ML041060404

Transmittal of Davis-Besse Emergency Plan Implementing Procedure RA-EP-01900, General Emergency, Revision 03

ML041060404
Person / Time
Site:	Davis Besse
Issue date:	04/08/2004
From:	FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
0404-49454
Download: ML041060404 (13)

Text

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4.<E ale C Davis Besse Power Station Control Copy Number: 1665 Transmittal / Receipt Acknowledgement Transmittal Number: 0404-49454 Transmittal Date: 04-08-2004

-To:--DOC. CONTROILDESK-Mail Stop / Address:= USNRC DIVISION OF EMERGENCY PREPARDNESS WASHINGTON, D.C. 20555 Document holders are responsible for control and maintenance of documents in accordance with the actions specified by this transmittal. Outdated material shall either be removed and destroyed or marked to reflect that it is superseded or voided and is no longer considered controlled.

Note: Destroy Safeguard information by shredding.

File documents in tab order as identified on the Table of Contents Contact Document Control with any questions at (419)-321-7483 0 ,

( Control Copy Number: 1665 Davis Besse Power Station Transmittal / Receipt Acknowledgement Transmittal Number: 0404-49454 Transmittal Date: 04-08-2004 TOC I TOC 2 Type Number Sht/Sec Changes Rev Status .

old EPIA PROC RA-EP-01900 0002 APPROVED new EPIA PROC RA-EP-01900 0003 APPROVED

Page 1 of 11 Davis-Besse Nuclear Power Station EMERGENCY PLAN IMPLEMENTING PROCEDURE RA-EP-01900 GENERAL EMERGENCY REVISION 03 Prepared by: B. W. Cope Procedure Owner: Manager - Regulatory Affairs Effective Date: APR 0 8 2004 Procedure Classification: LEVEL OF USE:

X Safety Related STEP-BY-STEP Quality Related Non-Quality Related

I

• .A4 2 RA-EP-01900 Revision 03 TABLE OF CONTENTS Page 1.0 PURPOSE .3

2.0 REFERENCES

.3 3.0 DEFINITIONS .3 4.0 RESPONSIBILITIES .4 5.0 INITIATING CONDITIONS .4 6.0 PROCEDURE .5 7.0 FINAL CONDITIONS .10 8.0 RECORDS .10 COMMITMENTS .............................. .............................. 11

3 RA-EP-01900 Revision 03 1.0 PURPOSE This procedure outlines the course of action and protective measures required to mitigate a General Emergency.

2.0 REFERENCES

2.1 Developmental 2.1.1 Davis-Besse Nuclear Power Station Emergency Plan 2.2 Implementation 2.2.1 RA-EP-01500, Emergency Classification 2.2.2 RA-EP-01600, Unusual Event 2.2.3 RA-EP-01700, Alert 2.2.4 RA-EP-0 1800, Site Area Emergency 2.2.5 RA-EP-02240, Offsite Dose Assessment 2.2.6 RA-EP-02245, Protective Action Guidelines 2.2.7 RA-EP-02520, Assembly and Accountability 2.2.8 RA-EP-02530, Evacuation 2.2.9 RA-EP-02710, Reentry 2.2.10 RA-EP-02720, Recovery Organization 3.0 DEFINITIONS 3.1 GENERAL EMERGENCY - Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with the potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.

3.2 TRANSITORY EVENT - An event which is classifiable in accordance with RA-EP-01500, Emergency Classification, but becomes a lower - classification or non-classifiable event before being declared.

4 RA-EP-01900 Revision 03 4.0 RESPONSIBILITIES 4.1 The Emergency Director shall be responsible for the implementing of this procedure.

4.1.1 The Shift Manager shall become the Emergency Director during activation of the Davis-Besse Emergency Plan and shall be responsible for coordinating the actions of the emergency organization until relieved.

4.1.2 The Unit Supervisor may assume the Emergency Director duties only if the Shift Manager is not in the Control Room, or is incapable of performing those duties.

4.1.3 The Shift Engineer (Shift Technical Advisor) may assume the Emergency Director duties only if neither the Shift Manager nor the Unit Supervisor is in the Control Room and capable of performing those duties.

4.1.4 Upon arrival in the Control Room, the Emergency Assistant Plant Manager or Emergency Plant Manager may relieve the Emergency Director.

4.1.5 The Emergency Plant Manager may assume the Emergency Director duties from the Technical Support Center (TSC) if the TSC and Emergency Operations Facility (EOF) are activated.

4.1.6 The Emergency Director shall remain in the Control Room until the TSC and EOF have been activated.

5.0 INITIATING CONDITIONS This procedure shall be utilized whenever a General Emergency has been classified in accordance with RA-EP-01500, Emergency Classification.

5 RA-EP-0 900 Revision 03 NOTE 6.0 The following procedure steps may be performed simultaneously.NE..

_DE.....

_______.. ____J 6.0 PROCEDURE DATE:

TIME INITIALS The Emergency Director shall direct performance of the following:

CAUTION 6.1-

1. If the General Emergency is due to a security event obtain security management concurrence prior to sounding the Station alarm.

6.1 Sound the appropriate Station alarm (fire, access evacuation, and/or initiate emer-gency procedures) and make the following announcement over the public address system, TWICE.  ; -

6.1.1 Upgrading:..

"ATTENTION ALL PERSONNEL; ATTEN-TION ALL PERSONNEL: A GENERAL EMERGENCY HAS BEEN DECLARED. NO EATING, DRINKING, OR SMOKING UNTIL FURTHER NOTICE. ALL MEM-BERS OF THE ONSITE EMERGENCY ORGANIZATION REPORT TO YOUR DESIGNATED EMERGENCY RESPONSE FACILITIES. ALL NONESSENTIAL PERSONNEL IMMEDIATELY EVACUATE TO THE LINDSEY SERVICE CENTER. THE REASON FOR THE GENERAL EMERGENCY IS (STATE REASON)

(SEE RA-EP-02520, ASSEMBLY AND ACCOUNTABILITY FOR FURTHER DETAIL.)

I 6 RA-EP-01900 l1 Revision 03 DATE:

TIME INITIALS 6.1.2 If there is a localized emergency (e.g., fire),

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

6.2 Notify the Emergency Response Organization (ERO) in accordance with RA-EP-021 10, Emergency Notification._

6.3 Protective Action Recommendations (PARs) shall be made in accordance with RA-EP-02245, Protective Action Guidelines.

6.4 Notify Ottawa County, Lucas County and the State of Ohio within 15 minutes of any emergency classification using the Initial Notification Form, DBEP-010, in accordance with RA-EP-021 10, Emergency Notification.

6.5 Notify the NRC within I hours using the Reactor Plant Event Notification Worksheet, DB-0095.

6.6 Initiate a general evacuation of the site in accordance with RA-EP-02530, Evacuation.

Nonessential personnel evacuated from the station.

6.7 Initiate personnel accountability (unless previously accomplished) in accordance with RA-EP-02520, Assembly and Accountability.

Accountability completed.

6.8 Terminate all radwaste releases.

6.9 Increase surveillance of Control Room instrumentation. Indications of core status (e.g.,

incore thermocouple reading, etc.) shall receive particular attention.

6.10 Ensure the following emergency response facilities are activated:

6.10.1 The Operations Support Center 6.10.2 The Technical Support Center

7 RA-EP-01900 Revision 03 DATE:

TIME INITIALS 6.10.3 The Emergency Operations Facility 6.10.4 The Joint Public Information Center 6.10.5 The Corporate Emergency Response Organization 6.11 Continue dose assessment activities in accordance with RA-EP-02240, Offsite Dose Assessment, with increased emphasis on determining the need for protective actions. i CAUTION 6.12 Changes in Protective Action Recommendations (PARs) shall be communicated to the offsite agencies using the Initial Notification Form (DBEP-010) within 15 minutes of the Emergency Director decision.

6.12 IF changes in plant conditions or projected offsite doses require a change in PARs, 2 THEN DO NOT change an existing PAR for a specific sub-area until the conditions that caused the PAR to be issued are fully under control, AND notify the offsite agencies of the PAR changes within 15 minutes of the change in the PAR using the Initial Notification Form (DBEP-010) in accordance with RA-EP-021 10, Emergency Notification. Include all PARs that are affected with each notification.

6.13 Make periodic updates to offsite agencies as conditions change, or hourly at a minimum, using the Periodic Update Form, DBEP-009, in accordance with RA-EP-02110, Emergency Notification. These updates may be omitted by mutual agreement with the offsite agencies.

6.14 When plant conditions change review RA-EP-01500, Emergency Classification, to determine if the event should be reclassified. .

I 8 RA-EP-01900 Revision 03 DATE:

TIME INITIALS 6.14.1 Once a General Emergency has been declared, the event shall NOT be downgraded without reviewing Downgrading Guidelines in RA-EP-01500, Emergency Classification.

6.14.2 If the event is reclassified, then implement the appropriate procedure.

6.15 When the General Emergency is downgraded, make the following notifications in accordance with RA-EP-021 10, Emergency Notification:

6.15.1 Ottawa County, Lucas County, and the State of Ohio using the Initial Notification Form, DBEP-010.

6.15.2 The NRC using the Reactor Plant Event Notification Worksheet, DB-0095.

6.16 If a transitory General Emergency condition has occurred, notify Ottawa County, Lucas County, State of Ohio, and the NRC in accordance with RA-EP-021 10, Emergency Notification.

6.17 The individual assuming the responsibilities of Emergency Director shall complete the Emergency Director Turnover Data Sheet, DBEP-304, using information provided by the Control Room log, unit log, and status boards.

6.18 If the emergency situation is mitigated and completely declassified, then perform the following:

6.18.1 Make this announcement over the public address system:

"ATTENTION ALL PERSONNEL, ATTENTION ALL PERSONNEL. THE EMERGENCY SITUATION HAS BEEN TERMINATED. I REPEAT, THE EMERGENCY SITUATION HAS BEEN TERMINATED.

6.18.2 Notify Ottawa County, Lucas County, and the State of Ohio using the Initial Notification Form, DBEP-010, in accordance with RA-EP-021 10, Emergency Notification.

9 RA-EP-01900 Revision 03 DATE:

TIME INITIALS 6.18.3 Notify the Nuclear Regulatory Commission using the Reactor Plant Event Notification Worksheet, DB-0095, in accordance with RA-EP-021 10, Emergency Notification.

6.18.4 Notify the Emergency Response Organization (ERO) in accordance with RA-EP-021 10, Emergency Notification. _

6.19 Perform necessary reentry actions in accordance with RA-EP-02710, Reentry.

6.20 Perform recovery actions in accordance with RA-EP-02720, Recovery Organization.

6.21 Records, other than Safeguard Records, shall be collected and forwarded to the Supervisor-Emergency Preparedness who shall submit them to Nuclear Records Management. Safeguards Records shall be collected and forwarded to the Supervisor -

Security Shift.

Section 6.0 completed by:

10 RA-EP-01900 Revision 03 7.0 FINAL CONDITIONS 7.1 The emergency condition has been downgraded and actions are being taken in accordance with RA-EP-01800, Site Area Emergency, RA-EP-01700, Alert or RA-EP-01600, Unusual Event.

OR 7.2 Emergency conditions no longer exist and actions are being taken in accordance with RA-EP-027 10, Reentry, and/or RA-EP-02720, Recovery Organization.

8.0 RECORDS 8.1 The following quality assurance records are completed by this procedure and shall be listed on the Nuclear Records List, captured, and submitted to Nuclear Records Management in accordance with NG-NA-00106:

8.1.1 None 8.2 The following non-quality assurance records are completed by this procedure and may be captured and submitted to Nuclear Records Management, in accordance with NG-NA-00106:

8.2.1 RA-EP-01900, General Emergency (when steps have been completed) 8.2.2 Emergency Director Turnover Data Sheet, DBEP-304 8.2.3 Initial Notification Form, DBEP-010 8.2.4 Periodic Update Form, DBEP-009 8.2.5 Reactor Plant Event Notification Worksheet, DB-0095

11 RA-EP-01900 Revision 03 COMMITMENTS Section Reference Comments 6.2, 6.4, 6.13 0 13532, 0 13969, Addresses 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification 0 15211,0 15212 capability 6.6 0 13600 Evacuation of non-essential personnel 4.1.3 0 13670 Specifies conditions under which STA may assume Emergency Director duties 6.11 0 13584 Concerns protective action recommendations 6.11 015209 Dose Assessment ALL Q 03113 Activating the ERO 6.12 0 20716 Provides additional guidance for modifying offsite protective action recommendations. RIS 2003-012 (CR03-06439)