Unusual Event procedure (1004.1).

(c) If emergency action levels exceed those for an Alert, escalate to a higher class, notify BRP on the Radiological Line and make the remaining notifica-tions in accordance with the appropriate emergency procedure as specified in Step 5.1.

4.22 If necessary, due to potential contamination of normally  !

non-contaminated sumps and/or tanks, or the need to closely monitor liquid releases, initiate procedure (1004.14), Moni-toring/ Controlling Liquid Discharges.

FOR USE IN tJNIT I ONLY

a FOR USE lN UNIT I ONLY 1004.2 Revision 6 5.0 FINAL CONDITIONS 5.1 A higher class of emergency has been declared by the Emergency Director,after meeting or exceeding an emergency action level of one of the higher classes and one of the following proce-dures is being implemented.

a. Site Emergency (1004.3)
b. General Emergency (1004.4) 5.2 A lower class of emergency has been declared by the Emergency Director and Unusual Event procedure (1004.01) is being implemented.

5.3 The Alert has been closed out since no recovery operations are required.

5.4 The Alert can be shifted to a recovery mode'by implementing the procedure Recovery Operations (1004.24).

DATE SIGNATURE OF PERSON RESPONSIBLE FOR IMPLEMENTING THE PROCEDURE L

'O FOR USE IN t3 NIT I ONLY

FOR USE IN UNIT I ONLY ~  !

1004.2 l Revision 6 ATTACHMENT I j

.]

Section I Initial Contact l The Communicator shall notify the following agencies and personnel and update the Attachment I,Section II checklist for each notification.

Initial

1. Dauphin County Emergency Operations Center (If this is a reclassification notification, first advise BRP via Radiological line then unaffected Control Room) go to Item 3.
a. Telephone: _

~

1) 11 no contact, activate Dauphin County ratiio system. l
b. MESSAGE:

This is (name/ Title) at the Three Mile Island Nuclear Station Unit I calling. We have declared'an Alert at (time) hours.

(Based upon Emergency Director judgment, deliver one of the following statements):

1) We have not had a radioactive release OR
2) We have had a radioactive release, but do not expect this situation to result in detectable changes in offsite radiation levels, OR

)

FOR USE IN'L3 NIT I ONLY

FOR USE IN UNIT I ONLY 1004.2 Revision 0 ATTACHMENT I I{C/ SECTION I Initial Contact Initial

3) We have had a radioactive release, but do not know if there will be a detectable change in offsite radiation levels. We will be keeping the Bureau of Radiation Protection informed of the results of our investigation, OR
4) We have had a radioactive release and expect to be able to detect changes in offsite radiation levels, but they are expected to be less than the levels calling for a Site Emergency. We will be keeping the Bureau of (a' Radiation Protection informed.
c. Give a short non-technical description of the emergency and the extent of the radioactive release and the affected populations and area.
2. Pennsylvania Emergency Management Agency (PEMA)

(If this is a reclassification notification, go to Item 3 Unaffected Control Room.)

b 3

FOR USE IN t3 NIT I ONLY

FOR USE IN UNIT I ONLY 1004.2 Revision 6 3 ATTACHMENT I Section !

Initial Contact Initial

a. Telephone: (A diverter forwards this call to PEMA Duty Officer after working hours.)

NOTE If no contact, proceed to step 2.d.  !

b. MESSAGE:

This is Three ' .le Island Nuclear Station Unit 1 calling. We have an emergency. Give me the Operations Duty Officer.

(When Outy Officer answers:)

This is (name/ title) at the Three Mile Island Nuclear Station

) Unit 1 calling. We have declared an Alert at (time) hours.

We request you contact Bureau of Radiation Protection. Bureau of Radiation Protection callback should be made on the Radio-logical Line or 7 -(Based upon Emergency Director judgment, deliver one of the following statements):

1) We have not had a radioactive release, OR

)

4 l

FOR USE IN t3 NIT I ONLY

---,~,e . - , , - -

FOR USE IN UNIT 1 ONLY 1004.2 Revision 0 ATTACHMENT I C J SECTION I Initial Contact

2) We have had a radioactive release, but do not expect this situation to result in detectable changes in offsite radiation levels, OR
3) We have had a radioactive release, but do not know if there will be detectable changes in offsite radiation levels. We will be keeping the Bureau of Radiation Protection informed of the results of our investigation, OR
4) We have had a radioactive rele3se and expect to be able to detect changes in offsite radiation levels but they

[gs) will be less than the levels calling for a Site Emergency. We will be keeping the Bureau of Radiation Protection informed.

c. Give a short non-technical description of the emergency, and any potentially affected populations and areas:

7 FOR USE IN 5dNIT I ONLY

l s

FOR USE IN UNIT I ONLY 1004.2

. Revision 0 ATTACHMENT I c SECTIG1 I Initial Contact Initial

d. If PEMA is unable to be contacted, contact Dauphin County; advise them that PEMA cannot be contacted and direct them to notify PEMA, BRP, and Lancaster, York, Lebanon, and Cumberland counties.
e. Message verification:

Expect Bureau of Radiological Protection (BRP) contact after PEMA notification. If no BRP confirmation is received within 30 minutes, notify PEMA of the situation. If unable to

contact PEMA (line busy) call Dauphin County and notify them that BRP has not verified initial contact. Request Dauphin County to contact PEMA and/or BRP.
3. Unaffected Control Room x_.
a. Te le ph onei ___ j or inter Control Room Hot Line.
b. Message: Give a brief description of plant status to Shift Supervis or, f>

t FOR USE IN 6L9 NIT I ONLY

j FOR USE IN UNIT l ONLY 1004.2

- Revision 3 l

!' ATTACHMENT I i

4 O SECTION I Initial Contact i l Initial l l

l 4) Institute of Nuclear Power Operations l

- .(Do not notify if this is a reclassification i

j notification.)

a. Telephone: u j ._-

b.' MESSAGE:

This is at Three Mile Island j (name/ title) i Nuclear Station Unit I calling. We have declared an h (Give a brief description of

') , Alert.at hours. l (time) the emergency.)
5) Notify the following personnel / agencies if the emergency situation is such that notification is deemed appropriate.

a Hershey Medical Center -

Notification to be performed per procedure 1004.16. l V

l .

FOR USE IN UNIT I ONLY

, 17.0 s

FOR USE IN UNIT I ONLY 1004.2

. Revision 3 ATTACHMENT I SECTION I Initial Contact Initial

~

b. Pennsylvania State Policd -

MESSAGE:

This is at the Three Mile Island (name/ title)

Nuclear Station Unit I calling. We have declared an Alert at hours. We had a (time) (have/have not) radioactive release. We require assistance as follows: (State any assistance required.)

{ c. Radiation Management Corporation

. Emergency number < ).

MESSAGE:

This is at the Three Mile Island Nuclear (name/ title)

Station Unit I calling. We have declared an Alert at hours. (Give a brief description of the (time) l l

i i

l FOR USE IN UNIT I ONLY 18.0

FOR USE IN UNIT I ONLY 1004.2 Revision 6 ATTACHMENT I Section l' Initial Contact

, Initial emergency). We had a radioactive (have/have not) release.

^'

d. American Nuclear Insurers or (afteFnormal wur a nig lours)

Message:

This is at the Three Mile Island Nuclear (name/ title)

Station Unit I calling. We have declared an Alert

)

at hours (Give a brief description of the (time) emergency).

We had a radioactive release.

(have/have not)

DATE TIME OF COMPLETION COMPLETED BY f ~')

FOR USE IN"dNIT I ONLY

FOR USE IN UNIT I ONLY 1004.2 Revision 3 ATTACHMENT I SECTION I Initial Contact Initial

4. Nuclear Regulatory Commission (NRC) - Bethesda, MD.

(Continuous communications with the NRC will be maintained following contact.)

a. Telephone: NRC Emergency Notification System (ENS)

(RED PHONE)

b. MESSAGE:

This is at the Three Mile Island Nuclear Station (name/ title)

E' ,

Unit I calling. We have declared an Alert at hours.

~

(time)

(Based upon Emergency Director judgment, use one of the following statements):

1) We have not had a radioactive release OR
2) We have had a radioactive release but do not expect this situation to result in detectable changes in offsite radiation levels.

OR f-FOR USE IN20.0UNIT I ONLY m _ - - _ - _ _ - -

FOR USE IN UNIT l ONLY 1004.2 Revision 6 ATTACHMENT I r3 O Section I Initial Contact 1

Initial )

3) We have had a radioactive release but do not know if there will be a detectable change in offsite radiation '

levels. We will be keeping the Bureau of Radiation Protection informed of the results of our investigation.

4) We have had a radioactive release and expect to be able to detect changes in offsite radiation levels but they will be less than the levels calling for a Site Emer-gency. We expect the levels to be <50 mrem /hr (gamma).

We will be keeping the Bureau of Radiation Protection f,s) informed. (Give a short non-technical description of the emergency and the extent of the radioactive release, if appropriate).

DATE TIME OF COMPLETION COMPLETED BY

NOTE: After initial NRC notificaion is complete per  :
Attachment I,Section I above; Refer to the NRC  :
Notification Checklist, Attachment III. This  :
Checklist contains information desired by the NRC  :
and may be helpful in providing follow-up  :
information.  :

'O' 21.0 FOR USE IN UNIT 1 ONLY

-s

(\-) fs

'd T

1004/-)

R::vidv.J 6 ATTACHMENT I Ti SECTION II Q NOTIFICATION CHECKLIST

TIME OF INITIAL NOTIFICATION TIME OF  : {
OR ESCALATION DE-ESCALATION OR CLOSE OUT  : @

T  ::  : rn O: :  ::UNU5UAL:  : SIIL  : GENERAL :: UNUSUAL:  : SIIt  : GENERAL : _

y AGENCY  :: EVENT : ALERT : EMERGENCY : EMERGENCY:: EVENT : ALERT : EMERGENCY : EMERGENCY :

:  :  : 7
Dauphin County'  :  :  :  :  :  :  :

[  :

@ : PEMA  ::  :  :  :  ::  :  :  :  : 2

. IT1 :  ::  :  :  :  ::  :  :  :  : -

^

_  : Unit 2 Control Room  ::  :  :  :  ::  :  :  :  : H 7  : INP0

{  :

NRC Q

l 2  :  ::  :  :  :  ::  :  :  :  : 2

Hershey Medical Center :: *: *: *: * ::  :  :  :  : I d  :  ::  :  :  :  ::  :  :  :  : 4

_: State Folice  :: *: *: *:  ::  :  :  :  :

Q: RMC  :: *: *: *: * ::  :  :  :  :

ANI  :: *: *:  :  ::  :  :  :  :

I~ :  ::  :  :  :  ::  :  :  :  :

N  : B and W  :: N/A : N/A :

5 Affected Counties  :: N/A : N/A : N/A  :  ::  :  :  :  :
  • Optional 22.0

FOR USE IN UNIT I ONLY 10CS.2 Revision 0 ATTACHMENT I lh b SECTION III Secondary Contact Initial The Communicator shall notify the following agencies and personnel and update the Attachment I,Section II checklist for each notification.

1. Bureau of Radiation Protection
a. Telephone: Radiological Line
b. MESSAGE:

This is at the Three Mile Island Nuclear Station (name/ title)

Unit 1. We have closed out the Alert at hours and (time) initiated recovery operations. Please notify PEMA, Dauphin, (s ')

Lancastar, York, Lebanon and Cumberland counties.

l 2. Unaffected Control Room l _--_. _

a. Telephone: , , _ _
b. Message: Notify Shift Supervisor of Close out of the Alert.

! 3. Nuclear Regulatory Commission Office - Bethesda, Md.

l a. Telephone: Emergency Notification System (ENS)

(REDPHONE) 1 r

!6 FOR USE IN2ONIT I ONLY

FOR USE IN UNIT I ONLY 1903.2 Revision 0 ATTACHMENT I SECTION III Secondary Contact Initial

b. MESSAGE:

This is at the Three Mile Island Nuclear (name/ title)

Station Unit 1. We have closed out the Alert at hours (time) and initiated recovery operations.

4. If applicable, notify the following persons and/or agencies of close out of the Alert:
a. Hershey Medical Center:
b. Pennsylvania State Police: A
c. Radiation Management Corporation (RMC):

4N s

-~s

d. American Nuclear Insurers:\ ..
e. Others - as directed by the Emergency Director.

DATE TIME OF COMPLETION COMPLETED BY l

FOR USE IN24L9 NIT I ONLY

FOR USE IN UNIT l ONLY 1004.2 Revision 2 ALERT ATTACHMENT I SECTION IV PROTECTIVE ACTION RECOMMENDATION GUIDELINES THESE RECOMMENDATIONS MAY BE DELIVERED ONLY BY THE EMERGENCY DIRECTOR

1. Consideration shall be given to sheltering if:
a. Release time is expected to be short (Puff release, <2 hours) and
b. Evacuation could not be well underway prior to expected plume arrival due to short warning time, high wind speeds, and/or foul weather.
2. Consideration shall be given to evacuation if:
a. A release is expected to occur with projected doses approaching cr C exceeding:

1 Rem Whole Body and/or 5 Rem Child Thyroid and

b. Release time is expected to be long (>2 hours) and
c. Evacuation can be well underway prior to plume arrival for above release, based upon wind speed and travel conditions.

l

' 25.0 FOR USE IN UNIT I ONLY

n FOR USE IN UNIT I ONLY

- c, 1004.2 Revision 0 ATTACHMENT 11 t

EMERGENCY STATUS REPORT Section I

1. Description of emergency:
2. Has the Reactor tripped Yes/No
3. Did the Emergency Safeguards System; actuate Yes/No If so, which ones (a) High Pressure Injection Yes / No (b) Low Pressure Injection Yes/No (c) Core Flood Yes/No (d) 4 No. Reactor Building Isolation Yes/No (e ) Reactor Building Cooling Yes/ No
4. What is the status of the plant (a) At power (b) Hot Standby (c) Hot Shutdown (d) Cooling Dwn (e ) Reactor Pressure psig (f) Reactor temperature *F 6

FOR USE IN26 UNIT I ONLY

x FOR USE IN UNIT I ONLY

. 1004.2 Revision 0 ATTACHMENT Il

' EMERGENCY STATUS REPORT Section I

5. Is offsite power available Yes/No
6. Are both diesel generators operable Yes /No
7. Have any personnel injuries occurred Yes / No (a) If so, is the injured person (s) contaminated Yes / No (1) What are the approximate radiation and/or contamination levels mR/hr 2

DPM/100 cm

8. Are these excessive radiation levels and/or contamination Levels Yes/No (a) If so, List below:

(1) Radiation Levels (Whole Body) 2 (2) Contamination levels DPM/100 cm at location:

DATE TIME COMPLETED BY 0;

FOR USE IN27tdNIT I ONLY

FOR USE IN UNIT I ONLY 1004.2 Revision 0

~

ATTACHMENT II EMERGENCY STATUS REPORT Section II Fill out if a release has (is) ocurring. Provide BRP all available information for verification call.

1. What is the approximate radioactive source term discharge rate from the plant (As determined by the Projected Dose Calculation procedure (1004.7 ) . )

(a) Noble gases Ci/sec (b) Iodine Ci/sec

2. What is the approximate meteoralogy (a) Wind speed mph (b) Wind direction (c) Stability Class-Stable /teutral/ Unstable
3. What is the projected whole body dose rate and iodine concentration at the nearest offsite downwind point (a) mR/hr (b) uCi/cc Iodine (c) (Location)
4. Estimated duration of the release L

FOR USE IN28 UNIT I ONLY

' TOR USE IN UNIT I ONLY 1004.2-Revision 0 ATTACHMENT II EMERGENCY STATUS REPORT Section II (a) If the release is terminated:

,. Si.ari. L ine Si.up tine i

Duration (b) If the release is still in progress:

Start Time ' Estimated duration (hrs / min /sec)

. 5. (a) Based on projected dose rates, iodine concentration anc: duration or estimated duration (if still in progress) of the release, will the lower limits of the EPA Protective Action Guides be exceeded (i.e.,

1 Rem Whole Body, 5 Rem Child Thyroid.

Yes/No (b) If yes, estimate time to exceeding PAG: hours i

i h

O

~f r

l FOR USE IN29L4 NIT I ONLY W_

e

.,FOR USE IN UNIT I ONLY 1004.2 Revision 6 r'~~ ATTACHMENT III (s

CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS PADE IN ACCORDANCE WITH 10 CFR 50.72 A. Identifitstion:

Date Time Name of Person Making Report Licensee Facility Affected Applicable Part of 10 CFR 50.72 B.

Description:

Date of Event Time Description of What Happened C. Consequences of Event: (Corplete depending on type of event)

Injuries Fatalities Contamination (personnel) (property)

(x,

(./ Overexposures (known/possible)

Safety Hazard (describe - actual / potential)

Offsite Radiation Levels Integrated Dose Location Meterology (wind speed) From (direction)

Weather Conditions (rain, clear, overcast, temperature)

Equipment / Property Damage D. Cause of Event:

o)

FOR USE INS UNIT I ONLY

- ,FOR:USE IN UNIT l ONLY 1004.2 Revision 6 ATTACHMENT III CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS MADE IN ACCORDANCE WITH 10 CFR 50.72 E. Licensee Actions:

Taken Planned Emergency Plan Activitated (Yes/No) Classification of Emergency 1 Resident Inspector Notified (Yes/No) -State Notified (Yes/No)

Press Release Planned (Yes/No)_ ., _ News Media Interest (Yes/No) local / National F. Current Status: (Complete depending on type of event)

1. Reactor Systems Status Power Level Before Event 'After Event Pressure Temp. (thot) (tcold)

RCS Flow (Yes/No) Pumps On (Yes/No)

Heat Sink: Condenser Steam Atm. Dump Other Sample Taken (Yes/No) Activity Level ECCS Operating (Yes/No) ECCS Operable (Yes/No)

ESF Actuation (Yes/No)

PZR or RX Level Possible Fuel Damage (Yes/No)

S/G Levels Feedwater Source / Flow Containment Pressure Safety Relief Valve Actuation (Yes/No) 1 See Emergency Action Levels, Appendix 1, NUREG-0654, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.

O FOR USE IN3 BNIT I ONLY

w

.- , *FOR.USE IN UNIT 1 ONLY

.1004.2 Revision 6 ATTACHMENT III

' CHECKLIST FOR NOTIFICATION ~0F SIGNIFICANT EVENTS MADE IN ACCORDANCE WITH 10 CFR 50.72 -

Containment Water Level Indication Equipment Failures Normal Offsite Power Availabe (Yes/No)

Major Busses / Loads Lost Safeguards Busses Power Source D/G Running (Yes/No) Loaded (Yes/No)

2. Radioactivity Release Liquid / Gas Location / Source Release Rate Duration Stopped (Yes/No)

Release Monitored (Yes/No)

Amount of Release Tech Spec. Limits Radiation Levels in Plant ' Areas Evacuated

3. Security / Safeguards.2-Bomb Threat: SearchConducted(Yes/No) Search Results .

Site Evacuated (Yes/No)

Intrusion: Insider i Outsider '

Point of Intrusion Extend of Intrusion Apparent Purpose Strike / Demonstrations: Size ~cf Group Purpose 2 See 10 CFR 73.71(c), effective April 6, 1981.

O.

FOR USE IN32LOJNIT I ONLY l

- ,FOR USE .IN UNIT l ONLY

- 1004.2 Revision 6 ATTACHMENT-III O

v CHECKLIST FOR NOTIFICATION OF SIGNIFICANT EVENTS MADE'IN ACCORDANCE WITH 10 CFR'50.72 Sabatoge: Radiological (Yes/_No) Arson (Yes/No)

Equipment / Property Extortion: Source (phone, letter, etc.)

Location of Letter Demands General: Firearms involved (Yes/No) Violence (Yes/No)

Control'of Facility Compromised or Threatened (Yes/No)

Stolen / Missing Material Agencies Notified (FBI, State Police, local Police, etc.)'

Media Interest (present, anticipated)

O FOR USE IN"6 NIT I ONLY

_

Retrieved from "https://kanterella.com/w/index.php?title=ML20039B965&oldid=2594472"