ML20247G378

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Confirms Telcon Re Deletion of Objection 5i from 890503 Emergency Preparedness Exercise.Demonstration of Relocation Capabilities Postponed Until Corrective Actions to Procedures Implemented
ML20247G378
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 04/24/1989
From: Trzyna G
COMMONWEALTH EDISON CO.
To: Bradley Davis
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20247G367 List:
References
0059T:68, 59T:68, NUDOCS 8905300390
Download: ML20247G378 (11)


Text

1 n

t N Commonwdith Edison

! 72 West Adams Street. Chicago, Illinois .

- [J Address Reply b: Post OTli5FBoi?F

\,

L_/ Chicago, Illinoir 60690 - 0767 April 24, 1989 Mr. Bert A. Davis Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137

SUBJECT:

ZION STATION UNITS 1 AND 2

" REQUEST FOR DELETION OF OBJECTIVE NUMBER 51 FROM THE,MAY 3, 1989 GENERATING STATION EMERGENCY PLAN

, (GSEP) EXERCISE" NRC DOCKET NOS. 50-295 AND 50-304

Dear Mr. Davis:

This letter is to confirm telephone conversations between Commonwealth Edison Emergency Planning Department and members of your staff at Region III concerning the deletion of Objective 51 from the May 3, 1989 Zion Station Emergency Preparedness Exercise. Objective 51 necessitates demonstration of evacuation and relocation of five individuals during the Exercise. During the Quad CJnies Exercise on April 5, 1989, capability to perform such a relocation was demonstrated. However, members of your staff brought up several concerns which would apply to Zion Station as well.

We have elected to postpone demonstrating Zion Station's relocation capabilities until we are able to incorporate the Quad Cities corrective actions into Zion's procedures. Telephone conversations with your staff have indicated that this is a prudent action. We intend to demonstrate these capabilities at Zion Station during the 1990 Emergency Preparedness

-Exercise.

Any questions or concerns regarding this deletion can be discussed with Terri Lechton (815) 942-8163 or Terry Gilman (815) 942-8150.

i j Very truly yours, 1

l l

Glenn E. Trzyna l Nuclear Licensing Administrator 1

i

' 890530039 890517 FDR -

Q ADOCk 0500o29s pdc APR % 71883 0059T:68

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - 1

ZION MICLEAR POWEE STATIO3 1989 CSEP EIIRCISE May 3, 1989 o=3=ctrv==

O PRIMARY OBJECTIVE:

D1lmonstrate the capability to implement the Commonwealth Edison Generating Station Emergency Plan (GSEP) to protect the.public in the event of a major accident at the Zion Nuclear Power Station.

Demonstrate this capability during the hours to qualify as a daytime Exercise in accordance with NRC guidelines.

ARPORTING OBJECTIVES:

1) incident Assessment and Classification
a. Demonstrate the capability to assess the accident conditions, to determine which Emergency Action Level (EAL) has been reached and to classify the accident level correctly in accordance with CSEP within 30 minutes of plant conditions warranting classification.

- (CR, TSC)

-deation

2) Notification and Cc
a. Demonstrate the capability to notify the applicable offsite State and local organizations within or dec1 i eid -

O ritte cis) 1 t classification.

- (CR, TSC)

b. Demonstrate the capability to notify the NRC as soon as possible and within one (1) hour of the initial incident.

- (CR)

c. Demonstrate the capability to contact pertinent organizations that would normally assist in an emergency, but are not participating in this Exercise (e.g., Murray & Trettel, Westinghouse, etc.)

- (TSC, EOF)

d. Demonstrate the ability to provide follow-up information/ updates to the State and NRC within I

thirty (30) minutes of major plant condition changes or at least hourly.

- (TSC, EOF)

e. Demonstrate the ability to maintain an open-line of communication with the NRC upon request.

- (CR, TSC, EOF) s 0135A/1/wjm l

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ . _ _ _ _.- i

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ZIO3 NDCLEAR POWER STATION 1989 CSEP EXERCISE May 3, 1989 QBJECTIVES

2) Modification and Communication (cont'd)
f. Demonstrate the capability to provide information interface with INPO.

- (EOF)

3) Radiological Assessment
a. . Demonstrate the ability to collect, doctament and trend plant radiological survey information and make appropriate recommendations concerning protective actions for personnel.

- (OSC, TSC, BOF) 1

b. Demonstrate the capability of the Operations  ;

Support Center (OSC) to implement proper Bealth Physica practices and dosimetry issuance for OSC' personnel and Maintenance Teams dispatched to radiologically controlled areas in-plant.

- (OSC)

c. ' Demonstrate the capability of the Operations Support Center (OSC) to track and document

.h personnel exp"sures for OSC personnel and Maintenance Teams dispatched from the OSC.

- (OSC)

d. Demonstrate the capability to calculate offsite dose projections.

- (TSC, EOF)

,e. Demonstrate the ability to make Protective Action Recommendations (PARS).

- (CR, TSC, EOF) f Demonstrate the ability of plant personnel to f.

perform decontamination of radioactively contaminated individuals.

- (OSC) 3 Demonstrate the capability to collect, analyze samples and communicate results using the P/,SS equipment in accordance with procedures and proper contamination control techniques under adverse conditions.

- (OSC) 0135A/2/wjm

    • - -ZION NUCLEAR POWER STATIOT 1989 CSEP IKERCISE
  • l May 3, 1989 LO .
3) M fological Assessment (cont'd) >
h. Danonstrate the ability of the Field Teams to collect and assess environmental samples in accordance wtih procedures and proper contamination control techniquer using sampling equipment and communication methods under the conditions of the scenario.

- (TSC, EOF)

4) *--rzency Facilities
a. Demonstrate the capability to activate and staff the on-site Emergency Response Facilities within sixty (60) minutes and'in accordance with procedures.

- (CR, TSC, OSC, JPIC)

b. Demonstrate the capability to activate sad staff the Emergency Operations Facility in a timely manner.

- (EOF)

c. Demonstrate the capability to record and track'

' - major plant status information relative to Exercise events using Plant Status Boards.

- (TSC, OSC, BOF)

+ d. Demonstrate the capability to track and document, on Status Boards and Logs, all dispatched Operations and Maintenance Team activities and in-plant job statuses.

- (TSC, OSC)

5) Emerzency Direction and Control
a. Demonstrate the ability of the individuals in the GSEP Organization to perform their assigned duties and responsibilities as specified in Generic GSEP and position-specific procedures.

(CR, TSC, OSC, EOF, JPIC)

b. Demonstrate the ability of the Managers and Directors to exert command and control in their respective facilities according to'the duties and responsibilities specified in Generic GSEP and position-specific procedures.

- (CR, TSC, OSC, EOF) 0135A/3/wjm

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1.~ ZION NGCLEAR POWER STATIO2 1989 GSEP EEERCISE May 3,.1989

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~5) Emsraency Direction =ad Control (cont'd)

c. Demonstrate the ability of the Shift Engineer and the OSC Director to. coordinate and prioritize Operations and Maintenance activities during abnormal and emergency situations.

- (CR, OSC).

d. Demonstrate the ability to requisition, acquire and.

transport emergency equipment and supplies 7

~

necessary to mitigate or control unsafe or abnormal plant conditions.-

- (CR, TSC, B0F)

~

e. Demonstrate the capability to assemble and account for all on-site personnel within thirty (30) minutes of sounding the evacuation alars.

- (TSC)-

f. Demonstrate the ability of each Facility Director / Manager to conduct appropriate periodic briefings / updates. covering plant status, event classification and plant activities in progress.

- (CR, TSC,.0SC, EOF)

-( -

3 Demonstrate the ability to provide' access for and-interface with, the ERC Site Team.

- (TSC, EOF)

h. Demonstrate the ability to provide a relief for one (1) EOF Manager position during the Exercise.

- (EOF)

1. Demonstrate the ability to interface with the Division and conduct an evacuation of five (5) non-essential personnel to the Division Offices.

- (TSC)

6) Offsite Agency Coordination
a. Demonstrate the capability of the Emergency Response Organization to coordinate the direction of the emergency response and exchange information with the States, Offsite Field Teams and local Emergency Operations Centers (EOCs) via CECO liaison personnel, Cossuunicators and on-site personnel.

- (TSC, EOF) 0135A/4/wjm i

  1. - ZION WCLEAR POWER STATIOJ
. ,.m '

'1989 GSEP EEERCISE

^

May 3, 1989 OBJECTIVES

{

6) Offsite Amency Coordination (cont'd) 1
b. Demonstrate the ability to discuss Protective

-Action Recommendations (PARS) with the State agencies.

(EOF)

.c. Demonstrate the ability to interface with the Fire Department to care for a medically affected (non-contaminated) individual.

- (EOF)

'7) Public Informatips

a. Demonstrate the ability of the JPIC Coordinator or designee to staff the JPIC'at all times and respond to Press requests.

- (JPIC).

b. Demonstrate the ability of CECO to coordinate and exchange event information for Press conferences with the State agencies.

(JPIC) 611t=1 t Pr P -

O - o tr e ta releasA and Press conferences with'in nine.ty (90) '

minutes of the events during Site and General Emergency classification phases.

- (JPIC)

d. Demonstrate the ability to use visual aids and other resources to support Press release / Press conference information.

- (JPIC)

n. Demonstrate the ability to coordinate the transfer of information between the EOF Public Information Staff and the JPIC Staff.

- (EOF, JPIC)

8) Recovery
a. Demonstrate the capability of the Emergency Response Organization to identify the requirements, criteria and implementing procedures for recovery.

- (TSC, EOF)

b. Demonstrate the capability to identify work priorities, procedures and programs which are required to return the plant to a normal operating status.

- (TSC, EOF) 0135A/5/vjm

I

( i

  • ZION NUCLEAR POWER STATIO3 1989 CSEP EIERCISE MAY 3, 1989 NARRATIVE SUlelARY INITIAL CONDITIONS (074E - 0815)

UNIT ORE - Mode 1 for.the last 25 days maintaining power between 96%

and 99%. Boron concentration is at 250 ppe and equilibritmi Xenon conditions exist. RCS activity has steadily increased over the last month to .77 uCi/gs. An.RCS leak from NOV-RC8003A Loop Bypass. Valve of 3 gym has been identified and steady for the last four days. On-site review and evaluation per Tech. Spec. 3.3.3.B is complete and J l

operation is acceptable. Bourly leak rate calculations are being performed. Pressurize:- PORY PCV-456 started leaking by 7 days ago and is closed. Also, the block valve ,

1 NOV-RC8000A has been closed and de-energized per Tech.

Spec. 3.3.1.F. Steam Generator tube leakage has been

. stable at 25 spd through A S/G for 18 days. The Steam Jet Air Ejector Rad Monitor has been 00S for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Tech.

~~~ -Spec. 3.12.3 Action 6 is,in affect. A B1 Work Request has been issued and RTs and IMs are investigating. . The IB Condensate / Condensate Booster Pusp breaker tripped at 0525. .IWis and ems are investigating. Main Turbine Governor Valve #3 has been fluctuating erratically, opening fully for a few seconds every couple of hours, since 1900 O yesterday. A B1 Work Requ;st has been issued to the IMs but no troubleshooting has been initiated. A Containment vent is in progress for reducing pressure. Vent form #999 expires at 0845. The 1A Diesel Generator has.just been started for PT-11 and is running unloaded.

UNIT TWO - In day 34 of an outage and in Mode 6 for the last 22 days i for refueling. Thr fuel shuffle is completed and preparations are being made to drain the refueling cavity and replace the Reactor Vessel Head. Cleanup of the Fuel Building is in progress. Seal table leakage was experienced prior to the shutdown and repairs are in progress. B RHR Pump is in service for shutdown cooling.

THe B Charging Pump and A RHR Pump are available. The A Charging Pump, all SI and CS Pumps are administrative 1y 005 per Tech. Specs. The Safety Injection Accumulators have been drained for level instrument modification. Refilling the accumulators is planned for tomorrow.

UNUSUAL EVElff (0815 - 0900) J At 0815, RCS leakage increases to approximately 15 spa.

The Unusual Event is classified per EAL #2E (leakage .

requiring shutdown per Tech. Spec. 3.3.3.D). The Station ra t- <* u it a 4 t 1'2= -

O a tr arri minute. When isolation of the Containment vent is performed, A0V-RV0006 is mechanically bound and will not close.

ZNPS '89 GSEP 01212/1/wjm

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EIPECTED ACTIONS The Control Room Operating Shift will notice the increased O< 1eakage.and quantify it. -A. check of the Tech Spec limit will D put thast in' tha' Action Statement.which requires shutdown. .When l the ramp down is started, the classification and notifications l are made. When the Containment Vent Isolation Valve does not-indicate closed,'and Operator will be sent to check the' valve locally.-

ALERT

-(0900 - 1015)

At 0845, the ORT-PR-10A Rad Monitor Alarm indicating a release is in progress from a Gas Deesy Tank. The RCS leakrate j escalates to 65 spa at 0900. Reactor power is approximately 85%. The Alert is classified'per RAL #2M (50 spai leakrate increase in a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> period). While unloading the 11 Diesel Generator, a trip on overspeed occurs. At 0930, the Loop A T-hot RTD fails low. The GUT release stops prior to 1000.

EXPECTED ACTIONS:

Verification of the Rad alarm and investigation of the source will confirm a release is in progress. Increased RCS leakrate verification will provide the condition for-Alert. The Alert condition will be classified and notifications made with the appropriate PARS (Prepare).

The Diesel Generator trip will be investigated by -

0,erations. Tech Staff and Maintenan,e.

.O SITE EMERGENCY (1015 - 1130) 1 An over-current trip (at 1015) on the System Aux. Transformer feed breaker to Bus 143 causes a loss of power to Bus 148 and B RCP trip. The Control Room Operators trip the reactor per AOP-1.4. . If attempted, the Unit 2 SAT crosstie to Bus 148 will not close. At the time of the trip, the leak escalates to a Small Break (approx. 1200 spm) LOCA, which causes the Control Room Operators to initiate a manual Safety Injection. RCS pressure stabilizes between 1400 and 1600 psig. Containment Pressure initially peaks and holds at approximately 5 pais. The Site Emergency is declared per RAL #2P (Containment Rad Level >

-400 R/hr.). An HRSS/ PASS sample is obtained to determine the extent of core damage. When assembly / accountability is called, two Fuel Handlers are found in the assembly area with contamination on their hands and faces. They had been removing poly sheeting from the Spent Fuel Pool handrails when the assembly sounded. At 1045, the NRC (sock) Site Team arrives at the EOF and the Statica Gatehouse.

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ZNPS '89 GSEP 0121Z/2/wjm i

7 RYPECTED ACTION 3:

The Reactor will be manually tripped due to the loss of power which tripped B RCP. The small break LOCA will provide conditions which will cause a Safety injection if o

-() the Operating Crew does not manually initiate first. .The Site Emergency classification and notifications will be made based on Containment Rad Levels > 400 R/hr with the appropriate PARS (Prepare). An assembly / accountability will be called during which two contaminated individuals will be discovered. Rad Protection will trace their path from the Fuel Building and start decontamination of the

' individuals and their path. The NRC (MOCK) Site Team will be accessed to the EOF (3 persons) and TSC (1 person)

GENERAL EMERGENCY (1130 - 1930)

At 1130, a large brsak LOCA occurs which results in a maximum of 47 psig and eventually equalizes RCS and Containment Pressure at approximately 25 psig. RVLIS fndicates that the top of the core is uncovered during the depressurization transient. Air operated valves in the Containment are not.available due to the failure of the Instrument Air Containment Isolation Valves to open. At 1200, A0V-RV0005 failti open and the Containment depressurizes through the vent s tack and from the effects of

' Containment Spray and RCFCs over the next two (2) hours. The General Emergency is declared per EAL #2T (Containment Rad levels >2000 R/hr and probable loss of Containment). Upon

- demand, the Pressurizer PORV PCV-455C will not open. An

() evacuation of non-essential personnel (5 individua1.s) to Waukegan District Offices is performed. At 1215, the Manager of Emergency Operations at the EOF has a heart attack.

EXPECTED ACTIONS:

The Large Break LOCA provides an urgency for repair of the Diesel Generator and restoration of power to Bus 143.

Investigation of the release path and optional' methods to isolate it will be undertaken by the TSC and OSC. ' Loss of Instrument Air to Containment will require a Maintenance Crew to investigate and affect repairs. The General Emergency classification and notifications will be made based on 10,000 R/hr in containment with the appropriate PARS (E), E), S)). The evacuation of non-essential' personnel to Waukegan District Offices will be coordinated with IESDA. The MEO will receive initial first aid from the EOF steff and a Zion Fire Department ambulance will be called. The paramedics will stabilize and transport the victim. A survey of the ambulance at the hospital (hospital run simulated) will reveal contamination.

t O\/ l ZNPS '89 GSEP 0121Z/3/wjm

- _ _ _ _ _ _ _ _ = . _ _ - -

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RECOVERY (1430 - 1530)

After a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time jump, Recovery and reentry planning for the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is accomplished in conjunction with JPIC' operations. A decision of whether or not Recovery can be entered must be made. Selected Radiological Data will be

-provided for offsite sampling during the last 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

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