Text

Revised Epips, Including 73EP-EIP-004-0, Version 9.0, 73EP-EIP-005-0, Version 8.0, 73EP-EIP-018-0, Version 7.0, 73EP-EIP-023-0S, Version 0.4 & 73EP-EIP-073-0. Version 15.1
	ML031220093
Person / Time
Site:	Hatch
Issue date:	04/30/2003
From:	Sumner H; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-03-0939
	Download: ML031220093 (82)
	v • d • e

Lewis Sumner Southern Nuclear Vice President Operating Company, Inc.

Hatch Project Support 40 Inverness Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205 992 7279 Fax 205 992 0341 SOUTHERN OA 4 COMPANY April 30, 2003 Energy to Serve Your World' Docket Nos.: 50-321 NL-03-0939 50-366 U. S. Nuclear Regulatory Commission AT'LN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Emergency Implementing Procedure Revisions Ladies and Gentlemen:

In accordance with 10 CFR 50, Appendix E, Section V, Southern Nuclear Operating Company hereby submits the following revisions to the Plant Hatch Emergency Implementing Procedures (EIP):

EIP No. Version Effective Date 73EP-EIP-004-0 9.0 4/22/2003 73EP-EIP-005-0 8.0 4/22/2003 73EP-EIP-011-0 5.0 4/22/2003 73EP-EIP-018-0 7.0 4/22/2003 73EP-EIP-023-OS 0.4 4/22/2003 73EP-EIP-073-0 15.1 4/22/2003 These revisions incorporate various changes to the above documents.

By copy of this letter, Mr. L. A. Reyes, NRC Region II Administrator, will receive two copies of the revised procedures.

This letter contains no NRC commitments. If you have any questions, please advise.

H. L. Sumner, Jr.

HLS/whc/ckb 4Uq5

U. S. Nuclear Regulatory Commission NL-03-0939 Page 2

Enclosures:

73EP-EIP-004-0, Duties of Emergency Director 73EP-EIP-005-0, On-Shift Operations Personnel Emergency Duties 73EP-EIP-01 1-0, Assembly, Accountability and Evacuation 73EP-EIP-018-0, Prompt Offsite Dose Assessment 73EP-EIP-023-OS, Core Damage Assessment 73EP-EIP-073 -0, Offsite Emergency Notifications cc: Southern Nuclear Operating Company Mr. J. D. Woodard, Executive Vice President Mr. P. H. Wells, General Manager - Plant Hatch Document Services RTYPE: CHAO2.004 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. S. D. Bloom, NRR Project Manager - Hatch Mr. N. P. Garrett, Acting Senior Resident Inspector - Hatch

SOUTHERN NUCLEAR DOCUMENT TYPE: PAGE PLANT E.I. HATCH l EMERGENCY PREPAREDNESS PROCEDURE 1 OF 13 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION DUTIES OF EMERGENCY DIRECTOR 73EP-EIP-004-0 NO:

9.0 EXPIRATION APPROVALS: EFFECTIVE DATE: DEPARTMENT MANAGER JCL DATE 4/14/2003 DATE:

4/22/2003 N/A NPGM/POAGM/PSAGM DRM DATE 4117/2003 1.0 OBJECTIVE This procedure establishes the responsibilities and actions taken by the Emergency Director to direct and manage emergency response, emergency operations and support activities.

TABLE OF CONTENTS Section Title Page 7.0 PROCEDURE 7.1 Initial Emergency Response 4 7.2 Normal Succession for Emergency Director 4 7.3 Transfer of Responsibilities 5 7.4 Emergency Director Duties 6 2.0 APPLICABILITY This procedure applies to responses taken by the Emergency Director after initial emergency classification and initial actions have been performed. This procedure is performed as required.

3.0 REFERENCES

3.1 10AC-MGR-006-0, Hatch Emergency Plan 3.2 Edwin I Hatch Nuclear Plant, Unit 1 and U2 Emergency Plan 3.3 OOAC-REG-001-0, Federal and State Reporting and Federal Document Posting Requirements 3.4 73EP-EIP-001-0, Emergency Classification and Initial Actions 3.5 73EP-EIP-005-0, On shift Operations Personnel Emergency Duties 3.6 73EP-EIP-009-0, Nuclear Security Duties 3.7 73EP-EIP-017-0, Emergency Exposure Control 3.8 73EP-EIP-019-0, Rally Point Team Duties MGR-0002 Rev. 8

SOUTHERN NUCLEAR PAGE 2 OF 13 PLANT E.l. HATCH I DOCUMENT TITLE: DOCUMENT NUMBER: REVISION NO:

DUTIES OF EMERGENCY DIRECTOR 73EP-EIP-004-0 9.0 3.9 73EP-EIP-054-0, Protective Action Recommendations to State and Local Authorities 3.10 73EP-EIP-063-0, Technical Support Center Activation 3.11 73EP-EIP-073-0, Offsite Emergency Notifications 3.12 75TR-TRN-001-0, Emergency Preparedness Training Program 3.13 10CFR50.72, Immediate Notification requirements for operating nuclear power reactors 3.14 31GO-OPS-013-0, Notifications and Reports 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS Personnel who have been designated to perform duties as Emergency Director shall receive training in applicable emergency response training areas as outlined in 75TR-TRN-001-0, Emergency Preparedness Training Program.

4.2 MATERIAL AND EQUIPMENT N/A - Not applicable to this procedure 4.3 SPECIAL REQUIREMENTS N/A - Not applicable to this procedure 5.0 PRECAUTIONSILIMITATIONS 5.1 PRECAUTIONS Hazardous levels of radiation and contamination may be encountered by plant personnel during emergency situations. Consult Health Physics and Chemistry supervision regarding radiological conditions.

5.2 LIMITATIONS 5.2.1 The Emergency Director may modify emergency plan implementing procedures and staffing to meet the needs of emergency response.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR lPAGE 3 OF 13 PLANT E.I. HATCH I I DOCUMENT TITLE: DOCUMENT NUMBER: REVISION NO:

DUTIES OF EMERGENCY DIRECTOR 73EP-EIP-004-0 9.0 5.2.2 The Emergency Director may prohibit or delay the performance of activities referenced in this procedure IF in his judgement, performance will present a threat to personnel or nuclear safety (i.e., security events, severe weather conditions or other hazards which may affect personnel safety).

5.2.3 The Emergency Director will NOT delegate the following responsibilities:

5.2.3.1 The decision to declare, escalate, downgrade, or terminate emergency classifications.

5.2.3.2 The decision to notify offsite emergency response agencies.

5.2.3.3 The decision to recommend protective actions to offsite authorities.

5.2.3.4 The decision to request federal assistance.

5.2.3.5 Authorization for plant personnel to exceed 10CFR20 radiation exposure limits.

5.2.3.6 Authorization for use of potassium iodide (KI) tablets during a declared emergency.

5.2.3.7 The decision to dismiss nonessential personnel from the site at an ALERT or higher emergency classification.

6.0 PREREQUISITES 6.1 The Superintendent of Shift (SOS) must complete the actions specified in subsection 7.1.5 of 73EP-EIP-001-0, Emergency Classification and Initial Actions prior to implementing this procedure.

6.2 This procedure will be utilized for drills, exercises and actual emergencies.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE 4 OF 13 Di ANT F I HATCH-I DOCUMENT TITLE: DOCUMENT NUMBER: REVISION NO:

DUTIES OF EMERGENCY DIRECTOR 73EP-EIP-004-0 9.0 I REFERENCE 7.0 PROCEDURE 7.1 INITIAL EMERGENCY RESPONSE Initially, the Emergency Director position is filled by the Superintendent of Shift (SOS). If the SOS is unavailable, then the affected unit's Shift Supervisor (SS) will become the Emergency Director. IF the SOS is unavailable and the event involves both units, the Unit 1 Shift Supervisor (SS) will become the Emergency Director. Any of these persons will assume the position of Emergency Director in the Control Room until a qualified relief, as specified in step 7.2, can arrive on site and receive an adequate turnover.

7.2 NORMAL SUCCESSION FOR EMERGENCY DIRECTOR The Emergency Director may operate from the Control Room, TSC, or EOF at his discretion. He may act as the TSC Manager and Emergency Director simultaneously during the early phases of emergency response until another qualified Emergency Director or another qualified TSC Manager arrives and takes over the applicable duties.

Any one of the following persons may assume the Emergency Director (ED) duties after he is given proper turnover from the off going ED.

Nuclear Plant - General Manager

Plant Operations - Assistant General Manager (POAGM)

Plant Support - Assistant General Manager (PSAGM)

Vice President - Project (Hatch) I

Other qualified Emergency Director MGR-0001 Rev. 3

l PAGE 5 OF 13 SOUTHERN NUCLEAR PIANT F I HATCH DOCUMENT TITLE: DOCUMENT NUMBER: REVISION NO:

DUTIES OF EMERGENCY DIRECTOR 73EP-EIP-004-0 9.0 7.3 TRANSFER OF RESPONSIBILITIES NOTE: Efforts should be made to coordinate the transfer of Emergency Director duties in l conjunction with state/local notifications and dose assessment activities.

7.3.1 Turnover from the off going Emergency Director (ED) to the relieving ED may be conducted in person or over the phone, as appropriate.

7.3.2 The off going ED will brief the relieving ED of the following:

Emergency Classification

Initiating and Current Plant Conditions

Emergency Organization Status

Mitigating Actions

Notifications

Dose Assessment activities/radiological release status

Other Relevant Information 7.3.3 The relieving ED will ensure the Emergency Response Facility (ERF) Managers are notified of who is functioning as the ED.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE 6 OF 13 PLANT E.I. HATCH DOCUMENT TITLE: DOCUMENT NUMBER: REVISION NO.

DUTIES OF EMERGENCY DIRECTOR 73EP-EIP-004-0 9.0 NOTE: (* ) indicates actions performed/approved by the E.D. All other actions may be delegated at the E.D.'s discretion.

7.4 EMERGENCY DIRECTOR DUTIES NOTE: Anytime an event is reclassified, ensure initial actions are performed per 73EP-EIP-001-0, Emergency Classification and Initial Actions.

NUE l ALERT SITE GENERAL

__________I___________ A R EA

7.4.1 Continue to assess the emergency condition and X X X X reclassify per 73EP-EIP-001-0, Emergency Classification and Initial Actions, as necessary, within 15 minutes of conditions requiring classification.

7.4.2 Inform Security of the emergency declaration. Direct X X X X them to merge the plant PA system with the Simulator Building PA system and start accountability, if appropriate, in accordance with 73EP-EIP-009-0, Nuclear Security Duties.

7.4.3 Direct PA announcements to be made in accordance X X X X with 73EP-EIP-005-0, On-shift Operations Personnel Emergency Duties.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE 7 OF 13 PLANT E.I. HATCH DOCUMENT TITLE: DOCUMENT NUMBER: REVISION NO:

DUTIES OF EMERGENCY DIRECTOR 73EP-EIP-004-0 9.0 NOTE: ( indicates actions performed/approved by the E.D. All other actions may be delegated at the E.D.'s discretion.

7.4 EMERGENCY DIRECTOR DUTIES (CONTVD)

NOTE:

The ED may delay staff augmentation as a result of a security event, severe weather conditions or other hazards to personnel safety.

Normal working hours is defined as Monday thru Friday between the hours of 7:30 am and 4:00 p.m. I INUE (ALERT SITE (GENE RAL

~AREA 7.4.4 Initiate staff augmentation IF the emergency event is X X X occurring outside of normal working hours, on the weekend, on a holiday OR when the ED determines additional staff is necessary. Obtain and follow the applicable instructions for activation of the HNP Autodialer System from the Emergency Director notebook in the Control Room.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE 8 OF 13 PLANT E-l HATCH I DOCUMENT TITLE: DOCUMENT NUMBER: REVISION NO:

DUTIES OF EMERGENCY DIRECTOR 73EP-EIP-004-0 9.0 NOTE: (*) indicates actions performed/approved by the E.D. All other actions may be delegated at the E.D.'s discretion.

7.4 EMERGENCY DIRECTOR DUTIES (CONT'D)

NOTE:

Initial and follow-up notifications to State and local authorities shall be made in accordance with 73EP-EIP-073-0, Offsite Emergency Notifications.

E.D. approval must be given prior to initiating notifications to State and local authorities.

. l1 NUE ALERT SITE GENERAL AREA

7.4.5 The initial ED in the Control Room will complete and X X X X approve the emergency notification form and ensure designated personnel transmit the emergency information to State and local authorities within 15 minutes of declaring or changing emergency classifications. Additionally, significant events, which potentially impact offsite emergency actions, must be reported as soon as practicable to State and local authorities in accordance with 73EP-EIP-073-0, Offsite Emergency Notifications. I

7.4.6 The ED in the TSC or EOF will review and approve X X X the emergency information for notification of State and local authorities and ensure designated personnel in the TSC or EOF transmit the emergency information to State and local authorities within 15 minutes of declaring or changing emergency classifications. Additionally, significant events, which potentially impact offsite emergency actions, must be reported as soon as practicable to State and local authorities in accordance with 73EP-EIP-073-0, Offsite Emergency Notifications. I MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE 9 OF 13 PiANT FI1- HATCH DOCUMENT TITLE: DOCUMENT NUMBER: REVISION NO:

DUTIES OF EMERGENCY DIRECTOR 73EP-EIP-004-0 9.0 NOTE: (* ) indicates actions performed/approved by the E.D. All other actions may be delegated at the E.D.'s discretion.

7.4 EMERGENCY DIRECTOR DUTIES (CONT'D)

NUE ALERT SITE GENERAL

- ._____AREA 7.4.7 Designate an individual to transmit emergency X X X X information to the NRC in accordance with OOAC-REG-001-0, Federal and State Reporting and Federal Document Posting Requirements and ensure an open line with the NRC is maintained, IF requested.

Information is to be provided to the NRC as soon as possible but no later than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months following the declaration of an emergency and in accordance with 31GO-OPS-013-0, Notifications and Reports.

7.4.8 Verify the NRC Resident Inspector has been notified. X X X X I NOTE: The ED may delay activation of the emergency response facilities as a result of a security event, severe weather conditions or other hazards to personnel safety.

NUE ALERT SITE jGENERAL

_ ~AREAJ 7.4.9 Ensure appropriate Emergency Response Facilities X X X (ERFs) are activated in accordance with applicable ERF activation procedures.

7.4.9.1 Ensure the TSC has activated the NRC-ERDS X X X system in accordance with 73EP-EIP-063-0, Technical Support Center Activation.

MGR-0001 Rev. 3

l SOUTHERN NUCLEAR PAGE 10 OF 13 Pi ANT El HATCH I DOCUMENT TITLE: DOCUMENT NUMBER: REVISION NO:

DUTIES OF EMERGENCY DIRECTOR 73EP-EIP-004-0 9.0 NOTE: ( *) indicates actions performed/approved by the E.D. All other actions may be delegated at the E.D.'s discretion.

7.4 EMERGENCY DIRECTOR DUTIES (CONT'D)

NUE ALERT SITE GENERAL AREA 7.4.9.2 Ensure Health Physics confirms habitability of the X X X rally points in accordance with 73EP-EIP-019-0, Rally Point Team Duties. IF unforeseen security/radiological/weather conditions preclude dismissal through the Plant Entry Security Building I (PESB) AND/OR Gate 17, determine and have announced over the Public Address (PA) system an alternate location for a rally point and a site exit route. I 7.4.9.3 Provide periodic briefings to ERF Managers. X X X 7.4.10 Consider ordering an early dismissal of non-essential personnel IF the potential for degrading plant X X conditions or a threat to the safety of onsite personnel exist.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE 11 OF 13 PLANT El HATCH DOCUMENT TITLE: DOCUMENT NUMBER: REVISION NO:

DUTIES OF EMERGENCY DIRECTOR 73EP-EIP-004-0 9.0 NOTE: (* ) indicates actions performed/approved by the E.D. All other actions may be delegated at the E.D.'s discretion.

7.4 EMERGENCY DIRECTOR DUTIES (CONrD)

NOTE: The ED may delay the release of personnel from the site as a result of a security event, severe weather conditions or other hazards to personnel safety.

NUE ALERT SITE GENERAL AREA .

7.4.11 Order dismissal of non-essential personnel from the X X I plant site.

7.4.12 Ensure Security initiates accountability for personnel X X X within the Protected Area and provides a status of the release of non-essential personnel in accordance with 73EP-EIP-009-0, Nuclear Security Duties.

7.4.13 Authorize emergency exposure in accordance with X X X 73EP-EIP-017-0, Emergency Exposure Control.

7.4.14 Authorize issuance of Potassium Iodide in X X X accordance with 73EP-EIP-017-0, Emergency Exposure Control.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE 12 OF 13 PLANT E.l. HATCH I DOCUMENT TITLE: DOCUMENT NUMBER: REVISION NO:

DUTIES OF EMERGENCY DIRECTOR 73EP-EIP-004-0 9.0 NOTE: ( indicates actions performed/approved by the E.D. All other actions may be delegated at the E.D.'s discretion.

7.4 EMERGENCY DIRECTOR DUTIES (CONT'D) l CAUTION: PROTECTIVE ACTION RECOMMENDATIONS TO STATE I LOCAL l AUTHORITIES ARE REQUIRED FOR A GENERAL EMERGENCY l CLASSIFICATION, IN ACCORDANCE WITH 73EP-EIP-054-0, PROTECTIVE l l ACTION RECOMMENDATIONS TO STATE AND LOCAL AUTHORITIES. l NUE 1 ALERT SITE 1 GENERAL I _ AA A

7415 Evaluate the need for and recommend protective X X actions to state and local authorities within 15 minutes of the existence of conditions requiring protective actions.

7.4.16 Ensure adequate communications with the Corporate X X X Emergency Operations Center (CEOC) are established and maintained by the TSC and EOF.

7.4.17 Ensure contact is established with the Public X X Information Director and Spokesperson. Remain I cognizant of news release information and assist in addressing rumors and media questions.

7.4.18 Coordinate response efforts and State/local X X X information and liaison needs.

7.4.19 Evaluate the need for State/local and Federal offsite X X X X assistance. Ensure requests for assistance are made, as needed; and arrangements are made to receive offsite support.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR lPAGE 13 OF 13 PLANT E.l. HATCH I DOCUMENT TITLE: DOCUMENT NUMBER: REVISION NO:

DUTIES OF EMERGENCY DIRECTOR 73EP-EIP-004-0 9.0 NOTE: ( * ) indicates actions performed/approved by the E.D. All other actions may be delegated at the E.D.'s discretion.

7.4 EMERGENCY DIRECTOR DUTIES (CONT'D)

NUE lALERT SITE GENERAL AREA T I 7.4.20 Initiate discussions with applicable members of the X X X emergency response organization and offsite authorities (i.e., Nuclear Regulatory Commission, Georgia Emergency Management Agency, Appling, Jeff Davis, Tattnall and Toombs County Emergency Management Agency Directors) before downgrading or terminating an emergency declaration.

7.4.21 When terminating the emergency, ensure the X X X X following actions have been performed:

7.4.21.1 Ensure verbal closeout to State and Local X X X X Authorities using ENN or alternate communications 7.4.21.2 Ensure verbal closeout to NRC using ENS or x x X X alternate communications.

7.4.21.3 Ensure all facilities and applicable offsiteXX agencies/organizations are provided emergency termination information and the status of recovery activities.

7.4.22 Contact the site Emergency Preparedness X X X X Coordinator after the event has been terminated to ensure a written report summarizing the event is being prepared for distribution to State and local authorities and the NRC. The written report will be provided in accordance with OOAC-REG-001-0, Federal and State Reporting and Federal Document Posting Requirements.

END OF 7.4, EMERGENCY DIRECTOR DUTIES MGR-0001 Rev. 3

SOUTHERN NUCLEAR DOCUMENT TYPE: PAGE PLANT E.l. HATCH l EMERGENCY PREPAREDNESS PROCEDURE 1 OF 10 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:

8.0 EXPIRATION APPROVALS: EFFECTIVE DATE: DEPARTMENT MANAGER JCL DATE 4/14/2003 DATE:

4/22/2003 N/A NPGM/POAGM/PSAGM DRM 4 DATE 4/142003 1.0 OBJECTIVE This procedure provides guidance to on-shift operations personnel for response to declared emergencies.

TABLE OF CONTENTS Section Title Paqe 2.0 APPLICABILITY 1

3.0 REFERENCES

1 4.0 REQUIREMENTS 2 5.0 PRECAUTIONS/LIMITATIONS 2 6.0 PREREQUISITES 2 7.0 PROCEDURE 3 7.1 SUPERINTENDENT OF SHIFT (SOS) 3 7.2 SHIFT SUPERVISOR (SS) 5 7.3 SHIFT SUPPORT SUPERVISOR 6 7.4 CONTROL ROOM OPERATOR 7 7.5 SYSTEM OPERATOR 10 2.0 APPLICABILITY This procedure applies to responses and actions taken by on-shift operations personnel. This procedure is performed as required.

3.0 REFERENCES

3.1. 10AC-MGR-006-0, Hatch Emergency Plan 3.2. Edwin I. Hatch Unit 1 and Unit 2 Emergency Plan 3.3. 73EP-EIP-001-0, Emergency Classification and Initial Actions I MGR-0002 Rev. 8

SOUTHERN NUCLEAR PAGE PLANT E.I. HATCH 2 OF 10 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:

18.0 3.4. 73EP-EIP-004-0, Duties of Emergency Director 3.5. 73EP-EIP-018-0, Prompt Offsite Dose Assessment 3.6. FULL SIZE FORM

TRN-0144, Emergency Page Announcement Guide 4.0 REQUIREMENTS 4.1. PERSONNEL REQUIREMENTS On-shift operations personnel who have received emergency response training are required to perform this procedure.

4.2. MATERIAL AND EQUIPMENT N/A - Not applicable to this procedure 4.3. SPECIAL REQUIREMENTS N/A - Not applicable to this procedure 5.0 PRECAUTIONS/LIMITATIONS 5.1. PRECAUTIONS N/A - Not applicable to this procedure 5.2. LIMITATIONS This procedure is NOT intended for use by the Emergency Director (ED).

6.0 PREREQUISITES A declared emergency or an emergency drill/exercise must exist before using this procedure.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE PiANT F I HATCH I 3 OF 10 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:

8.0 I REFERENCE 7.0 PROCEDURE 7.1 SUPERINTENDENT OF SHIFT (SOS)

NUE [ALERT SITE- GENERAL I llAREA 7.1.1 Review the event and classify the emergency x x x x in accordance with 73EP-EIP-001-0, Emergency Classification and Initial Actions.

7.1.2 Assume the duties of the ED in accordance x x x x with 73EP-EIP-004-0, Duties of Emergency Director.

7.1.3 After turnover of ED duties, perform the following:

7.1.3.1 Direct operation of the plant to mitigate x x x x consequences of the event and to restore to a safe operating condition.

7.1.3.2 Analyze plant conditions and assist the ED X X X X with reclassifications and protective action recommendations.

7.1.3.3 Advise the ED and TSC Manager on X x x x degrading plant conditions, initiation of any release or changes in the magnitude of any release as soon as practical.

7.1.3.4 Ensure communications is established and x x x maintained with the emergency response facilities (ERFs), NRC, and Security, as appropriate.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR lPAGE PLANT E.. HATCH I 4 OF 10 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:

8.0 7.2 SUPERINTENDENT OF SHIFT (SOS) (CONT'D)

[NUE l ALERT l SITE- l GENERAL I lAREA 7.1.3.5 IF the main access road can not be used as x x x x a site exit route, coordinate with the Emergency Director and Security to open the alternate site exit route(s) to allow evacuating personnel to leave the plant site.

7.1.3.6 IF the following conditions are present which x xX may prevent facility activation, dismissal of personnel from the protected area or plant site, THEN consult with the ED and Security prior to dispatching Control Room personnel, making PA announcements or augmenting on-shift staffing:

security events

severe weather conditions

other hazards that affect personnel safety .

END OF 7.1, SUPERINTENDENT OF SHIFT (SOS)

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE PLANT F I HATCH I 5 OF 10 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:

8.0 7.2 SHIFT SUPERVISOR (SS)

NUE [ALERT SITE- GENERAL I AR E 7.2.1 IF the SOS is unavailable or incapacitated, x x x x assume the duties of SOS and perform the SOS duties in accordance with section 7.1 of this procedure. IF available, assign any qualified SRO to assume the unit SS duties.

7.2.2 Direct operation of the plant to mitigate x x x x consequences of the event and to restore to a safe operating condition.

7.2.3 Activate emergency response teams, IF X x x x necessary, by contacting the TSC (or the Health Physics office and other support departments IF the TSC is not activated) and provide directions regarding needed actions.

7.2.4 Assist in the performance of prompt offsite X x x x dose assessments, as needed.

7.2.5 Advise the SOS on any degradation of plant X X X X equipment, onset of a release, and changes in release magnitude as soon as possible.

7.2.6 Establish communications with the ERFs, x x x Plant Security, the ED and the NRC as requested by SOS.

END OF 7.2, SHIFT SUPERVISOR (SS)

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE PiAMNT F I HATCH I 6 OF 10

* ., ., _ . .. _ _ I DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:

8.0 7.3 SHIFT SUPPORT SUPERVISOR (SSS)

NUE I ALERT SITE- GENERAL AREA 7.3.1 Maintain accountability of all SOs dispatched X T from the Control Room. l l l l NOTE: All entries to areas with higher than normal radiological conditions must be dispatched from the OSC.

l NUE l ALERT l SITE- GENERAL l l l AREA 7.3.2 Ensure SOs are logged on the Operations l X lX X rounds blanket RWP to track their dose. l1l NOTE: Os can be dispatched with no limitations provided radiological conditions are not degraded.

NUE ALERT SITE- [GENERAL I AREA 7.3.3 Dispatch SOs to perform various tasks to x X X assist in mitigation of an emergency condition.

7.3.4 Coordinate with Control Room Operators to X X X monitor ARM readings and plant conditions for the location where SOs have been dispatched. IF conditions change, THEN withdraw all personnel dispatched to that location.

7.3.5 Send extra SOs to the OSC as conditions X X X allow. SOs for shutdown activities will remain in the Control Room.

END OF 7.3, SHIFT SUPPORT SUPERVISOR (SSS)

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE PLANT E-l HATCH I 7 OF 10 DOCUMENT TITLE: DOCUMENT NUMBER: REVISION/VERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:

8.0 7.4 CONTROL ROOM OPERATOR NUE ALERT SITE- GENERAL 7.4.1 Take actions to place the plant ina safe X X X X condition in accordance with annunciator response procedures, emergency operating procedures and Technical Specifications.

7.4.2 Periodically report plant status to the SS. X X X X 7.4.3 Notify the SS or SOS of any degradation to X X X X plant equipment.

7.4.4 Perform prompt offsite dose assessment X X X calculations in accordance with 73EP-EIP-018-0, Prompt Offsite Dose Assessment, as required. Refer to 'Prerequisites" section of 73EP-EIP-018-0 to determine necessity to perform prompt offsite dose assessment calculation. Notify the SOS or SS of the onset of a release or any change in the magnitude of release. When the TSC is activated, turnover dose assessment duties to the TSC and exit procedure 73EP-EIP-018-0.

7.4.5 Notify the SSS of changes in plant conditions, X X X radiological conditions or radiological releases.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE PLANT E.l. HATCH 8 OF 10 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:

8.0 7.4 CONTROL ROOM OPERATOR (CONT'D)

CAUTION: CHANGES IN WIND DIRECTION MAY REQUIRE CHANGING RALLY POINTS AND EVACUATION ROUTES; THEREFORE, USE OF AVERAGE WIND DIRECTION IS ACCEPTABLE AND DESIRED. BE AWARE OF CHANGING CONDITIONS.

l NUE ALERT SITE- GENERAL l l -- l AREA 7.4.6 Complete form TRN-0144, Emergency Page Announcement Guide, filling in the X X X X required sections.

7.4.7 Obtain concurrence from the SOS for PA x x x x announcements being made for the following circumstances:

security events

severe weather conditions

other hazards that affect personnel safety.

NOTE: The purpose of making announcements is to inform plant personnel of an event or change in conditions that warrants a response. The timeliness and accuracy of the announcement will have a direct effect on the implementation of that response.

Announcements are normally concise statements containing sufficient detail to elicit the appropriate response.

NUE I ALERT I SITE- l GENERAL I____- AREA _

7.4.8 Verify with the SOS/ED that Security has been directed to merge the plant PA X X X X system with the Simulator Building PA system prior to beginning emergency announcements.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE PLANT E. HATCH 9 OF 10 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:

8.0 NUE ALERT SITE- GENERAL I A AREA 7.4.9 Sound the applicable warning tone, THEN make the appropriate announcement as X X X X directed by the SOS or SS and using the applicable section of form TRN-0144, Emergency Page Announcement Guide.

The appropriate announcement/tone will be made as soon as practicable but will not exceed 15 minutes after an initial emergency declaration. Additionally, the announcement/tone will be repeated every thirty (30) minutes for the first two (2) hours of the declared emergency. After the first two (2) hours, the announcement/ tone will be repeated as directed by the SOS or SS.

END OF 7.4, CONTROL ROOM OPERATOR MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE PLANT E.l. HATCH 10 OF 10 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONIVERSION ON-SHIFT OPERATIONS PERSONNEL EMERGENCY DUTIES 73EP-EIP-005-0 NO:

8.0 7.5 SYSTEM OPERATOR (SO)

NUE ALERT SITE- GENERAL AREA 7.5.1 Complete current assigned task OR restore x x X equipment to a safe condition and report status to the Control Room.

7.5.2 Report to the SSS in the Control Room and X X x remain under his direction until dispatched to the OSC.

NOTE: Unusual circumstances may require personnel to immediately terminate work activities and exit the area. These circumstances include, but are not limited to:

an ARM alarms in the work area

the worker's digital dosimeter alarms, or

a radiological event is announced and personnel are directed to evacuate the area NUE ALERT l SITE- I GENERAL

___________________________j - j- jAREA 7.5.3 IF unusual circumstances occur in or near X X X your present location, THEN terminate your work activities, exit the area and report back to the SSS in the Control Room.

END OF 7.5, SYSTEM OPERATOR (SO)

MGR-0001 Rev. 3

SOUTHERN NUCLEAR DOCUMENT TYPE: PAGE PLANT E.I. HATCH EMERGENCY PREPAREDNESS PROCEDURE 1 OF 5 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION ASSEMBLY, ACCOUNTABILITY AND EVACUATION 73EP-EIP-011-0 NO:

5.0 EXPIRATION APPROVALS: EFFECTIVE DATE: DEPARTMENT MANAGER JCL DATE 4/14/2003 DATE:

4/22/2003 N/A NPGM/POAGM/PSAGM DRM DATE 4/17/2003 1.0 OBJECTIVE This procedure provides instructions for assembly, accountability, and evacuation of site personnel during a declared emergency.

TABLE OF CONTENTS Section Title Pagqe 7.0 PROCEDURE 7.1 INVOLVED PERSONNEL 2 7.2 NON-INVOLVED PERSONNEL 3 (INSIDE THE PROTECTED AREA) 7.3 NON-INVOLVED PERSONNEL 5 (OUTSIDE THE PROTECTED AREA) 2.0 APPLICABILITY This procedure applies to the activities and responses of personnel that are necessary to assemble, account for, and evacuate site personnel during an emergency. This procedure is performed as required.

3.0 REFERENCES

3.1 IOAC-MGR-006-0, Hatch Emergency Plan 3.2 Edwin I. Hatch Unit 1 & Unit 2 Emergency Plan 3.3 73EP-EIP-009-0, Nuclear Security Duties

3.4 Forms

TRN-0159, Directions to State Reception Centers I 4.0 RESPONSIBILITIES 4.1 PERSONNEL REQUIREMENTS Personnel who conduct assembly, accountability, and evacuation of personnel will receive indoctrination and training in applicable emergency implementing procedures.

4.2 MATERIAL AND EQUIPMENT N/A - Not applicable to this procedure MGR-0002 Rev. 8

SOUTHERN NUCLEAR PAGE PLANT E.I. HATCH 2 OF 5 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION ASSEMBLY, ACCOUNTABILITY AND EVACUATION 73EP-EIP-011-0 NO:

15.0 4.3 SPECIAL REQUIREMENTS N/A - Not applicable to this procedure 5.0 PRECAUTIONS/LIMITATIONS 5.1 PRECAUTIONS Uncertain or varying levels of radiation and/or contamination may be encountered.

5.2 LIMITATIONS N/A - Not applicable to this procedure 6.0 PREREQUISITES A declared emergency OR an emergency drill/exercise must exist before using this procedure.

I REFERENCE 7.0 PROCEDURE 7.1 INVOLVED PERSONNEL NUE ALERT ARTEA GENERAL l l l AREAl 7.1.1 Report incident status to the Control Room and take actions to limit the incident, IF possible. Retreat to an X X X X unaffected area.

7.1.2 Report to the Health Physics Office for contamination surveys and decontamination, IF applicable. X 7.1.3 Contact Health Physics in the Operations Support X X Center (OSC) for contamination surveys and decontamination.

END OF 7.1, INVOLVED PERSONNEL MGR-0002 Rev. 8

SOUTHERN NUCLEAR PAGE PLANT E.I. HATCH I 3 OF 5 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION ASSEMBLY, ACCOUNTABILITY AND EVACUATION 73EP-EIP-011-0 NO:

5.0 7.2 NON-INVOLVED PERSONNEL (INSIDE THE PROTECTED AREA)

NOTE: Personnel actions (i.e., emergency response facility activation, escorting visitors to the PESB, evacuation from the site, etc.) may be delayed as a result of a security event, severe weather conditions or other hazards to personnel safety. l NUE 1ALERT SITE- l GENERAL

______ __IAREAj 7.2.1. Observe the Public Address (PA) announcements and/or warning signals for emergency information (i.e., X X declaration, upgrades in severity and evacuation orders). Stay clear of affected areas.

7.2.1.1 Remain at your present location until further notice IF a security emergency is occurring. X 7.2.2 Stand by for an escalation in emergency classification and continue normal work activities until advised X otherwise.

7.2.3 Emergency Response Organization members will report to assigned facility [Technical Support Center (TSC), X X X Operations Support Center (OSC) or Emergency Operations Facility (EOF)].

7.2.4 Escort all escorted personnel to Plant Entry Security Building (PESB) for processing out. These persons will X X X be directed to report to the Simulator cafeteria and await further instructions on actions to be taken.

7.2.5 Department supervisory personnel will account for personnel under their supervision. The names of personnel who are unaccounted must be immediately reported to Security at the PESB.

7.2.6 Secure your work location. IF in a contaminated area, follow normal undressing and frisking procedures as time allows. THEN, go to your reporting area and await further instructions.

7.2.7 Secure your work location. IF in a contaminated area, follow normal undressing and frisking procedures as time allows.

______________________________________________________________________ L A L A MGR-0002 Rev. 8

SOUTHERN NUCLEAR PAGE PLANT E.l. HATCH I 40F5 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION ASSEMBLY, ACCOUNTABILITY AND EVACUATION 73EP-EIP-011-0 NO:

5.0 7.2 NON-INVOLVED PERSONNEL (INSIDE THE PROTECTED AREA) (CONT'D)

NOTE:

The Emergency Director may order evacuation of non-essential personnel at any emergency classification.

Unless otherwise specified, the rally points designated for use are the Plant Entry Security Building (PESB) or Gate 17 (Northwest section of the protected area).

_ _NUE ALERT I SITE-l GENERAL 7.2.8 Leave the protected area, using the designated rallyX X X X point, as directed by PA announcement and/or Security force personnel. Turn in your protected area badge, IF directed to do so by Security personnel. Submit to radiological monitoring as directed by Rally Point Team members. Report to the Simulator cafeteria and await further instructions on actions to be taken.

7.2.9 Leave the plant site using specified site exit routes as directed by PA announcement and/or Security force X X X X personnel. IF DIRECTED, report to the appropriate State Reception Center for contamination monitoring IF a radiological release is underway AND radiological monitoring at the plant site is not feasible. Areas designated as State Reception Centers are shown in form TRN-01 59.

END OF 7.2, NON-INVOLVED PERSONNEL (INSIDE THE PROTECTED AREA)

MGR-0002 Rev. 8

SOUTHERN NUCLEAR PAGE PLANT E.I. HATCH 50F5 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION ASSEMBLY, ACCOUNTABILITY AND EVACUATION 73EP-EIP-011-0 NO:

5.0 7.3 NON-INVOLVED PERSONNEL (OUTSIDE THE PROTECTED AREA)

NOTE: Personnel actions (i.e., emergency response facility activation, escorting visitors to the PESB, evacuation from the site, etc.) may be delayed as a result of a security event, severe weather conditions or other hazards to personnel safety.

NUE ALERT SITE- GENERAL I AREA 7.3.1 When notified, Emergency Response Organization members will report to their assigned facility (TSC, OSC, X X X or EOF).

7.3.2 IF in areas with a PA system, personnel will observe PA announcements/ warning tones and stay clear of X X X X affected areas.

7.3.3 IF in areas without a PA system, personnel will observe instructions provided by Security, stay clear of affected X X X areas, secure their work location and THEN report to the Simulator Building cafeteria for further instructions.

NOTE:

The Emergency Director may order evacuation of non-essential personnel at any emergency classification.

Unless otherwise specified, the rally points designated for use are the Plant Entry Security Building (PESB) or Gate 17 (Northwest section of the protected area).

l NUE l ALERT l SITE- GENERAL I I AREA l 7.3.4 Leave the plant site using specified site exit routes as directed by PA announcement and/or Nuclear Security X X X personnel. IF DIRECTED, report to the State Reception Center IF DIRECTED, report to the appropriate State Reception Center for contamination monitoring IF a radiological release is underway AND radiological monitoring at the plant site is not feasible. Areas designated as State Reception Centers are shown inform TRN-0159.

I END OF 7.3, NON-INVOLVED PERSONNEL (OUTSIDE THE PROTECTED AREA)

MGR-0002 Rev. 8

SOUTHERN NUCLEAR lDOCUMENT TYPE: PAGE PLANT E.I. HATCH EMERGENCY PREPAREDNESS PROCEDURE 1 OF 12 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION PROMPT OFFSITE DOSE ASSESSMENT 73EP-EIP-018-0 NO:

7.0 EXPIRATION APPROVALS: EFFECTIVE DATE: DEPARTMENT MANAGER JCL DATE 4/14/2003 DATE:

4/22/2003 N/A NPGM/POAGM/PSAGM DRM DATE 4/17/2003 1.0 OBJECTIVE This procedure provides the initial method used by the Control Room Staff to determine the dose I rate at the site boundary to assist in Emergency Classifications based on gaseous effluent. This procedure also provides the projection of offsite TEDE and CDE doses to assist in the initial protective action recommendations (PARs).

TABLE OF CONTENTS Section Title Pace 2.0 APPLICABILITY 1

3.0 REFERENCES

2 4.0 REQUIREMENTS 2 5.0 PRECAUTIONS/LIMITATIONS 3 6.0 PREREQUISITES 5 7.0 PROCEDURE 6 7.2 SYSTEM START-UP 6 7.3 DATA ACQUISITION 6 7.4 DETERMINATION OF OFFSITE DOSE RATES 8 AND DOSE PROJECTIONS 7.7 DOCUMENTATION AND RECORDS 11 Attachment 1 GENERIC SCREEN GUIDELINES 12 2.0 APPLICABILITY This procedure is applicable to initial determinations of offsite dose based upon estimated noble gas release from the Main Stack and Unit 1 and Unit 2 Reactor Building Vents. This procedure is performed as required.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR I PAGE PLANT E.I. HATCH 2 OF 12 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION PROMPT OFFSITE DOSE ASSESSMENT 73EP-EIP-018-0 NO:

7.0

3.0 REFERENCES

3.1 1OAC-MGR-006-0, Hatch Emergency Plan 3.2 20AC-ADM-002-0,Quality Assurance Records Administration 3.3 73EP-EIP-001-0, Emergency Classification and Initial Actions 3.4 73EP-EIP-005-0, On-Shift Operations Personnel Emergency Duties 3.5 73EP-EIP-054-0, Protective Action Recommendations to State and Local Authorities 3.6 64CI-OCB-032-0, KAMAN 3.7 31EO-EOP-013-1/2, Primary Containment Control 3.8 73EP-EIP-015-0, Offsite Dose Assessment

3.9 Forms

TRN-0052 MIDAS Input Data Acquisition

TRN-0146 Prompt Offsite Dose Assessment Flowchart 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS 4.1.1 Emergency response personnel who have been trained in and are responsible for Emergency Classification and offsite dose assessment are required to perform this procedure.

4.1.2 The number and qualifications of personnel performing this procedure during an emergency will be determined by the SOS/ED.

4.2 MATERIAL AND EQUIPMENT 4.2.1 Dose Rate Instrument 4.2.2 Key for Main Stack Door MS-2 MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE PLANT E.I. HATCH 3 OF 12 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION PROMPT OFFSITE DOSE ASSESSMENT 73EP-EIP-018-0 NO:

7.0 4.2.3 The system requirements for the Meteorological Information and Dispersion Assessment System (MIDAS) dose assessment program are:

I Component Minimum system Recommended system CPU 486 DX 586 DX (Pentium)

Speed 50 MHz 133MHZ (or higher)

RAM 16 MB (greater speed is achieved 32 MB through use of a RAM disk (8 MB)

Hard Disk 240 MB 480 MB Floppy drive 1.44 MB 1.44 MB Interface Mouse Mouse Monitor VGA VGA Ports 1 parallel, 2 Serial 1 parallel, 2 serial Keyboard 101 101 Operating DOS 5.0 DOS 6.0 or higher system Printer HP DeskJet 550 C HP DeskJet 550 C 4.3 SPECIAL REQUIREMENTS Obtain a Radiation Work Permit (RWP) or a Health Physics escort when entering the Main Stack Operating Deck.

5.0 PRECAUTIONS / LIMITATIONS 5.1 PRECAUTIONS 5.1.1 Significant radiation hazards may be encountered during entries to obtain local instrument readings. Maintain occupational exposure As Low As Reasonably Achievable (ALARA) in the performance of assigned duties.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE PLANT E-l HATCH 4 OF 12 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION PROMPT OFFSITE DOSE ASSESSMENT 73EP-EIP-018-0 NO:

7.0 5.1.2 IF any of the following Annunciators are indicated on annunciator panels, INFORM the Chemistry department PRIOR to requesting the Chemistry Department to obtain a grab sample if a grab sample is required; 1H1-11-P650-2 MAIN STACK EFFLUENT ANY COLLECTOR RADN LEVEL MAXIMUM MAIN STACK EFFLUENT ALL COLLECTORS RADN LEVEL MAXIMUM RB VENT EFFL ANY COLLECTOR RADN LEVEL MAX RB VENT EFFL ALL COLLECTORS RADN LEVEL MAX 2H1 1-P650-2 RB VENT EFFL ANY COLLECTOR RADN LEVEL MAX RB VENT EFFL ALL COLLECTORS RADN LEVEL MAX 5.2 LIMITATIONS 5.2.1 This procedure can NOT be used to downgrade the severity of an emergency classification.

5.2.2 This procedure is based upon using the Meteorological Information and Dispersion Assessment System (MIDAS) for calculating indications of offsite dose and dose rates.

MIDAS utilizes data from both radiological and meteorological plant instrumentation.

Readings may be obtained from SPDS, control room monitors, and/or locally at the instruments. Information is required for all three release paths (Main Stack, Ul Rx Bldg.

Vent, and U2 Rx Bldg. Vent).

FNOTE: Values obtained from MIDAS for the purpose of Protective Action Recommendations are based on the avoided dose concept.

5.2.3 For the purpose of Protective Action Recommendations (PARs), the TEDE and CDE values for Site Boundary, 2 miles, 5 miles, and 10 miles from the printed ENN Worksheet providedI by MIDAS may be utilized.

MGR-0001 Rev. 3

l-SOUTHERN NUCLEAR PAGE PLANT E.L HATCH 5 OF 12 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION PROMPT OFFSITE DOSE ASSESSMENT 73EP-EIP-018-0 NO:

7.0 6.0 PREREQUISITES 6.1 Contact Health Physics prior to making entries to obtain local radiation readings, OR entry into the main stack for grab samples.

6.2 The annunciators outlined in white in the Main Control Room are indications of a potential release condition; the following annunciators may indicate a radioactive release.

6.2.1 Main Stack Annunciators Annunciator Panel Number OFF GAS VENT RADIATION HIGH-HIGH 1H11-P601-4 OFF GAS VENT RADIATION HIGH 1H11-P601-4 OFF GAS VENT RADIATION DNSC/INOP 1H11-P601-4 OFF GAS VENT SAMPLE FLOW HIGH/LOW 11 11-P601-4 6.2.2 Unit I Reactor Building Vent Stack annunciators Annunciator Panel Number RX BLDG VENT SAMPLE FLOW HIGH/LOW 1H11-P601-4 REFUELING FLOOR VENT EXHAUST RADIATION HI-HI 1H11-P601-4 RX BLDG STACK RADN MON HIGH-HIGH 1H11 -P603-2 RX BLDG STACK RADN MON HI 1H11 -P603-2 6.2.3 Unit 2 Reactor Building Vent Stack Annunciators Annunciator Panel Number RX BLDG VENT EXHAUST RADIATION HI-HI 2H11-P601-2 RX BLDG VENT EXHAUST RADIATION HIGH 2H11-P601-2 RX BLDG VT MON HIGH/LOW FLOW 2H1-1-P601-4 DOWNSCALE/INOP REFUELING FLOOR VENT EXHAUST RADIATION HI-HI 2H11-P601-4 MGR-0001 Rev. 3

SOUTHERN NUCLEAR I PAGE PLANT E.I. HATCH I 6 OF 12 DOCUMENT TITLE: DOCUMENT NUMBER: REVISION/VERSION PROMPT OFFSITE DOSE ASSESSMENT 73EP-EIP-018-0 NO:

17.0 I REFERENCE l 7.0 PROCEDURE 7.1 Upon indication of a potential release condition as indicated by step 6.2, and activation of this procedure, perform the following steps or utilize the job aid in TRN-0146, Prompt Offsite Dose Assessment Flowchart.

7.2 SYSTEM START-UP NOTE:

General instructions for the use of the MIDAS Code are found in Attachment 1, Generic Screen Guidelines for MIDAS.

The MIDAS Program files are loaded on the hard drive of the computer located at the STA's desk.

7.2.1 With the computer off, obtain the MIDAS startup disk from the Emergency Director notebook and insert the MIDAS startup disk in the "A" drive of the computer containing the MIDAS program files.

7.2.2 Turn the computer on.

7.2.3 The computer will normally automatically "boot" into the MIDAS subdirectory and start the program.

7.2.4 WHEN prompted by the computer, enter the current date (mm-dd-yyyy) and time (HH.MM.SS.00 a/p). IF the current date and time are correct, press "ENTER".

7.2.5 IF it is determined that the MIDAS computer cannot be initiated properly or a prompt offsite dose assessment cannot be performed for any reason, THEN turn over dose assessment responsibilities to the TSC.

7.2.5.1 IF the TSC is not activated, contact the on-shift HP/Chemistry foreman and instruct him to initiate dose assessment activities on the dose assessment computer in the TSC.

7.3 DATA ACQUISITION 7.3.1 Instruments in alarm will be handled in accordance with the applicable annunciator response procedures.

7.3.2 IF any annunciator or indication is determined to be "inoperable" or unavailable, THEN increased operator awareness will be required to determine if an effluent release is ongoing.

MGR-0001 Rev. 3

l SOUTHERN NUCLEAR I PAGE PLANT E.I. HATCH I 7 OF 12 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION PROMPT OFFSITE DOSE ASSESSMENT 73EP-EIP-018-0 NO:

7.0 7.3.3 The MIDAS code requires the input of meteorological and radiological data. The data required is listed in TRN-0052, MIDAS Data Input Acquisition. TRN-0052 may be used to gather data for input. Data is to be gathered in accordance with the following steps.

7.3.3.1 Record readings from the appropriate meteorological instrumentation. Appropriate meteorological instrumentation are listed in TRN-0052 Page 1 of 3. Record only valid readings. IF the primary meteorological instrumentation listed is unavailable, THEN use TRN-0052 page 2 of 3, Alternate Meteorological Instrument Designation for Dose Assessment Use, to determine which alternate meteorological instrumentation can be utilized.

7.3.3.2 Record readings from the appropriate effluent monitors. Appropriate effluent monitors are listed in TRN-0052 Page 3 of 3, Radiological Data Entry. Record only valid readings as indicated below. Record EITHER Normal Range OR Accident Range Effluent Monitor (KAMAN) value and the flow associated with that value. Do NOT record or enter data for both monitors or both flows for each release point. MIDAS will sum the release and significantly overestimate the dose rate and projected dose output.

7.3.3.3 IF it is determined that the normal range effluent monitor is offscale high or not functioning AND the accident range instrumentation (KAMAN) does not function for the Main Stack, Unit 1 Rx Bldg. or Unit 2 Rx Bldg. vent monitors, THEN turn over dose assessment responsibilities to the TSC.

7.3.3.3.1 IF the TSC is not activated, contact the on-shift HP/Chemistry foreman and instruct him to initiate dose assessment activities on the dose assessment computer in the TSC.

7.3.3.4 IF there is a difference between the A and B channel readings for the Unit 1 Rx Bldg.

Stack Vent monitor (1D11-R619 A/B), Unit 2 Rx Bldg. Stack Vent Monitors (2D11-R619 A/B) OR Main Stack monitor readings (1D11-R600 A/B), THEN use the most conservative (higher) reading for input into MIDAS.

7.3.3.5 IF the effluent monitors AND either: THEN:

exceed any of the following values:

Main Stack Normal

An abnormal plant Notify the SOS/ED that a Range 2 500 cps condition exists Or radioactive release is in

Either Reactor Bldg.

An emergency has progress and Stack Vent 10,000 been declared immediately proceed with cpm OR a dose projection.

The sum of Unit 1 and Unit 2 Reactor Bldg Stack Vent is 2 10,000 cpm MGR-0001 Rev. 3

SOUTHERN NUCLEAR I PAGE PiANT EI HATCH I 8 OF 12 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION PROMPT OFFSITE DOSE ASSESSMENT 73EP-EIP-018-0 NO:

7.0 7.3.3.6 A Hi-Hi Alarm contact from 1Dl1-RIS-K600 AB (34AR-601-412-1 S) will trip the normal range effluent monitor 1D11-P001 and start both the Accident Range Effluent Monitor 1D11-P007 (KAMAN) and the Wide Range Recorder 1D11 -R631 (BLUE Pen). Normal Kaman Operation is indicated on SPDS primary screen by vent stack window changing red with a value showing.

7.3.3.7 A Hi- Hi Alarm contact from 1D11 -RIS-K61 9 ANB (34AR-603-216-1 S) will trip the normal range effluent monitor 1D11 -P002 and start both the Accident range effluent monitor 1D11-P601 (KAMAN) and the Wide range Recorder 1D11-R631 (RED Pen). Normal Kaman Operation is indicated on SPDS primary screen by vent stack window changing red with a value showing.

7.3.3.8 A Hi- Hi Alarm contact from 2D1 1-RIS-K636 ANB (34AR-601-229-2S) will trip the normal range effluent monitor 2D1 1-P002 and start both the Accident range effluent monitor 2D1 1-P601 (KAMAN) and the Wide range Recorder 2D1 1-R631 (RED Pen). Normal Kaman Operation is indicated on SPDS primary screen by vent stack window changing red with a value showing.

7.3.3.9 IF the Control Room flow instruments are inoperable or unreliable; THEN the default flow values listed on TRN-0052, page 3 of 3 may be utilized for input.

7.4 DETERMINATION OF OFFSITE DOSE RATES AND DOSE PROJECTIONS 7.4.1 From the SITE SELECTION menu screen, select "PLANT HATCH". The selection will illuminate.

7.4.2 Select "CONFIRM" to continue.

7.4.3 From the FUNCTION SELECTION menu screen, select "ACCIDENT DOSE CALCULATIONS". The selection will illuminate.

7.4.4 Select "CONFIRM" to continue.

7.4.5 The SCENARIO DATA TABLE CONTROL menu screen will appear. You may perform an initial projection or an update projection.

7.4.5.1 To perform an initial projection, select 'START NEW SCENARIO" to initialize the dose projection spreadsheets. A warning will appear to confirm that you wish to initialize.

Select"CONFIRM" to continue.

7.4.5.2 To perform an update projection, select "CURRENT SCENARIO EDIT" to perform an update calculation.

7.4.6 The METEOROLOGICAL DATA spreadsheet will appear. Enter meteorological data from TRN-0052 as required by the spreadsheet at the current time. The current time frame will be illuminated. If performing an update, data previously entered will be displayed.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR I PAGE PLANT E.I. HATCH 9 OF 12 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION PROMPT OFFSITE DOSE ASSESSMENT 73EP-EIP-018-0 NO:

7.0 7.4.7 Depress the "X" key to save the data on the spreadsheet and exit to the remainder of the program.

CAUTION: RELEASE POINT MONITOR DATA MAY BE DISPLAYED ON SPDS IN UNITS OTHER THAN THOSE REQUIRED BY MIDAS. IF USING SPDS FOR DATA ACQUISITION, CHECK ALL UNITS TO ENSURE THAT THE UNITS MATCH THOSE REQUIRED BY MIDAS. SPDS MAY DISPLAY THE SAME MONITOR l-- ON DIFFERENT SCREENS IN THE APPROPRIATE UNIT.

7.4.8 The GASEOUS VENT AND FLOW spreadsheet will appear. Enter the data from TRN-0052 as required by the spreadsheet at the current time. The current time frame will be illuminated. If performing an update, data previously entered will be displayed.

__________________ i CAUTION: THE GASEOUS VENT AND FLOW SPREADSHEET CONTAINS (13) DATA I COLUMNS, OF WHICH (8) DATA COLUMNS ARE DISPLAYED. THE ADDITIONAL (5) DATA COLUMNS CAN BE DISPLAYED BY USING THE "RIGHT" ARROW KEY ONCE DATA HAS BEEN ENTERED IN THE FIRST (8)

DATA COLUMNS SHOWN ON THE INITIAL SCREEN. FAILURE TO ENTER DATA FOR EACH RELEASE POINT WILL RESULT IN A POTENTIAL UNDERESTIMATE OF THE OFFSITE DOSE RATE AND PROJECTED DOSE ESTIMATES.

7.4.9 Depress the "X" key to save the data on the spreadsheet and exit to the remainder of the program.

CAUTION: IF THE REMAINING DURATION OF THE RELEASE IS UNKNOWN, A DEFAULT REMAINING DURATION OF 240 MINUTES (4 HOURS) WILL BE l l UTILIZED.

7.4.10 The RELEASE TIMING menu screen will appear. The "DURATION" field will display the total number of minutes from the onset of the release to the current time plus the time period specified in "REMAINING DURATION". The "REMAINING DURATION" field will display the default release duration of 240 minutes. Changes made to the "REMAINING DURATION" field will be automatically reflected in the "DURATION" field.

7.4.10.1 IF the default "REMAINING DURATION" of 240 minutes is acceptable, select "CONFIRM" to continue.

7.4.10.2 IF the "REMAINING DURATION" is determined to be some time period other than 240 minutes, THEN enter the release duration time in minutes and select "CONFIRM" to continue. IF a release time other than 240 minutes is used, THEN ensure this information is provided to the TSC or EOF Dose Assessment staff when a transfer of Dose Assessment responsibility occurs.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR I PAGE PLANT E.I. HATCH I 10 OF 12 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION PROMPT OFFSITE DOSE ASSESSMENT 73EP-EIP-018-0 NO:

7.0 NOTE: MIDAS will perform the required calculations. A plot of the Total Effective Dose Equivalent (TEDE) Rate will be displayed on the screen. The peak TEDE rate used for release determination and classification is shown on the right center portion of the screen. A working copy of the Emergency Notification Form will be delivered to the attached printer. Line 13 of the working copy of the ENN form contains TEDE and Thyroid CDE values for the site boundary, 2, 5, and 10 mile distances.

_______________ -L 7.4.11 MIDAS will display a plot of the Total Effective Dose Equivalent (TEDE) rate based on a .25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months (15 minute) projection. The display gives an estimated peak TEDE Dose Rate value at or beyond the site boundary. The display also includes the direction and distance for this value.

7.4.11.1 The current calculated daily average site dose rate is >E-03 mR/hr. IF the peak TEDE dose rate (mR/hr) value is an order of magnitude (10 times) higher than this value > E-02 mR/hr AND an emergency has been declared THEN notify the Emergency Director that a radioactive release is in progress.

7.4.11.2 IF the peak TEDE Dose Rate value exceeds 0.057 mR/hr (5.7 E-02 mR/hr), THEN notify the Emergency Director for possible emergency classification declaration or upgrade AND notify the affected Unit Shift Supervisor for possible EOP Actions.

7.4.12 MIDAS will print a working copy of the ENN Form. The values listed on line 13 of the working copy of the ENN Form may be utilized for the purpose of making Protective Action Recommendations (PARs) to state and local authorities. IF required, PARs will be made in accordance with 73EP-EIP-054-OS, Protective Action Recommendations.

7.4.13 Printouts of the working copy of the Emergency Notification Form can be obtained if it does not print properly or additional copies are needed. First, attempt to correct the problem with the printer, if appropriate, then follow the steps below.

7.4.13.1 Select "CONTINUE" from the TEDE RATE PLOT Screen, then select "NEXT REPORT",

then "MORE REPORTS" which will display the available report selections. Select the option "SEND STATE REPORT TO PRINTER", then select "CONFIRM". This will send the working copy of the ENN Form to the printer.

7.4.14 Report the TEDE and Thyroid CDE values from line 13 of the working copy of the ENN Form to the Emergency Director. IF this report is not available, the information may be obtained from the TEDE 4-day report and Thyroid CDE options under more reports. Values will be based on the 4-hour projection period.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE PLANT E.I. HATCH 11 OF 12 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION PROMPT OFFSITE DOSE ASSESSMENT 73EP-EIP-018-0 NO:

7.0 NOTE: You may elect to continue your evaluation of this projection or exit to perform an update projection.

CAUTION: CHOICES AVAIABLE UNDER THE "MORE REPORTS" MENU SCREEN WITH l ~THE EXCEPTION OF EXIT ARE BEYOND THE SCOPE OF THISl l ~PROCEDURE. USE OF THESE OPTIONS FOR THE PERFORMANCE OF l I PROMPT OFFSITE DOSE ASSESSMENT IS NOT REQUIRED.l 7.4.15 To exit, select "CONTINUE" from the TEDE RATE PLOT Screen, then select "NEXT REPORT", then "MORE REPORTS" which will display the available report selections. From this screen select "EXIT" which requires a double "click" with the mouse. This will return you to the FUNCTION SELECTION menu screen.

7.5 IF the dose assessment capabilities are functional from the TSC or EOF, THEN turnover Offsite Dose Assessment to either facility and proceed to subsection 7.7. TSC or EOF activation is NOT required prior to turnover of dose assessment activities.

7.6 IF the dose assessment capabilities are NOT functional from the TSC or EOF, THEN continue to monitor the gaseous effluent release parameters until instructed to terminate dose assessment activities by the SOS/ED. IF any of these parameters begin to increase, THEN perform additional prompt offsite dose assessment calculation(s) as follows:

7.6.1 IF not already at the "Function Selection" menu screen, return to the "Function Selection" menu screen.

7.6.2 Perform additional dose projections in accordance with subsection 7.3, Data Acquisition and 7.4, Determination of Offsite Dose Rates and Dose Projections.

7.7 REVIEWS AND RECORDS Records generated during actual emergencies will be maintained in accordance with 20AC- I ADM-002-0, Quality Assurance Records Administration.

MGR-0001 Rev. 3

SNC PLANT E.I. HATCH l Pg. 12 of 12 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

OFFSITE DOSE ASSESSMENT 73EP-EIP-018-0 7.0 ATTACHMENT 1 Att. Pg.

TITLE: GENERIC SCREEN GUIDELINES 1 of 1 GENERIC SCREEN GUIDELINES MIDAS utilizes a "point and click" feature for all menu applications.

Menu choices will illuminate when selected. Invalid choices will not illuminate.

> Menu choices backlit in red indicate important selectors.

> All menu selections must be "confirmed". This is accomplished by selecting the "CONFIRM" option on the screen.

> The NUMPAD is used to enter data which may be required as a result of selecting a box on the screen.

> "EXIT" is used to stop processing and return to the function menu. A double click is required.

> "CONFIRM" is used to save selections and display the next screen.

"RESET" will clear box selections if "clicked" once and will reset the user to the previous screen(s) if "clicked" twice. On the first screen (Accident Run Menu) reset has no effect.

> Selecting "CONFIRM" before selecting the required boxes will result in a beep and no changes will be made.

NUMPAD DATA ENTRY

> IF the NUMPAD is selected by mistake, select "EN" to return to the main screen.

> IF the entry is NOT complete or NOT valid, selecting "EN" will NOT be accepted.

> To correct an erroneous entry into the NUMPAD, select "EN" with the display box empty.

> IF reset is selected after a NUMPAD entry has been completed ("EN" is selected), THEN all of the data for every screen box will be cleared.

> To clear data for any one screen box, select the box and redefine the data value (do not use reset since all boxes will be cleared).

> Plus signs are not necessary but minus signs are required for negative numbers including exponential notation (e.g., 1E-6).

> On the meteorological screen, stability class may be entered as a letter between A and G. In this case the NUMPAD will contain each letter.

> Red warning message will appear when there is a problem with data that makes it impossible to continue the calculations. Selecting continue will allow you to correct the erroneous data.

Selecting "EXIT" will return you to the menu selection screen.

MGR-0009 Rev. 4

SOUTHERN NUCLEAR DOCUMENT TYPE: PAGE PLANT E.I. HATCH I EMERGENCY PREPAREDNESS PROCEDURE 1 OF 18 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION CORE DAMAGE ASSESSMENT 73EP-EIP-023-OS NO:

0.4 EXPIRATION APPROVALS: EFFECTIVE DATE: DEPARTMENT MANAGER CLC DATE 9-19-90 DATE:

04122/2003 N/A NPGM/POAGM/PSAGM HLS DATE 9-19-90 1.0 OBJECTIVE The objective of this procedure is to provide the instruction necessary during emergency conditions to evaluate the extent of core damage.

TABLE OF CONTENTS Section Title Page 2.0 APPLICABILITY 2

3.0 REFERENCES

2 4.0 REQUIREMENTS 2 5.0 PRECAUTIONS/LIMITATIONS 2 6.0 PREREQUISITES 3 7.0 PROCEDURE 3 7.1 CORE DAMAGE ESTIMATE BASED ON 3 FISSION PRODUCT CONCENTRATION 7.2 CORE DAMAGE ESTIMATE BASED ON 10 DRYWELL WIDE RANGE MONITORS 7.3 CORE DAMAGE ESTIMATE BASED ON 11 CONTAINMENT HYDROGEN 7.4 RECORDS 11 Attachments 1 Relationships Between Isotopes and Core 12 Damage 2 Reference Plant Fuel Inventory Release 16 3 Post LOCA Monitor [Log (Multiplier)] 17 4 Containment % Hydrogen Versus % Zr-Steam 18 Reaction MGR-0002 Rev. 8

SOUTHERN NUCLEAR PAGE 2 OF 18 PLANT E.I. HATCH DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION CORE DAMAGE ASSESSMENT 73EP-EIP-023-OS NO:

0.4 2.0 APPLICABILITY This procedure is applicable to the evaluation of core damage under accident conditions for both Unit 1 and Unit 2. Procedure frequency will be as necessary. Individual subsections, or methods for determining core damage, may be performed out of sequence IF necessary to expedite the determination of core damage.

3.0 REFERENCES

3.1 1OAC-MGR-006-OS, Hatch Emergency Plan 3.2 NEDO-2215, Procedure for the Determination of the Extent of Core Damage Under Accident Conditions, by C.C. Lin 3.3 NEDE-30050A, Engineering Training, Degraded Core 3.4 20AC-ADM-002-0, Quality Assurance Records Administration 3.5 FULL SIZE FORM

TRN-01 14, Core Damage Assessment Log 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS Personnel performing this procedure must be trained in performing the calculations required by this procedure and familiar with procedure content.

4.2 MATERIAL AND EQUIPMENT Calculator or computer for performing calculations 4.3 SPECIAL REQUIREMENTS N/A - Not applicable to this procedure 5.0 PRECAUTIONSILIMITATIONS 5.1 PRECAUTIONS N/A - Not applicable to this procedure MGR-0001 Rev. 3

SOUTHERN NUCLEAR IPAGE 3 OF 18 PLANT E.I. HATCH I DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION CORE DAMAGE ASSESSMENT 73EP-EIP-023-0S NO:

0.4 5.2 LIMITATIONS The calculation of core damage fraction is only as accurate as the measurements used in this procedure's calculations. Accurate measurements of Cs-137 and Kr-85 activities are not very likely until the reactor has been shut down for longer than a few weeks and most of the shorter-lived isotopes have decayed.

6.0 PREREQUISITES An abnormal plant condition, drill or exercise must exist prior to performing this procedure.

I REFERENCE l 7.0 PROCEDURE 7.1 CORE DAMAGE ESTIMATE BASED ON FISSION PRODUCT CONCENTRATION 7.1.1 RCS/CAS Sampling Request the OSC to dispatch Chemistry personnel to obtain a reactor coolant and/or containment atmosphere sample and perform a gamma isotopic analysis of the sample(s). I NOTE: PASS reactor coolant data will be provided in pCi/ml. This unit of measure is equivalent to pCi/g and does not need to be converted.

7.1.1.1 Obtain the following applicable information from Chemistry when the gamma isotopic analysis of the sample(s) are complete:

Reactor coolant 1-131 and Cs-137 concentration (pCi/g)

Containment atmosphere Xe-133 and Kr-85 concentration (uCi/cc)

Containment atmosphere pressure (psig) and temperature (OF)

Containment atmosphere manual grab sample pressure (psig) and temperature (OF) [available only if manual grab sample is obtained]

Method of sampling (automated system or manual grab sample) 7.1.1.2 Request Chemistry to provide a copy of the sample's gamma isotopic analysis results to the TSC Reactor Engineer.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR IPAGE 4 OF 18 Pi ANT F I HATC.H I DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION CORE DAMAGE ASSESSMENT 73EP-EIP-023-0S NO:

0.4 7.1.2 Pressure/Temperature and Decay Correction 7.1.2.1 Record the following applicable information on TRN-0114, Core Damage Assessment Log:

1-131 and Cs-1 37 concentrations as Cw

Xe-133 and Kr-85 concentration(s) as Cg

Containment atmosphere pressure and temperature

Containment atmosphere manual grab sample pressure and temperature

[available only if manual grab sample is obtained]

7.1.2.2 Decay correct the measured concentration(s) of 1-131 and Cs-1 37 in Reactor Coolant from the time of reactor shutdown by using the following formula. Record the decay corrected water sample concentrations (Cwo) for 1-131 and Cs-137 on TRN-0114, Core Damage Assessment Log.

Cwo = Cw ext Where:

CWo = activity concentration in water sample decay corrected to the time of shutdown (J4Ci/g)

Cw = measured activity concentration in water sample (ptCi/g)

X = decay constant of isotope: 1-131 = 0.086/days; Cs-1 37 = 6.31 E-5/days t = decay time between reactor shutdown and analysis of activity concentration (days) 7.1.2.3 IF the 1-131 concentration is determined to be greater than 100,Ci/g, report this information to the TSC Manager and the Emergency Director to evaluate for appropriate emergency classification.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR lPAGE 5 OF 18 PLANT E.I. HATCH I I DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION CORE DAMAGE ASSESSMENT 73EP-EIP-023-OS NO:

0.4 7.1.2.4 Decay correct the measured concentrations of Xe-133 and Kr-85 in Containment Atmosphere from the time of reactor shutdown by using the applicable formula below. Record the corrected gas sample concentrations (Cgo) for Xe-133 and Kr-85 on TRN-0114, Core Damage Assessment Log.

IF the method of THEN:

sampling is:

Automated Use the following formula:

Cg = C eXt Where:

Cgo = activity concentration in gas sample decay and pressure/

temperature corrected to time of shutdown(uCi/cc) g = measured activity concentration in gas sample (jaCi/cc)

decay constant of isotope: Xe-133 = 0.131/days, Kr-85

1.77 E-4/days t = decay time between reactor shutdown and analysis of activity concentration Manual Grab Use the following formula:

go = 1PT2 Where:

Cgo = activity concentration in gas sample decay and pressure/

temperature corrected to time of shutdown(uCi/cc)

Cg= measured activity concentration in gas sample (piCilcc)

decay constant of isotope: Xe-133 = 0.131/days, Kr-85

1.77 E-4/days t = decay time between reactor shutdown and analysis of activity concentration P2= Containment pressure (psig)

T2 = Containment temperature (0 F)

P1 = Manual Grab sample pressure (psig)

T1= Manual Grab sample temperature (OF)

J MGR-0001 Rev. 3

SOUTHERN NUCLEAR IPAGE 6 OF 18 PLANT E.I. HATCH I DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION CORE DAMAGE ASSESSMENT 73EP-EIP-023-0S NO:

0.4 7.1.3 Analysis of Fission Product Concentration Compare the sample activities to the upper limit values on Table 1, Fission Product Concentrations In Reactor Water and Drywell Gas Space During Reactor Shutdown Under Normal Conditions.

7.1.3.1 IF the corrected concentration of a fission product in reactor water or containment atmosphere is measured to be higher than the upper limit values shown in Table 1, perform subsection 7.1.4 through 7.1.5. The extent of fuel or cladding damage can then be determined directly from Attachment 1 based on isotopes 1-131, Cs-137, Xe-133, and Kr-85.

7.1.3.2 IF the corrected concentrations fall into the range where release of the fission product from the fuel gap or the molten fuel cannot be definitively determined, perform subsection 7.1.4 through subsection 7.1.7. The additional data in subsections 7.1.6 and 7.1.7 may be needed to determine the source of fission product release.

TABLE 1 FISSION PRODUCT CONCENTRATIONS IN REACTOR WATER AND DRYWELL GAS SPACE DURING REACTOR SHUTDOWN UNDER NORMAL CONDITIONS REACTOR WATER (uCi/g) DRYWELL GAS (uCi/cc)

ISOTOPE UPPER LIMIT NOMINAL UPPER LIMIT NOMINAL 1-131 29 (Note D) 0.7 (Note D) l Cs-137 (Note C) 0.3 (Note A) .03 (Note B) l Xe-1 33 1 E-4 (Note A) 1 E-5 (Note B)

Kr-85 _ 4 E-5 (Note A) 1 4 E-6 (Note B)

Note A: Observed experimentally, in an operating BWR/3 with Mark I containment.

Note B: Assuming 10% of the upper limit values.

Note C: Release of Cs-1 37 will strongly depend on core inventory which is a function of fuel burnup.

Note D: These values consider iodine spiking, i.e., they are the highest values expected in a "normal" iodine spiking transient.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR IPAGE 7 OF 18 PLANT El HATCH DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION CORE DAMAGE ASSESSMENT 73EP-EIP-023-OS NO:

0.4 7.1.4 Fission Product Inventory Calculate and record on TRN-01 14, Core Damage Assessment Log, the inventory correction factor for each isotope by performing the following:

NOTE:

Calculating reactor operation back from time of shutdown for a period equal to 6 isotope half-lives will normally be accurate enough.

The half- lives of the applicable isotopes are as follows: 1-131 = 8.05 days; Cs-137 = 30 years; Xe-133 = 5.27 days; Kr-85 = 10.76 years.

7.1.4.1 Break the reactor power history prior to the event into "N" periods. In each period power variations must normally be limited to + 20%. Record the results on TRN-0114, Core Damage Assessment Log.

7.1.4.2 Calculate the Inventory Correction Factor for each isotope "i" using the following formula. Record results on TRN-0114, Core Damage Assessment Log.

3651 [1 - e-1095 A]

Fli = --------------------------------

n

[P( - e-ATJ )-ATOJ]

j=l Where:

F11 =inventory correction factor for isotope "i" pi = steady reactor power operated in period j (MWth)

Tj = duration of operating period j (day)

Toj =time (in days) between the end of operating period j and time of the last reactor shutdown (day) k= decay constant of isotope: Xe-1 33 = 0.132/days, Kr-85 =

1.77E-4/days, 1-131 = .086/days, Cs-137 = 6.29E-5/days MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE 8 OF 18 PLANT E.l. HATCH I DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION CORE DAMAGE ASSESSMENT 73EP-EIP-023-OS NO:

0.4 7.1.5 Equivalent Activity Concentration and Fuel Damage Assessment NOTE:

The dilution correction factor for either a Unit 1 or a Unit 2 water sample (Ew) is 0.68.

The dilution correction factor for either a Unit 1 or a Unit 2 gas sample (Fg) is 0.18.

7.1.5.1 Calculate the equivalent activity concentration (Czw and Czg) for each isotope, using the following formulas. Use the results from 7.1.2.2, 7.1.2.4, 7.1.4.2, 7.1.5.1 and 7.1.5.2 and the applicable dilution correction factor from the note above.

Czw = Cwo x Fix Fw Czg Cgo x F. x Fg Record results on TRN-0114, Core Damage Assessment Log 7.1.5.2 Compare the calculated equivalent activity concentrations with the appropriate graph in Attachment 1 to determine the amount of produced (i.e., fraction of fuel tubes with failed cladding or fraction of U02 melted). Record results on TRN-0114, Core Damage Assessment Log.

7.1.6 Isotope Ratio Comparison NOTE: Because certain isotopes will be released preferentially due to a cladding failure versus a fuel melting, the presence of higher or lower relative amounts provide an indication of which type of failure occurred.

7.1.6.1 Determine from the isotopic analysis of the containment atmosphere gas sample and reactor coolant sample the concentrations of Xe-1 33, Kr-87, Kr-88, and Kr-85m,1-131,1-132,1-133,1-134 and 1-135. Record on TRN-0114, Core Damage Assessment Log.

MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE 9 OF 18 PLANT E.I. HATCH DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION CORE DAMAGE ASSESSMENT 73EP-EIP-023-OS NO:

0.4 7.1.6.2 Decay correct the above concentrations to the time of shutdown using the following formula. Record the results on TRN-0114, Core Damage Assessment Log:

A0 =AeXt Where:

AO= activity concentration decay corrected to time of shutdown A =measured activity concentration in sample

decay constant of isotope: Xe-133 = 0.131/days, Kr-85m

3.7/days, Kr-87 = 13.13/days, Kr-88 = 5.94/days, 1-131 =

0.086/days, 1-132 = 7.263/days, 1-133 = 0.8/days, 1-134 =

18.972/days and 1-135 = 2.535/days t = decay time between reactor shutdown and analysis of isotope concentration (days) 7.1.6.3 Determine the ratio of the decay corrected noble gas concentrations (Kr-87, Kr-88, and Kr-85m) to the Xe-1 33 concentration (decay corrected to time of shutdown).

Record the resulting ratios on TRN-01 14, Core Damage Assessment Log.

7.1.6.4 Determine the ratio of the decay corrected iodine isotope concentrations (1-132, 1-133, 1-134, and 1-135) to the 1-131 concentration (decay corrected to time of shutdown). Record the resulting ratios on TRN-0114, Core Damage Assessment Log.

7.1.6.5 Compare the ratio(s) to the expected values given in Table 2, Ratios of Isotopes in Core Inventory and Fuel Gap. Record any conclusions reached as to cladding failure or fuel melt on TRN-01 14, Damage Assessment Log.

TABLE 2 RATIOS OF ISOTOPES IN CORE INVENTORY AND FUEL GAP ACTIVITY RATIO ACTIVITY RATIO ISOTOPE HALF-LIFE IN CORE INVENTORY IN FUEL GAP Kr-87 76m 0.233 0.0234 Kr-88 2.84h 0.33 0.0495 Kr-85m 4.48h 0.122 0.023 1-134 52.6m 2.3 0.155 1-132 2.28h 1.46 0.127 1-135 6.59h 1.97 0.364 1-133 20.8 2.09 0.685 MGR-0001 Rev. 3

SOUTHERN NUCLEAR I lPAGE 10 OF 18 PLANT E.I. HATCH I I DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION CORE DAMAGE ASSESSMENT 73EP-EIP-023-0S NO:

0.4 7.1.7 Low Volatility Isotopes Another indication of a fuel melt release is the presence of low volatility isotopes. IF the less volatile fission products, [i.e., isotopes of Sr, Ba, and Ru (either soluble or insoluble)]

are found to have unusually high concentrations in the water sample, a fuel meltdown to some extent may be assumed. In a mixture of fission products, 2.7h Sr-92 (1.385 MeV) and 40h La-140 (1.597 MeV) will normally be relatively easy to identify and measure through gamma isotopic analysis.

7.1.7.1 Record on TRN-0114, Core Damage Assessment Log the concentrations of any isotope of the following elements measured: Sr, Ba, Ru and La.

7.1.7.2 Record on TRN-01 14, Core Damage Assessment Log the conclusions reached, if any, concerning Cladding Failure or Fuel Melt.

7.2 CORE DAMAGE ESTIMATE BASED ON DRYWELL WIDE RANGE MONITORS 7.2.1 Determine the Drywell Wide Range Monitor (DWWRM) reading, (D1 1-K621 A & B found on panels Hll-P689 and H1I-P690) (R) in Rem/hr. Record the results on TRN-0114, Core Damage Assessment Log.

7.2.2 Determine elapsed time from plant shutdown to the DWWRM reading (t) in hours. Record the results on TRN-0114, Core Damage Assessment Log.

7.2.3 Use Attachment 2 to determine the reference plant fuel inventory release 'ref in %.

Record the results on TRN-01 14, Core Damage Assessment Log.

7.2.4 Determine the inventory release to the containment (I) using the following formula. Record the results on TRN-0114, Core Damage Assessment Log.

I = Iref (.6855) X (V) X (6/D)

Where:

V = normalizing of total containment free volume: Unit 1 = 1.08, Unit 2 = 1.07 D =distance of detector from reactor biological shield wall, ft.

1D11-K621 A = 2.5 ft, 1D11-K621 B = 3.5 ft 2D1 1-K621 A = 2.5 ft, 2D11-K621 B = 3.5 ft MGR-0001 Rev. 3

SOUTHERN NUCLEAR PAGE 11 OF 18 PLANT E.l. HATCH DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION CORE DAMAGE ASSESSMENT 73EP-EIP-023-0S NO:

0.4 7.2.5 IF the DWWRM are inoperable, Post LOCA Monitor readings must be used to calculate an estimate of core damage. The following equation must be used to determine the equivalent DWWRM reading:

Equivalent DWWRM Reading = (Post LOCA monitor reading) (1 Ox)

Where X = the Log (multiplier) from Attachment 3.

7.2.6 Compare the hours after shutdown (on x-axis) with the curve plotted on Attachment 3 to determine the log (multiplier) (on y-axis). Once the Equivalent DWWRM reading is determined, complete steps 7.2.3 and 7.2.4.

7.3 CORE DAMAGE ESTIMATE BASED ON CONTAINMENT HYDROGEN A consequence of inadequate cooling (loss-of-coolant accident) can be the production of hydrogen; the primary source is from the zirconium water reaction. The extent of fuel clad damage can be estimated by determination of containment hydrogen concentration.

7.3.1 Obtain the containment hydrogen monitor reading in % hydrogen (%H) and record on TRN-0114, Core Damage Assessment Log.

7.3.2 Apply the containment % H to Attachment 4, Containment % Hydrogen Versus % Zr-Steam Reaction, to determine the percent Zr-Steam reaction for the reference plant (% Zr-SteamRef). Record on TRN-01 14, Core Damage Assessment Log.

7.3.3 Determine the % Zr-Steam reaction (extent of fuel clad damage) by performing the following calculation and record the % Zr-Steam reaction on TRN-0114, Core Damage Assessment Log.

% Fuel Clad Damage = (% Zr-SteamRef) x (.925) 7.4 RECORDS Submit completed TRN-0114, Core Damage Assessment Log sheets to the Technical Support Center (TSC) Manager for review and evaluation. Records generated during actual emergencies will be maintained in accordance with 20AC-ADM-002-0, Quality Assurance Records Administration.

MGR-0001 Rev. 3

SNC PLANT E.I. HATCH I Pg. 12 of 18 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

CORE DAMAGE ASSESSMENT 73EP-EIP-023-OS 0.4 ATTACHMENT 1 Att. Pg.

TITLE: RELATIONSHIPS BETWEEN ISOTOPES AND CORE DAMAGE 1 of 4 1-131 147.000 14.700 cm 1,470 147 3

14.7 1-

-4 1.47

.147 1.. .A..a..L.,-- I._._..I . , ._._._.....

0.1 1.0 10 100 1* o CLADDING FAILURE -i 1.0 100 1 Z FUEL MELTDOWN -

Relationship Between 1-131 Concentration in the Primary Coolant (Reactor Water + Pool Water) and Extent of Core Damage.

MGR-0009 Rev. 4

SNC PLANT E.I. HATCH l Pg. 13 of 18 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

CORE DAMAGE ASSESSMENT 73EP-EIP-023-OS 0.4 ATTACHMENT I Att. Pg.

TITLE: RELATIONSHIPS BETWEEN ISOTOPES AND CORE DAMAGE 2 of 4 Cs-1 37 14,700 1.470 147

-J LI I.- 14.7 L15Y C.-)

C)

F-W-.

9S-1.47 r-

<M

.147

.0147 O.1 1.0 10 100 4 CLADDING FAILURE -

1.0 100 1 -- FUEL MELTDOWN -$

Relationship Between Cs-137 Concentration in the Primary Coolant (Reactor Water + Pool Water) and Extent of Core Damage MGR-0009 Rev. 4

SNC PLANT EJl. HATCH . Pg 14 of 18 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

CORE DAMAGE ASSESSMENT 73EP-EIP-023-OS 0.4 ATTACHMENT I Att. Pg.

TITLE: RELATIONSHIPS BETWEEN ISOTOPES AND CORE DAMAGE 3 of 4 Xe-1 33 55,000 5,550 V~ 550 Van

-5 I-

° 5.50 cc CD 2

z U b s 0.5 x05 0.1 1.0 10 100 14 - CLADDING FAILURE E-1.0 I( 00

'..FUEL MELTDOWN 1l Relationship Between Xe-133 Concentration in the Containment Gas (Drywell e Torus I Gas) and Extent of Core Damage MGR-0009 Rev. 4

SNC PLANT E.I. HATCH I Pg. 15 of 18 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

CORE DAMAGE ASSESSMENT 73EP-EIP-023-0S 0.4 ATTACHMENT 1 Att. Pg.

TITLE: RELATIONSHIPS BETWEEN ISOTOPES AND CORE DAMAGE 4 of 4 Kr-85 _

550 55 i-5.5 L"

ISl C-c co 0.55.

cc I-taJ cj

=p en

.055 By

.005

.0005 L-0.1 1.0 10 100 e - %CLADDING FAILURE - 4 1.0 100 14 - FUEL MELTDOWN .9-Relationship Between Kr-85 Concentration in the Containment Gas (Drywell + Torus Gas)l and Extent of Core Damage I MGR-0009 Rev. 4

SNC PLANT E.I. HATCH I Pg. 16 of 18 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

CORE DAMAGE ASSESSMENT 73EP-EIP-023-OS 0.4 ATTACHMENT 2 Att. Pg TITLE: REFERENCE PLANT FUEL INVENTORY RELEASE 1 of 1 Percent of Fuel Inventory Airborne in the Containment 108 100% Fuel Inventory = 100% Noble Gases

+ 25% Iodine

+ 1X- Particulate!

-S (U

CD ARE:

45 Ca 40 4-S C)

.0 TIME SHUT DOWN (iHRS)-

l Percent of Fuel Inventory Airborne in Containment MGR-0009 Rev. 4

DOCUMENT TITL: lDOCUMENT NUMBER: RevNer No:

CORE DAMAGE ASSESSMENT I 73EP-EIP-023-OS 0.4 ATTACHMENT 3 Att. Pg.

TITLE: POST LOCA MONITOR [LOG (MULTIPLIER)] 1 of 1 3.

2.8.

2.6 -

2.4 2.2 2

1.8 1.6 0

IQa. 1.4 1.2 0

-j 1

0.8 0.6 0.4 0.2 0

0 20 40 Hours After Shutdown X-AXitS)

Post LOCA Monitor Log Multiplier MGR-0009 Rev. 4

SNC PLANT E.I. HATCH l Pg. 18 of 18 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

CORE DAMAGE ASSESSMENT 73EP-EIP-023-OS 0.4 ATTACHMENT 4 Att. Pg.

TITLE: % CONTAINMENT HYDROGEN VERSUS % ZR-STEAM REACTION 1 of 1 100 - - - - J * - - - - -

90 80

____________________ I I ______

1 1 3 BWR-MAR 1 & II V =300,OOOft 70 ______ _______ _______ _______ I. _______ _______ _______

I.-

= 60 I __ __

1 Li w

cc 50

1

= 40 __ __ I __ __ __ __

1*

a-

__ __ __ 1 __ __ __

30 20

_____ _____ A _____ _____

10 0

IA -

. - - - - - rn U lu zu 3u qu DU Du fU oqJ OU 7v v

- Zr-STEAM REACTION l Containment % Hydrogen versus % Zr-Steam Reaction MGR-0009 Rev. 4

SOUTHERN NUCLEAR lDOCUMENT TYPE: PAGE PLANT E.l. HATCH EMERGENCY PREPAREDNESS PROCEDURE 1 OF 22 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION OFFSITE EMERGENCY NOTIFICATIONS 73EP-EIP-073-0 NO:

15.1 EXPIRATION APPROVALS: EFFECTIVE DATE: DEPARTMENT MANAGER J. C. Lewis DATE 1/24/2003 DATE:

4/2212003 N/A NPGM/POAGM/PSAGM J. A. Betsill DATE 1/27/2003 1.0 OBJECTIVE This procedure provides instructions for initial and follow-up notifications to State and Local authorities by emergency communication networks and systems. This procedure further provides initial notification time requirements and systems to be used for communicating with the Nuclear Regulatory Commission (NRC) in the event of a declared emergency. Included in the time requirements are instructions for utilizing the appropriate emergency communication links.

TABLE OF CONTENTS Section Title Page 2.0 APPLICABILITY 2

3.0 REFERENCES

2 4.0 REQUIREMENTS 2 5.0 PRECAUTIONS/LIMITATIONS 3 6.0 PREREQUISITES 3 7.0 PROCEDURE 4 7.1 Notification to State and Local Authorities 4 7.2 Initial Notifications 5 7.3 Follow-up Notifications 8 7.4 Communications Protocol and Use 9 7.5 False Notifications 9 7.6 NRC Notifications 9 7.7 Major Loss of Communications Systems 10 7.8 Documentation and Records 10 Attachment 1 Emergency Notification Form Information 11 Attachment 2 Operating Instructions for Southern LINC 18 Equipment for ENN Notifications Attachment 3 Major Loss of Communications Systems 19 Attachment 4 "Quick Guide: Instructions to Perform ENN 21 Notification Attachment 5 Instructions to Fax the ENN Form (TRN-0001) 22 MGR-0002 Rev. 8

SOUTHERN NUCLEAR I PAGE PLANT E.I. HATCH l 2 OF 22 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION OFFSITE EMERGENCY NOTIFICATIONS 73EP-EIP-073-0 NO:

15.1 2.0 APPLICABILITY This procedure is applicable to the use of emergency communications networks and systems to notify federal (NRC), State and Local authorities during an emergency. This procedure is performed as required.

3.0 REFERENCES

3.1 Edwin I. Hatch Nuclear Plant, Unit 1 and Unit 2 Emergency Plan 3.2 10AC-MGR-006-0, Hatch Emergency Plan 3.3 30AC-OPS-003-0, Plant Operations 3.4 31GO-OPS-013-0, Notifications and Reports 3.5 TRN-0001, Emergency Notification Form 3.6 00AC-REG-001-0, Federal and State Reporting and Federal Document Posting Requirements 3.7 REG-0024, Reporting Requirements 3.8 NUREG-1022, Event Reporting Guidelines, 10 CFR 50.72 and 50.73 3.9 73EP-ADM-001-0, Maintaining Emergency Preparedness 3.10 73EP-EIP-054-0, Protective Action Recommendations to State and Local Authorities 3.11 20AC-ADM-002-0, Quality Assurance Records Administration 3.12 Emergency Call List 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS 4.1.1 The Emergency Director authorizes offsite notifications of emergency conditions to State and Local authorities.

4.1.2 The Emergency Director may delegate, to other specifically trained emergency response personnel, actual performance of notifications.

4.2 MATERIAL AND EQUIPMENT Emergency communication systems MGR-0001 Rev. 3

SOUTHERN NUCLEAR I PAGE PI ANT P I ATC.H I 30 F 22 DOCUMENT TITLE: DOCUMENT NUMBER: REVISIONNERSION OFFSITE EMERGENCY NOTIFICATIONS 73EP-EIP-073-0 NO:

15.1 4.3 SPECIAL REQUIREMENTS The Emergency Director shall authorize notification to offsite authorities.

5.0 PRECAUTIONS/LIMITATIONS 5.1 PRECAUTIONS N/A - Not applicable to this procedure 5.2 LIMITATIONS 5.2.1 Initial notifications to State and Local authorities must be initiated within approximately (15) minutes of declaring or changing emergency classifications. Information which may not be available at the time of initial notification will be included on the subsequent message as soon as it becomes available.

5.2.2 Notification of protective action recommendations (PARs) to State and local authorities must be initiated within 15 minutes of approval of the PARs.

5.2.3 Follow-up notifications to State and Local authorities will be made periodically during an Alert or higher emergency classification.

5.2.4 Notification to State and Local authorities, regarding significant events which potentially impact offsite emergency actions, must be initiated within approximately (15) minutes of the event occurring. Significant events to be reported include, but are not limited to the following situations:

An actual radiological release

Any event of itself which indicates degradation of plant conditions

Any event which indicates a threat to core or containment integrity

Any event, which will impact offsite resources (for example: dismissal of non-essential plant personnel, transportation offsite of contaminated injured personnel, requests for offsite support, etc.)

5.2.5 Emergency communication systems will be used to transfer emergency information during a declared emergency OR an emergency drill/exercise.

6.0 PREREQUISITES A declared emergency or an emergency drill/exercise must exist before using this procedure.

MGR-0001 Rev. 3

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15.1 REFERENCE 7.0 PROCEDURE 7.1 NOTIFICATION TO STATE AND LOCAL AUTHORITIES i

CAUTION: SPECIAL CARE MUST BE TAKEN IN TRANSFERRING RESPONSIBILITY FOR PERFORMING OFFSITE NOTIFICATIONS TO ANOTHER FACILITY. A PROPER TURNOVER IS IMPERATIVE. NOTIFICATION OF STATE AND LOCAL AUTHORITIES WILL BE MADE WITHIN APPROXIMATELY FIFTEEN MINUTES OF DECLARING OR CHANGING ANY EMERGENCY CLASSIFICATION. THE EMERGENCY DIRECTOR'S AUTHORIZATION MUST BE OBTAINED PRIOR TO TRANSMITTING THE NOTIFICATION MESSAGE.

-I 7.1.1 The Emergency Director will designate the Emergency Response Facility, which has priority over emergency notifications and communications (i.e., Control Room, TSC, or EOF). The Emergency Director in the Control Room will complete form TRN-0001, Emergency Notification, when offsite notifications originate from the Control Room. Designated personnel in the TSC or EOF will obtain the information to complete form TRN-0001, Emergency Notification, when offsite notifications originate from either of these locations.

7.1.2 Information contained on form TRN-0001, Emergency Notification, will be communicated to State and Local authorities via the Emergency Notification Network (ENN). Attachment 1 outlines the information requirements of form TRN-0001, Emergency Notification for initial and follow-up notifications. Attachment 2 outlines operating instructions for use of the Southern LINC equipment for ENN notifications. Attachment 5 outlines operating instructions for the fax machines used to fax for TRN-0001, Emergency Notification, to State and local authorities and the company emergency facility locations.

MGR-0001 Rev. 3

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15.1 NOTE: An initial notification is a notification which indicates an emergency classification has been declared and/or changed.

7.2 INITIAL NOTIFICATIONS 7.2.1 For initial notifications, obtain information to complete all line items (except line items 11, 12,

& 13) on form TRN, 0001, Emergency Notification. Line items 11, 12, & 13 may be omitted from the initial notification IF it is NOT available within the 15 minute initial notification timeframe or if "A" or "B" on line item 10 is checked. Line items 11, 12 & 13 must, however, be transmitted as soon as this information becomes available.

NOTE: The placard, shown in attachment 4, may be utilized to provide quick guidance on I steps necessary to perform ENN notifications.

7.2.2 Obtain the Emergency Director's approval on line item 16 of the information on form TRN-0001, Emergency Notification.

7.2.3 Complete the following items in line items 1-3 of form TRN-0001, Emergency Notification, after receipt of the approved form from the Emergency Director:

Message Number (facility abbreviation & sequential number).

Reported By (name of person transmitting information)

Transmittal time/date (of the verbal transmission of the information)

Confirmation phone number NOTE:

The Emergency Notification form is faxed to provide clarification to offsite authorities on emergency information reported to them.

The placard, shown in attachment 5, may be utilized to provide guidance on steps necessary to fax the ENN form.

7.2.4 Fax form TRN-0001, Emergency Notification, to the offsite authorities. Refer to attachment 5 for fax instructions.

MGR-0001 Rev. 3

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15.1 NOTE: Acknowledgment may be received from either the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months point of contact OR the l alternate point of contact for the State/Local authorities. I 7.2.5 Prior to verbally transmitting any information, alert the offsite authorities. Record the time acknowledgement is received on the back of the ENN form (TRN-0001). A message similar to the following may be used:

"This is (Give your Name and Title) at Plant Hatch. Stand by to receive emergency notification information using the Emergency Notification Form."

Please acknowledge Georgia Emergency Management Agency (GEMA).

Please acknowledge Appling County.

Please acknowledge Jeff Davis County.

Please acknowledge Tattnall County.

Please acknowledge Toombs County."

7.2.6 Acknowledgment must be received from GEMA and each Local authority. The acknowledgement may come from the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months point of contact, the State/Local Emergency Operations Center (EOC), or the County EMA Director. IF the State OR any Local authority fail to acknowledge using the ENN Southern LINC radio, the message transfer and acknowledgment must be obtained by commercial telephone (alternate communications method). The commercial telephone numbers for the State/local authorities are located in the Emergency Call List (section I., Offsite Agencies List, page 1). A facsimile of the notification form is also acceptable as an alternate communications method.

IF the Southern LINC equipment for ENN notifications is inoperable, complete notifications using commercial telephone to contact the offsite authorities. Inform the Emergency Director of the inoperable Southern LINC equipment. Contact Information Resources so that repairs can be initiated.

7.2.7 Proceed with verbally transmitting information from form TRN-0001, Emergency Notification using the Southern LINC radio or commercial telephone. Operating instructions for the Southern LINC radio are found in attachment 2. IF verbal transmission cannot be established, ensure a facsimile of the notification form is provided to the offsite authorities.

MGR-0001 Rev. 3

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15.1 NOTE: Acknowledgment may be received from either the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months point of contact OR the alternate point of contact for the State/Local authorities.

7.2.8 Complete the verbal notification with a statement similar to the following. Record the time acknowledgement is received on the back of the ENN form (TRN-0001).

Please acknowledge Georgia Emergency Management Agency (GEMA).

Please acknowledge Appling County.

Please acknowledge Jeff Davis County.

Please acknowledge Tattnall County.

Please acknowledge Toombs County."

7.2.9 Acknowledgment of receipt of the notification must be received from the State/Local authorities. IF the State OR Local authorities fail to acknowledge, then acknowledgment must be obtained by alternate means as outlined in step 7.2.6.

7.2.10 After completion of the above steps, fax form TRN-0001, Emergency Notification to the applicable company emergency facility locations. Refer to attachment 4 for fax instructions.

7.2.11 IF it is determined that any information, which has been provided to State and Local authorities, is in error, the information must be corrected. The Emergency Director's authorization must be obtained prior to transmitting the corrected information. It is acceptable to provide only the corrected information on the notification form.

MGR-0001 Rev. 3

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15.1 NOTE:

A follow-up notification is a notification, which provides additional information that relates to the current emergency classification.

Follow-up notifications to State and Local authorities will be made periodically during an Alert or higher emergency classification.

Notification to State and Local authorities, regarding significant events which potentially impact offsite emergency actions, must be initiated within approximately (15) minutes of the event occurring. Significant events to be reported include, but are not limited to the following situations:

An actual radiological release

Any event of itself which indicates degradation of plant conditions

Any event which indicates a threat to core or containment integrity

Any event, which will impact offsite resources (for example: dismissal of personnel, transportation offsite of contaminated injured personnel, I requests for offsite support, etc.)

I 7.3 FOLLOW-UP NOTIFICATIONS 7.3.1 For follow-up notifications, obtain information to complete, at a minimum, line items 1, 2, 3, 5, 6, & 7 on TRN-0001, Emergency Notification. Any changes in events which are occurring, any changes in parameters and/or any information which was not available within the 15 minute initial notification timeframe (line items 8-15) must be reported on the appropriate line item for all follow-up notifications. Any other line item that is not changed can be left blank. It is acceptable to provide only information that has changed for any item on the form for a follow-up notification.

7.3.2 Obtain the Emergency Director's approval on line item 16 of the information on form TRN-0001, Emergency Notification.

7.3.3 Refer to steps 7.2.3 through 7.2.11 to complete the follow-up notification to the State and Local authorities.

MGR-0001 Rev. 3

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15.1 7.4 COMMUNICATIONS PROTOCOL AND USE 7.4.1 Whenever one organization is contacting another organization, appropriate communications protocol must be used. An acceptable protocol is as follows:

Example: "GEMA, This is the EOF, over."

GEMA would then respond:

"EOF, this is GEMA, go ahead."

7.4.2 The ENN may also be used for the transmission of technical, radiological and meteorological data upon request of State and Local authorities.

7.5 FALSE NOTIFICATIONS 7.5.1 IF an attempted false notification OR other misuse of the ENN occurs, the speakers in the Emergency Operations Facility (EOF), Technical Support Center (TSC), and Control Room will automatically activate, allowing Plant Hatch personnel to also receive the information.

7.5.2 IF the information is an attempt to cause a false notification, supervisory personnel will lift the phone and state the following or a similar statement:

"Negative, Negative, Negative. This is (give Name and Title). Acknowledge negative."

7.5.3 Acknowledgment must be received from State and Local authorities. IF the State OR Local authorities fail to acknowledge using the ENN, acknowledgment must be obtained by alternate means as outlined in step 7.2.3.

7.6 NRC NOTIFICATIONS 7.6.1 The Emergency Director will ensure that notifications to the NRC will be in accordance with 31GO-OPS-013-O and OOAC-REG-001-0. Notifications to the NRC will be as soon as possible, but no later than one hour following declaration of the emergency.

7.6.2 The Emergency Director will designate the Emergency Response Facility which has priority over NRC Notifications and Communications (i.e., Control Room, or TSC). The Control Room will be relieved of this duty as soon as the TSC is activated.

7.6.3 IF requested by the NRC, an open communication pathway must be maintained.

Follow-up notifications to the NRC are required as conditions change (reactor/plant status, emergency class, release status, etc.).

MGR-0001 Rev. 3

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15.1 7.6.4 The primary method of communication with the NRC will be the Emergency Notification System (ENS). The ENS operates on the NRC Emergency Telecommunications System (ETS). Other ETS communication links in the TSC and EOF may also be utilized to contact the NRC Operations Center (NRCOC) as required. The other ETS communication links are listed below:

Health Physics Network (HPN)

Protective Measures Counterpart Link (PMCL)

Reactor Safety Counterpart Link (RSCL)

Management Counterpart Link (MCL)

To contact the NRC via the ENS or the other ETS communications links, dial the telephone numbers, either posted on the ENS (or ETS) phones or as listed in the Emergency Call List..

7.7 MAJOR LOSS OF COMMUNICATIONS SYSTEMS A major loss of communications capability maybe reportable to the NRC, in accordance with form REG-0024, Reporting Requirements. Refer to attachment 3 to determine if a major loss of communications has occurred.

7.8 DOCUMENTATION AND RECORDS 7.8.1 Emergency Response Facility personnel responsible for offsite notifications will document the notifications, acknowledgments, and pertinent communications to the State and Local authorities on the Emergency Notification Form. Notifications to the NRC will be documented in accordance with 31GO-OPS-013-0 and OOAC-REG-001-0.

7.8.2 All data and information generated during the emergency event will be maintained by applicable emergency response personnel in each facility. This information will be utilized to generate a written close-out report upon termination of the emergency event.

The report will be prepared as described in 73EP-ADM-001-0, Maintaining Emergency Preparedness.

7.8.4 Records generated during actual emergencies will be maintained in accordance with 20AC-ADM-002-0, Quality Assurance Records Administration.

MGR-0001 Rev. 3

SNC PLANT E.I. HATCH I Pg. 11 of 22 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

OFFSITE EMERGENCY NOTIFICATIONS l 73EP-EIP-073-0 15.1 ATTACHMENT 1 Att. Pg.

TITLE: EMERGENCY NOTIFICATION FORM INFORMATION 1 of 8 The following provides information on the type of information to include on the various line items of the Emergency Notification Form.

Item 1 Drill/Actual Emergency:

Check the appropriate block indicating the Emergency Notification is for drill/exercise

('This is a Drill") or an actual emergency condition ('This is an Actual Emergency").

Initial/Follow-up Check the appropriate block indicating the message is an "initial" or "follow-up" notification by checking the appropriate block. "Initial" will be checked for any notification associated with the declaration and/or change of an emergency classification. "Follow-up" will be checked for any notification, which provides additional information related to the current emergency classification.

Message Number Enter the facility abbreviation and sequential number of the notification being made.

The facility where notifications are made may change based on location of the Emergency Director; however, the number will remain sequential throughout the event (i.e., CR-1, TSC-2, EOF-3, etc.).

Item 2 Site:

Site location already filled in.

Unit:

Enter the affected unit number 1 or 2. In the event both units are involved in the emergency, enter unit number 1 & 2.

Reported by:

Enter name of person transmitting information.

Item 3 Transmittal Time/Date:

Enter time (Eastern) and date WHEN the verbal transmission of data begins.

Confirmation Phone Number:

Enter a plant phone number and extension (in your facility), to be used by the State and Local authorities for verification of information being transmitted.

Item 4 Authentication This block is NOT applicable for emergency notifications made at Plant Hatch.

MGR-0009 Rev. 4

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TITLE: EMERGENCY NOTIFICATION FORM INFORMATION 2 of 8 Item 5 Emergency Classification:

Check the appropriate block indicating the current emergency classification declared.

Refer to Facility Management to confirm this information.

Item 6 Emergency Declaration at:

Enter the time (Eastern) and date when the current emergency classification was declared. Refer to Facility Management to confirm this information.

Emergency Termination at:

Enter the time (Eastern) and date the emergency is terminated and proceed to item 16.

Refer to Facility Management to confirm this information.

NOTE:

Follow-up notifications to State and Local authorities will be made periodically during an Alert or higher emergency classification.

Notification to State and Local authorities, regarding significant events which potentially impact offsite emergency actions, must be initiated within approximately (15) minutes of the event occurring. Significant events to be reported include, but are not limited to the following situations:

An actual radiological release

Any event of itself which indicates degradation of plant conditions

Any event which indicates a threat to core or containment integrity

Any event, which will impact offsite resources (for example: dismissal of non-essential personnel, transportation offsite of contaminated injured personnel, requests for offsite support, etc.)

I L

Item 7 Emergency

Description:

Enter a brief description of the initiating conditions for the emergency classification declared and any other current information regarding significant events which have occurred since the last notification was made. This may include information on significant equipment which is out of service or malfunctioning. The use of acronyms to describe the emergency needs to be avoided. This section can also include important information to be given to the State and Local authorities. For example, IF a site evacuation is taking place, they will need to know information about the evacuation direction provided to evacuated plant personnel (i.e., evacuation route and applicable Reception Center). Refer to Facility Management to confirm this information.

MGR-0009 Rev. 4

SNC PLANT E.I. HATCH l IPg. 13 of 22 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

OFFSITE EMERGENCY NOTIFICATIONS l 73EP-EIP-073-0 15.1 ATTACHMENT 1 Att. Pg.

TITLE: EMERGENCY NOTIFICATION FORM INFORMATION 3 of 8 Item 8 Plant Condition:

Check the most accurate prognosis of current plant condition. Refer to Facility Management to confirm this information.

Item 9 Reactor Status:

Check the appropriate block to indicate the current status of the affected unit's reactor.

IF the unit is shutdown, enter the time (Eastern) and date of the shutdown. IF the unit is operating, indicate % power. Refer to Facility Management to confirm this information.

NOTE: Change in radiological release status must be reported to State and local N E authorities as soon as possible.

Item 10 Emergency Releases:

Check the appropriate block to indicate status of a radiological release:

A. None (Go to item 14)

B. Potential (Go to item 14);

C. Is Occurring D. Has Occurred The current calculated daily average site dose rate (for normal plant operations) runs in the mE-3 mR/hr range or below. IF it is determined, by dose projection calculations, that the peak TEDE dose rate (mRlhr) value at or beyond the site boundary is an order of magnitude (10 times) higher than the daily average site dose rate AND an emergency has been declared, THEN a radioactive release is in progress.

IF no release is occurring, check the "None" block and proceed to item 14.

IF a potential for release exists, check the "Potential" block and proceed to item 14.

IF a release is occurring, check the "Is Occurring" block and proceed to item 11.

IF a release has occurred, check the "Has Occurred" block and proceed to item 11.

Refer to Facility Management [i.e., TSC HP/Chem Supervisor or Dose Assessment Manager (in the EOF)] to confirm this information.

MGR-0009 Rev. 4

SNC PLANT E.I. HATCH IPg. 14 of 22 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

OFFSITE EMERGENCY NOTIFICATIONS 73EP-EIP-073-0 15.1 ATTACHMENT 1 Att. Pg.

TITLE: EMERGENCY NOTIFICATION FORM INFORMATION 4 of 8 NOTE:

Item 11 may be omitted from the initial notification IF it is NOT available within the 15 minute initial notification time frame. It must be included on the subsequent message.

The 100 m meteorological data must be used IF the radiological release is from the elevated release point.

The 10 m meteorological data must be used IF the radiological release is from the ground level release point.

Item 11 Type of Release:

Check the appropriate block to indicate IF the release is an elevated release (through the main stack) or a ground level release (through the reactor building vents) for the appropriate release. IF the release type is NOT known, assume that the release is from the elevated release point (Main Stack) until informed otherwise.

Indicate IF; A. Airborne or B. Liquid release is occurring or has occurred by entering the start time (eastern) and date and IF applicable the time and date the release stopped.

Item 12 may be omitted from the initial notification IF it is not available within the 15 minute initial notification time frame. It must be included on the subsequent message.

Item 12 Release Magnitude This section requires the completed results of dose assessment:

Check the appropriate block indicating units of measurement for the release.

Normal Operating Limits indicate IF release rates, projected at or beyond the site boundary, are above or below the TS limit of .057 mR/hr. IF the release rate is below TS limit of .057 mR/hr, THEN check the "BELOW" block. IF the release rate is above the TS limit of .057 mR/hr, THEN check the "ABOVE" block.

Enter the release rate (in "Ci/sec" or 'Curies") next to noble gases, iodines, particulates and other, as appropriate.

These values can be obtained from the dose projection printout, line item 12.

MGR-0009 Rev. 4

SNC PLANTE.I.HATCH l Pg. 15 of 22 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

OFFSITE EMERGENCY NOTIFICATIONS 73EP-EIP-073-0 15.1 ATTACHMENT 1 Att. Pg.

TITLE: EMERGENCY NOTIFICATION FORM INFORMATION 6 of 8 IOTE: item 13 may be omitted from the initial notification IF it is NOT available within the 15 minute initial notification time frame. It must be included on the subsequent message.

Item 13 Estimate of Proiected Offsite Dose:

Check the appropriate block indicating IF the projected offsite dose is new information or unchanged information from the last notification.

This section requires the completed results of dose assessment.

Check the appropriate block indicating IF the projected offsite dose is new information or unchanged information from the last notification. Enter the time of the dose projection from the dose projection printout. Enter the duration of dose projection in hours; this is normally a four (4) hour projected dose.

Enter the projected Total Effective Dose Eq. (TEDE) and Committed Dose Eq. (CDE) thyroid dose (in mrem) at site boundary, 2, 5, and 10 miles distances.

MGR-0009 Rev. 4

SNC PLANT E.I. HATCH l Pg. 16 of 22 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

OFFSITE EMERGENCY NOTIFICATIONS l 73EP-EIP-073-0 15.1 ATTACHMENT I Att. Pg.

TITLE: EMERGENCY NOTIFICATION FORM INFORMATION 7 of 8 NOTE:

Recording of Stability Class or the actual differential temperature (OF) reading is acceptable.

The 100 m meteorological data must be used IF the radiological release is from the elevated release point.

The 10 m meteorological data must be used IF the radiological release is from the ground level release point.

Item 14 Meteoroloqical Data:

This information is to be included on all notifications to the State and Local authorities.

This information may be found on the dose projection printout, the SPDS Meteorological Screen or the SPDS MIDAS Screen.

To determine Stability Class, use the following chart to convert differential temperature or Sigma Theta information to Stability Class:

Stability Class Conversion Table CSablass Differential Temperature (AT) (0 F) jSigma Theta (a8l~)

1 I Primary Met Tower II Backup Met Tower 1 Primary &

I Backup Met Towers lI l0m -l1in 60m-l10m ll 45m[-lm 11100, 60,45, & 10 m A

(extremely <-3.1 <-1.4 <-1.2 l 22.5 u n sta b le) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

B (moderately 2 -3.1 to < -2.8 2 -1.4 to < -1.3 2 -1.2 to -1.1 < 22.5 to 2 17.5 unstable)

(slightly unstable) l -2.8 to < -2.4 2 1.3 to < -1.1 2 -1.1 to < -0.9 < 17.5 to 2 12.5 l (neutral) l -2.4 to < -0.8 2 1.1 to < -0.4 2 -0.9 to < -0.3 < 12.5 to 2 7.5 l (slightly stable) j -0.8 to < 2.4 2 -0.4 to < 1.1 2 -0.3 to < 0.9 < 7.5 to 2 3.8 j(moderately stable) j 2.4 to < 6.5 2 1.1 to < 2.9 2 0.9 to < 2.5 < 3.8 to 2 2.1 G

(extremely l 2 6.5 2 2.9 2 2.5 < 2.1 stable) l . .

MGR-0009 Rev. 4

SNC PLANT E.I. HATCH I Pg. 17 of 22 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

OFFSITE EMERGENCY NOTIFICATIONS 73EP-EIP-073-0 15.1 ATTACHMENT 1 Att. Pg.

TITLE: EMERGENCY NOTIFICATION FORM INFORMATION 8 of 8 Item 15 Recommended Protective Actions:

This section requires the completed results of 73EP-EIP-054-0. This information can be provided by the TSC HP/Chem Supervisor and/or the Operations Supervisor or the EOF Ops Advisor and/or Dose Assessment Manager upon approval by the Emergency Director.

Check the appropriate block to indicate:

a. No recommended protective actions;

b. Enter distance and affected zones recommended for evacuating;

c. Enter distance and affected zones recommended for sheltering in place;

d. Enter other recommended protective actions as appropriate.

Item 16 Approved By:

Obtain concurrence and approval of emergency information from the Emergency Director prior to transmission of any message to offsite authorities. Any changes to form after the Emergency Director's approval will require his concurrence.

Time/Date:

The Emergency Director will enter the time (Eastern) and date the emergency notification form is approved.

The back of the notification form may be used for recording the roll call prior to transmitting the information and the acknowledgment after the information has been transmitted. Record the date and time (eastern) of notification of the State and each Local county authority.

MGR-0009 Rev. 4

SNC PLANT E.I. HATCH l Pg. 18 of 22 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

OFFSITE EMERGENCY NOTIFICATIONS 73EP-EIP-073-0 15.1 ATTACHMENT 2 Att. Pg.

TITLE: OPERATING INSTRUCTIONS FOR SOUTHERN LINC EQUIPMENT FOR ENN 1 of 1 NOTIFICATIONS OPERATING INSTRUCTIONS FOR SOUTHERN LINC EQUIPMENT FOR ENN NOTIFICATIONS

1. Press the 'Group" button on the So. Linc - ENN unit to ensure you are in the Group mode of operation. The unit will display "Wide Area" and '21: HEP ENN". This group includes all State and local agency locations with which emergency notification information is to be provided.

NOTE: A "time-out" timer limits the amount of time you can continuously talk to 2 minutes.

When the allotted time expires, you will hear a low-pitched cut-off tone. Releasing the "push to talk" button inside the handset will clear this condition and allow to reestablish communications.

2. Pick up the handset from the cradle and press and hold the 'push to talk" (PTT) button located inside the handset. Upon pressing the PTT button, you will hear a high, chirp-like tone that indicates you have permission to talk. Begin speaking after hearing the tone.

3. Release the PTT button when you have finished talking. This will allow you to hear incoming transmissions.

MGR-0009 Rev. 4

SNC PLANT E.I. HATCH l Pg. 19 of 22 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

OFFSITE EMERGENCY NOTIFICATIONS 73EP-EIP-073-0 15.1 ATTACHMENT 3 Att. Pg.

TITLE: MAJOR LOSS OF COMMUNICATION SYSTEMS 1 of 2 MAJOR LOSS OF COMMUNICATIONS SYSTEMS

1. Loss of ENS lNOTE: l The phone numbers to contact the NRC Operations Center (NRCOC) are posted on the ENS phones and in the Emergency Call List.

A loss of ENS is confirmed by the inability to contact the NRC Operations Center (NRCOC) on the ENS phone. This is considered reportable in accordance with REG-0024, Reporting Requirements. If this occurs, contact the NRCOC using a commercial telephone line to report

- that the ENS line is out of service.

IF you are unable to establish contact with the NRC using commercial telephone lines, THEN use other means of communications [i.e., the other ETS communication links in the TSC and EOF (see listing on page 10), Southern LINC, cell phones, etc.) to contact the NRCOC.

2. Loss of ENN NOTE: The phone numbers to contact the State and local authorities are listed in the Emergency Call List.

A loss of ENN is confirmed by the inability to contact ANY State or Local authority over the ENN system. If this occurs, contact the State/Local authorities using commercial telephone lines. .

Report that the ENN is out of service and we are confirming operability of our backup system.

This is not considered a reportable event.

IF, when using commercial telephone lines, you are unable to establish contact with the State and one of each Local authority point of contact, THEN this is considered reportable in accordance with REG-0024, Reporting Requirements.

MGR-0009 Rev. 4

SNC PLANT E.I. HATCH l Pg. 20 of 22 DOCUMENT TITLE: DOCUMENT NUMBER: RevNer No:

OFFSITE EMERGENCY NOTIFICATIONS l 73EP-EIP-073-0 15.1 ATTACHMENT 3 Att. Pg.

TITLE: MAJOR LOSS OF COMMUNICATION SYSTEMS 2 of 2

3. Loss of Health Physics Network (HPN)

NOTE: The phone numbers to use to contact the NRC Operations Center (NRCOC) are posted on the HPN phones and in the Emergency Call List.

A loss of HPN is confirmed by the inability to contact the NRC Operations Center (NRCOC) on the HPN phone, which is located in the TSC and EOF. This is considered reportable in accordance with REG-0024, Reporting Requirements. If this occurs, contact the NRCOC using a commercial telephone line to report that the HPN line is out of service.

IF you are unable to establish contact with the NRC using commercial telephone lines, THEN use other means of communications [i.e., the other ETS communication links in the TSC and EOF (see listing on page 10), Southern LINC, cell phones, etc.) to contact the NRCOC.

4. Loss of the Prompt Notification System (i.e.. NOAA Weather Radio System)

A complete loss of the broadcast ability of the prompt notification system is considered a major loss of Offsite Notification System capability and is reportable in accordance with REG-0024, Reporting Requirements.

5. Loss of Commercial Telephone Lines IF a loss of commercial telephone lines is reported and confirmed in by the inability to make phone calls offsite, operability of the following notification systems must be confirmed. This condition is considered reportable IF any of the following systems are also unavailable:

Ensure the operability of the ENS phone by contacting the NRC Operations Center using the ENS.

Ensure operability of the HPN phone by contacting the NRCOC using either HPN phone, located in the TSC and EOF.

Ensure the operability of the ENN by conducting a roll call of the State and Local county authorities.

Ensure operability of the Prompt Notification System (PNS) by turning on the NOAA weather radio, located in the Control Room:

Refer to the appropriate section of this attachment for actions to take if any of the above communication systems are not operating.

MGR-0009 Rev. 4

SNC PLANT E.I. HATCH l IP9. 21 of 22 DOCUMENT TITLE: DOCUMENT NUMBER: RevVer No:

OFFSITE EMERGENCY NOTIFICATIONS 73EP-EIP-073-0 15.1 ATTACHMENT 4 Att. Pg.

TITLE: *QUICK GUIDE" INSTRUCTIONS TO PERFORM ENN NOTIFICATION 1 of 1 The following placard may be utilized to provide quick guidance on steps necessary to perform ENN notifications. The information contained on this placard will be performed as directed by the body of this procedure.

"QUICK GUIDE" INSTRUCTIONS TO PERFORM ENN NOTIFICATION

01. OBTAIN APPROVED ENN FORM (TRN-0001) FROM THE EMERGENCY DIRECTOR. (step 7.2.2)

02. COMPLETE FOLLOWING IN LINE ITEMS 1-3 OF ENN FORM (TRN-0001):

(step 7.2.3)

MESSAGE NUMBER (FACILITY ABBREVIATION & SEQUENTIAL NUMBER)

REPORTED BY (NAME OF PERSON TRANSMITTING INFORMATION)

TRANSMITTAL TIME/DATE (OF VERBAL TRANSMISSION OF INFORMATION)

CONFIRMATION PHONE NUMBER

03. FAX ENN FORM TO STATE & LOCAL AUTHORITIES (speed dial button #1 labeled "ENN"). (step 7.2.4)

04. ALERT STATE & LOCAL AUTHORITIES ON THE ENN (SO. LINC RADIO).

(step 7.2.5) 115. VERBALLY TRANSMIT INFORMATION ON THE ENN FORM TO STATE AND LOCAL AUTHORITIES. (step 7.2.7)

06. REQUEST ACKNOWLEDGEMENT AND RECORD TIME OF RECEIPT OF VERBAL NOTIFICATION FROM STATE & LOCAL AUTHORITIES. (step 7.2.8)

07. FAX ENN FORM TO APPLICABLE COMPANY EMERGENCY FACILITY LOCATIONS (speed dial button #2 labeled "FACILITIES") (step 7.2.10)

Ref: 73EP-EIP-073-0 MGR-0009 Rev. 4

SNC PLANT E.I. HATCH l P. 22 of 22 DOCUMENT TITLE: DOCUMENT NUMBER: Rev/er No:

OFFSITE EMERGENCY NOTIFICATIONS 73EP-EIP-073-0 15.1 ATTACHMENT 5 Att. Pg.

TITLE: INSTRUCTIONS TO FAX THE ENN FORM (TRN-0001) I of 1 The following placard may be utilized to provide guidance on steps necessary to fax the ENN form (TRN-0001). The information contained on this placard will be performed as directed by the body of this procedure.

INSTRUCTIONS TO FAX THE ENN FORM

1. Place ENN form face down in the machine.

2. Press the speed dial Button #01 (labeled "ENN") on the right key pad of the machine.

3. Obtain form from machine and perform verbal notification.

4. After completing the verbal notification, place the ENN form face down in the machine and press the speed dial button #02 (labeled "Facilities") on the right key pad of the machine.

Ref: 73EP-EIP-073-0 MGR-0009 Rev. 4

NL-03-0939, Revised Epips, Including 73EP-EIP-004-0, Version 9.0, 73EP-EIP-005-0, Version 8.0, 73EP-EIP-018-0, Version 7.0, 73EP-EIP-023-0S, Version 0.4 & 73EP-EIP-073-0. Version 15.1

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3.4 Forms

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3.9 Forms

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decay constant of isotope: Xe-133 = 0.131/days, Kr-85

decay constant of isotope: Xe-133 = 0.131/days, Kr-85

decay constant of isotope: Xe-133 = 0.131/days, Kr-85m

3.0 REFERENCES

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NL-03-0939, Revised Epips, Including 73EP-EIP-004-0, Version 9.0, 73EP-EIP-005-0, Version 8.0, 73EP-EIP-018-0, Version 7.0, 73EP-EIP-023-0S, Version 0.4 & 73EP-EIP-073-0. Version 15.1

Text

Enclosures:

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

3.0 REFERENCES

3.4 Forms

3.0 REFERENCES

3.0 REFERENCES

3.9 Forms

3.0 REFERENCES

3.0 REFERENCES

decay constant of isotope: Xe-133 = 0.131/days, Kr-85

decay constant of isotope: Xe-133 = 0.131/days, Kr-85

decay constant of isotope: Xe-133 = 0.131/days, Kr-85m

3.0 REFERENCES

3.0 REFERENCES

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