ML021190201
| ML021190201 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/17/2002 |
| From: | Nazar M Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| Download: ML021190201 (15) | |
Text
Committed to Nuclea Exellence Nuclear Management Company, LLC Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East
- Welch MN 55089 April 17, 2002 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 Docket Nos. 50-306 License Nos. DPR-60 Prairie Island EOF Emergency Plan Implementing Procedures - F8 EOF Emergency Response Plan Implementing Procedures Furnished with this letter are the Prairie Island Nuclear Generating Plant EOF Emergency Plan Implementing Procedures F8. This revision includes the following procedures:
INDEXES: EOF Emergency Plant Implementing Procedures TOC REVISIONS:
F8-9 Event Termination or Transition to Recovery Rev 7 INSTRUCTIONS:
Please post changes in your copy of the Prairie Island Nuclear Generating Plant EOF Emergency Implementing Procedures. Procedures which have been superseded or deleted should be destroyed.
Please sign and return the acknowledgment of this update to Bruce Loesch, Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089.
If you have any questions, please contact Mel Agen at 651-388-1121 Extension 4240.
Mano K. Naz e
Site Vice Pre ident Prairie Island Nuclear Generating Plant
c: USNRC - Steve Orth, Region III (2 copies)
NRC Resident Inspector (w/o attachment)
J Silberg (w/o attachment)
M Agen (w/o attachment)
Records Management (Doc Control Copy) (w/o attachment)
NL File (w/o attachment)
Mfst Num: 2002 - 0292 Date 04/15/02 FROM : Bruce Loesch/Mary Gadient Loc Prairie Island TO : UNDERWOOD, BETTY J Copy Num: 515 Holder US NRC DOC CONTROL DESK SUBJECT : Revisions to CONTROLLED DOCUMENTS Procedure # Rev Title Revisions:
F8-9 7 EVENT TERMINATION OR TRANSITION TO RECOVER UPDATING INSTRUCTIONS Place this material in your Prairie Island Controlled Manual or File. Remove revised or cancelled material and recycle it. Sign and date this letter in the space provided below within ten working days and return to Bruce Loesch or Mary Gadient, Prairie Island Nuclear Plant, 1717 Wakonade Drive E.,
Welch, MN 55089.
Contact Bruce Loesch (ext 4664) or Mary Gadient (ext 4478) if you have any questions.
Received the material stated above and complied with the updating instructions Date
I PRAIRIE ISLAND NUCLEAR
Title:
GENERATING PLANT EOF Emerg Plan Implementing Procedures TOC Effective Date : 04/15/02 jApproved By: SLCdI hi
( JBPSSupt//lj Document # Title Rev F8-1 EMERGENCY OPERATIONS FACILITY ORGANIZATION 6 F8-2 RESPONSIBILITIES DURING AN ALERT, SITE AREA OR 7 GENERAL EMERGENCY IN THE EOF F8-3 ACTIVATION & OPERATION OF THE EOF 5 F8-4 EMERGENCY SUPPORT & LOGISTICS 4 F8-5 OFFSITE DOSE ASSESSMENT & PROTECTIVE ACTION 7 RECOMMENDATIONS F8-6 RADIOLOGICAL MONITORING & CONTROL AT THE EOF 6 F8-8 OFFSITE AGENCY LIAISON ACTIVITIES 4 F8-9 EVENT TERMINATION OR TRANSITION TO RECOVERY 7 F8-10 RECORD KEEPING IN THE EOF 2 F8-11 TRANSFER TO THE BACKUP EOF 3 F8-12 EMERGENCY REMP 3 Page 1 of 1
PRAIRIE ISLAND NUCLEAR POWER PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:
EVENT TERMINATION OR F TRANSITION TO RECOVERY RE:9 REV: 7 REFERENCE USE
"* Proceduresegments may be performed from memory.
"* Use the procedure to verify segments are complete.
"* Mark off steps within segment before continuing.
"* Procedureshould be availableat the work location.
O.C. REVIEW DATE: OWNER: EFFECTIVE DATE 0CIcL So- M. Werner (/f5 - O)ý Page 1 of 11
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:
EVENT TERMINATION OR F8-9 TRANSITION TO RECOVERY 1.0 PURPOSE The purpose of this procedure is to:
1.1 Provide guidelines for termination of the emergency response phase and transition to the Recovery phase.
1.2 Provide guidelines for transfer of control from the emergency organization to Recovery Organization.
2.0 APPLICABILITY This procedure applies to the Emergency Manager, Recovery Manager, Technical Support Supervisor, Radiation Protection Support Supervisor and EOF Coordinator.
3.0 PRECAUTIONS NONE 4.0 RESPONSIBILITIES 4.1 The Emergency Manager is responsible for the implementation and conduct of this procedure and the decision to terminate the event or enter the Recovery phase.
4.2 The Emergency Director is responsible for assisting the Emergency Manager in the decision to terminate the event or enter the Recovery phase.
4.3 The Recovery Manager (named the Event Manager in 5AWl 1.13.0) is responsible for overall management of the recovery activities necessary to return the plant to a normal operational or shutdown status.
4.4 The Plant Manager is responsible for coordinating the onsite recovery activities and assisting the Recovery Manager.
4.5 The EOF Technical Support Supervisor is responsible for developing short term and long term recovery actions necessary to return the plant to normal or shutdown status.
4.6 The Radiation Protection Support Supervisor is responsible for developing short term and long term offsite radiological support activities for the Recovery phase.
4.7 The EOF Coordinator is responsible for assisting the Emergency Manager in formulating recovery actions and ensuring emergency documents are collected and properly processed.
Page 2 of 11
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:
EVENT TERMINATION OR F8-9 F8 TRANSITION TO RECOVERY REV: 7 5.0 DISCUSSION 5.1 Recovery In general, an Unusual Event or Alert may be terminated without transition to a Recovery phase. A Site Area Emergency or General Emergency will probably require a planned transition to a Recovery phase and the establishment of a Recovery Organization under the direction of the Recovery Manager. In either case, termination or transition to a recovery phase, a review of 5AWI 1.13.0, "Plant Event Investigation and Recovery," should be completed. A determination to implement 5AWI 1.13.0 should involve the Plant Manager and Emergency Director.
Termination of an Alert classification includes the dismissal of the site Emergency Response Organization. Necessary in-plant or on-site follow-up activities should be coordinated and managed by the normal plant site organization. Post-Alert conditions may require the establishment of a Recovery Organization. The Emergency Director and Emergency Manager should make this determination based on the extent of damage or other considerations.
If a Site Area Emergency does not require significant repairs or analysis beyond the capabilities of the normal plant site organization, the event may be terminated without transition to a Recovery phase.
5.2 NRC Post-Accident Assessment It is expected that the NRC will, as a minimum, send an Augmented Inspection Team (AIT) to the plant to perform a thorough investigation of the incident. As a result, the AIT will request the following:
5.2.1 Any failed equipment not necessary for safe shutdown or operation of the plant will be quarantined. No work on failed equipment should be performed unless absolutely necessary for plant safety. The NRC will want to perform failure analysis on the failed equipment.
5.2.2 No written or electronic records be destroyed or erased.
5.2.3 Schedules be adjusted or additional resources be made available for NRC interviews with plant personnel involved with the incident. A court reporter may be present to transcribe the interviews.
5.2.4 Office space (or trailer space) be made available for the NRC AIT.
Page 3 of 11
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:
EVENT TERMINATION OR F8-9 F8 TRANSITION TO RECOVERY REV: 7 6.0 PREREQUISITES The Emergency Manager has assumed authority for reclassifications from the Emergency Director and:
6.1 An Alert has been declared and conditions indicate that plans for event termination may begin, or 6.2 A Site Area Emergency or General Emergency has been declared and conditions indicate the immediate emergency phase is over and transition plans to the Recovery phase may begin.
7.0 PROCEDURE 7.1 Termination from an Alert Condition 7.1.1 As plant conditions stabilize during an Alert, consider terminating the event classification subject to the conditions below.
7.1.2 Assess plant and environmental conditions. PINGP 1102 or PINGP 1103, Shutdown Safety Assessment, may be used as an assessment guide.
7.1.3 The emergency classification may be terminated once the following criteria are met:
A. The plant is in stable condition with at least one fission product barrier intact, and B. Radioactive gaseous and liquid effluent are being controlled within the following limits:
- 1. Gaseous effluent release rates (or resulting dose rates) are within plant limits as defined in Section 3.1 of H4, ODOM.
- 2. Liquid effluent release rates (or resulting concentrations) are within the plant limits as defined in Table II, Column 2 of H4, ODOM Table 4.3, Old 100FR20 Appendix B (April 1992).
and C. The potential for future degradation of plant conditions is small (PINGP 1102 or PINGP 1103, Shutdown Safety Assessment, may be used as an assessment guide).
Page 4 of 11
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:
EVENT TERMINATION OR F TRANSITION TO RECOVERY 7 S 7.1.4 When the criteria for termination are met, terminate the Alert.
7.1.5 Upon event termination, ensure the Emergency Director is advised of the termination.
7.1.6 Review and approve the Notification Report Form (PINGP 577) and designate the Offsite Emergency Communicator to complete the notifications of state, local and site personnel in accordance with PINGP 1054, EOF Offsite Notification Call List For Reclassifications.
7.1.7 Initiate outage planning if equipment and plant systems are significantly damaged and extended plant shutdown is required. Refer to 5AWI 1.13.0, "Plant Event Investigation and Recovery," before any outage planning.
7.1.8 Direct the EOF Coordinator to collect all EOF emergency checklists, documentation and records generated during the event.
7.1.9 Provide the necessary resources to support the requirements of the NRC post-event investigation team.
7.1.10 Develop and submit NRC follow-up reports through normal plant administrative procedures.
7.2 Termination from Site Area or General Emergency with Transition to the Recovery Phase 7.2.1 WHEN the event has stabilized and plant conditions warrant possible transition to the Recovery phase, THEN assess plant and environmental conditions. PINGP 1102 and PINGP 1103, Shutdown Safety Assessment, may be used with other assessment tools to assess the condition of the plant.
7.2.2 Direct the Technical Support Supervisor and the Radiation Protection Support Supervisor to assess conditions and identify recovery actions necessary to return the plant to a normal operational or shutdown status.
The Recovery Action Item Form, PINGP 1017 should be used to identify recovery action items.
7.2.3 Direct the EOF Coordinator to compile all identified recovery actions on the Recovery Action Item Form, PINGP 1017. The list should identify short-term corrective actions (to be completed within hours or days) and long-term actions which may require an extended plant outage (i.e., weeks or months).
7.2.4 Direct the Recovery Manager to begin formulating a Recovery Organization.
Page 5 of 11
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:
EVENT TERMINATION OR F8-9 F8 TRANSITION SREV: TO RECOVERY 7 7.2.5 When formulating a Recovery Organization, the Recovery Manager should consider the following:
A. Implementation of the Recovery Organization should be established using 5AWI 1.13.0, "Plant Event Investigation and Recovery."
B. There may be a need for offsite contract organizations to support recovery.
If the Site Area Emergency event does not require significant repairs or analysis beyond the capabilities of the normal plant site organization and the conditions of 7.1.3A, 7.1.3B, &
NOTE: 7.1.3C are met, then the Site Area Emergency may be terminated without a transition to Recovery. However, review and implementation of 5AWI 1.13.0 should be completed as appropriate.
7.2.6 Continue to assess plant and environmental conditions and when all of the following criteria are met, transition to the Recovery phase should be considered:
A. The plant is in a stable condition with at least one fission product barrier intact, and B. Radioactive gaseous and liquid effluents are being controlled within the following limits:
- 1. Gaseous effluent release rates (or resulting dose rates) are within plant limits as defined in Section 3.1 of H4, ODCM.
- 2. Liquid effluent release rates (or resulting concentrations) are within the plant limits as defined in Table II,Column 2 of H4, ODCM, Table 4.3 Old 10CFR20 Appendix B (April 1992),
and C. If Severe Accident Management (SAM) was implemented, the SAM termination criteria per the SAMG Diagnostic Flow Chart are met, and D. The potential for future degradation of plant conditions is small, and E. NRC Headquarters (or the Director of Site Operations of the on-site response team) concurs with the transition to Recovery.
Page 6 of 11
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:
EVENT TERMINATION OR F8-9 TRANSITION SREV:
TO RECOVERY F8-97 7.2.7 When the criteria for transition to Recovery are met, contact the Emergency Director and discuss the conditions.
7.2.8 Ifthe Emergency Director concurs that conditions for transition to Recovery are met, discuss the proposed transition with the NRC.
Ifthe NRC Incident Response Team has not been mobilized or has not arrived, the proposal to enter the Recovery phase NOTE: should be discussed with NRC Headquarters. If the NRC Response Team is onsite, the Emergency Manager and Emergency Director should meet with the Director of Site Operations to discuss the transition to Recovery.
7.2.9 Ifthe NRC concurs that transition to Recovery is appropriate, obtain the compiled list of short and long term corrective actions on the Recovery Action Item Form PINGP 1017. Review the list with the Technical Support Supervisor, RPSS, and Recovery Manager to ensure all items have been addressed.
7.2.10 Upon review completion, schedule and conduct a meeting with the Emergency Director and Recovery Manager. The meeting should include:
A. Review of activities in progress, long term problems and established interfaces.
B. Review of the identified recovery actions.
C. Identification of additional resources or organizations needed to support Recovery.
D. Establishment of a Recovery Organization.
E. Establish a method and turnover rate of existing Emergency Organization to the Recovery Organization.
7.2.11 The transition to Recovery meeting should conclude with the Emergency Manager authorizing the termination of the emergency event, authorizing Recovery and designating the Recovery Manager in charge of the plant's recovery activities.
7.2.12 Advise the TSC when the transition to Recovery is made.
Page 7 of 11
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:
-EVENT TERMINATION OR F8-9 STRANSITION TO RECOVERY REV: 7 7.2.13 Review and approve the Notification Report Form (PINGP 577) and designate the Offsite Emergency Communicator to complete the notifications of state, local and site personnel in accordance with PING P 1054, EOF Offsite Notification Call List For Reclassification.
7.2.14 Direct the EOF Coordinator to collect EOF emergency checklists, documentation and records generated during the event.
7.2.15 Provide the necessary resources to support the requirements of the NRC post-event investigative team.
7.2.16 The development and submittal of follow-up reports to the NRC should be conducted through normal plant administrative procedures.
Page 8 of 11
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:
EVENT TERMINATION OR F8-9 F8 TRANSITION TO RECOVERY REV: 7 Figure 1 Example of Recovery Action Item Form EXAMPLE ONLY USE CURRENT REVISION PINGP 1017, Rev. 4 Page 1 of 3 Retention: Life RECOVERY ACTION ITEM FORM Short Term = Hours or Days Long Term = Weeks or Months PERFORM ASSESSMENTS IN THE FOLLOWING AREAS AND IDENTIFY POTENTIAL SHORT TERM AND LONG TERM RECOVERY ACTION ITEMS:
A. Current operational status of plant systems and equipment involved in the emergency. Include reviews of "Operator Workarounds" and current "in progress" Work Orders to evaluate current plant configuration.
B. Current Operational status of the unaffected unit and its effect on the affected unit.
C. Identification of all systems, components, or equipment damaged or made inoperable during the event.
D. Estimate of necessary repairs, parts and tools to restore all affected systems and equipment back to a fully operational state.
E. Identification of special tools or equipment that may be required during the restoration period.
F. Estimate of additional personnel resources that may be required during the restoration period.
G. Identification of applicable plant surveillance tests and procedures required for post maintenance testing.
H. Identification of applicable system operability tests and procedures to restore plant systems to normal operational or shutdown configuration.
I. Estimate of liquid and solid radioactive waste generated during the event and recommendations on management and disposal.
J. Identification of special radiological considerations for personnel entry into affected areas with elevated dose rates or contamination levels (i.e.; temporary shielding engineering evaluations, robotics, etc.)
K. Estimate of the decontamination and monitoring activities necessary to restore affected areas inside and outside the plant site to pre-accident levels.
L. Identification of continued offsite radiological sampling and potential assistance to state or local agencies in the area of sampling, monitoring, and decontamination.
M. Following a containment LOCA, sample and adjust (if necessary) the pH of the primary coolant/recirculation loop within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the accident. Acceptable range is between 7.0 and 10.5 to minimize the potential for stress corrosion cracking of the stainless steel piping and components.
1017 Recovery Action Item Form.DOT Page 9 of 11
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES RNUMBER:
EVENT TERMINATION OR F8-9 F8 TRANSITION TO RECOVERY REV: 7 Figure 1 Example of Recovery Action Item Form PINGP 1017, Rev. 4 Page 2 of 3 USE CURRENT REVISION EXAMPLE ONLY RECOVERY ACTION ITEM FORM SHORT-TERM RECOVERY ACTIONS (Hours or Days)
PREPARED BY _ TSC _ EOF (Check one)
ITEM # ACTION ITEM DESCRIPTION COMMENTS Reviewed by: Date:
Emergency Director/Emergency Manager Page 10 of 11
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EOF EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER:
EVENT TERMINATION OR F8-9 F8 TRANSITION TO RECOVERY REV Figure 1 Example of Recovery Action Item Form USE CURRENT REVISION]
EXAMPLE ONLY I PINGP 1017, Rev. 4 Page 3 of 3 RECOVERY ACTION ITEM FORM LONG-TERM RECOVERY ACTIONS (Weeks or Months)
PREPARED BY _ TSC _ EOF (Check one)
ITEM # ACTION ITEM DESCRIPTION COMMENTS Reviewed by: Date:
Emergency Director/Emergency Manager Page 11 of 11