ML032250554
| ML032250554 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/31/2003 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EP-PS-307, Rev 8 | |
| Download: ML032250554 (13) | |
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I Jul. 31, 2003 Page 1 of 1 MANUAL HARD COPY DISTRI8UTION DOCUMENT TRANSMITTAL 2003-34483 USER INFORMATION:
Name:GERLACH*ROSE M EMPL#:28401 CA#:0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:
TO: GERLACH*ROSE M 07/31/2003 LOCATION: DOCUMENT CONTROL DESK I.-.
FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE:HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:
307 - 307 - ENGINEERING SUPPORT MANAGER: EMERGENCY PLAN-POSITION SPECIFIC PROCEDURE REMOVE MANUAL TABLE OF CONTENTS DATE: 06/26/2003 1%ADD MANUAL TABLE OF CONTENTS DATE: 07/30/2003 CATEGORY: PROCEDURES TYPE: EP ID: EP-PS-307 ADD: PCAF 2003-1554 REV: N/A UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
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PROCEDURE CHANGE PROCESS FORM
- 1. PCAF NO. - _S 12. PAGE 1 OF 3. PROC. NO. EP-PS-307 REV. 8
- 4. FORMSREVISED -A R 12 - R _ R _, - R_ - R-, - R_
- 5. PROCEDURE TITLE Engineering Support Supervisor.Emergency Plan Position Specific Instruction
- 6. REQUESTED CHANGE PERIODIC REVIEW 3 NO -J YES INCORPORATE PCAFS 0 NO Q YES# -
REVISION [] PCAF Z DELETION [ (CHECK-ONE ONLY)
- . -e ps
- 7.
SUMMARY
OF I REASON FOR CHANGE : . :-
Revised Tab A to add additional guidance for communication with
- Added Tab 5 to provide list of anticipated questions - i /.
41 IT Crnflnued n-
. -,- (Refer to Section 6.1.4)
PORC REVIEW REQ'D? 9. PORCMTG_
BLOCKS 11 THRU 16AREONPAG OFFRM
- 17. T.C. Dalplaz I/ 3227- -I: 07/01/2003 18. COMMUNICATION OF CHANGE REQUIRED?
PREPARER
-(Print or Twpe) r -wN;
~
2 i
. DATE I
LI NO -I YES (TYPE) E Mail Notification
-. SIGNATURE ATrESTS THAT RESPONSIBLE SUPERVISOR HAS
- CONDUCTED QADR AND TECHNICAL REVIEW UNLESS OTHERWISE 71/P/f3 -DOCUMENTED IN BLOCK 16 OR ATTACHED REVIEW FORMS.
7-/.&
'f'CROSS DISCIPLINE REVIEW OF REQUIRED) HAS BEEN COMPLETED EFATE v BY SIGNATURE IN BLOCK 16 OR ATTACHED REVIEW FORMS.
l71 I3
-DATE :
I
- 21. R P ENTER N/A IF FUM HAS APPROVAL AUTHORITY INITIALS -
I§ m7 JURl29 01 .J Um28.2L FORM NDAP-QA-0002-8, Rev. 8, Page 1 of 2 (Electronic Form)
DOUETRCNTOL SERVICES S¢ES
I-PROCEDURE CHANGE PROCESS FORM
- 1. PCAF NO. ;2-/*5/ 12. PAGE 2 OF , 3. PROC. NO. EP-PS-307 REV. 8
- 11. This question documents the outcome of the 50.59 and 72.48 Review required by NDAP-QA-0726. Either 1a, b, c or d must be checked "YES" and the appropriate form attached or referenced.
- a. This change is an Administrative Correction for which 50.59 and 72.48 are not [ YES NIA applicable.
- b. This change is a change to any surveillance, maintenance or administrative 0 YES a N/A procedure for which 50.59 and 72.48 are not applicable.
- c. This change is bounded by a 50.59172.48 Screen/Evaluation, therefore, no new a YES s NIA 50.59/72.48 Evaluation is required.
Screen/Evaluation No. ___
- d. 50.59 and/or 72.48 are applicable to this change and a 50.59172.48 [ YES 3 NIA Screen/Evaluation Is attached.
- 12. This change is consistent with the FSAR or an FSAR change Is required. YES Change Request No. : __
- 13. Should this change be reviewed for potential effects on Training Needs or Material? F] YES 0 NO If YES, enter an Action Item @ NIMS/Action/Gen Work Mech/PICN
- 14. Is a Surveillance Procedure Review Checklist required Oer NDAP-QA-0722? a YES 3 NO
- 15. IsaSpecial,InfrequentorComplexTest/EvolutionAnalysisFormrequiredper a YES NO NDAP-QA-0320? (SICT/E form does not need to be attached.)
- 16. Reviews may be documented below orby attaching Document Review Forms NDAP-QA-0101-1.
REVIEWED BY WITH DATE REVIEW NO COMMENTS QADR __ _
TECHNICAL REVIEW _ _-_ _
REACTOR ENGINEERINGINUCLEAR FUELS * : D X _
IST _ __CC_ __X OPERATIONS X_ __ __ __
NUCLEAR SYSTEMS ENGINEERING _ _ _ _
NUCLEAR MODIFICATIONS MAINTENANCE _ _
HEALTH PHYSICS : X_ _
NUCLEAR TECHNOLOGY =___i CHEMISTRY ___ __:__
OTHER 10 CFR 50.54Q EX
- Required for changes that affect, or have potential for affecting core reactivity, nuclear fuel, core power level indication or impact the thermal power heat balance. (58)
Required for changes to Section Xi Inservice Test Acceptance Criteria.
FORM NDAP-QA-0002-8, Rev. 8, Page 2 of 2 (Electronic Form)
rGAA X -
PAGE-3-OF .L2 EP-PS-307 Revision 8 Page 2 of 3 ENGINEERING SUPPORT SUPERVISOR Emergency Plan Position Specific Procedure WHEN: When the EOF is activated HOW NOTIFIED: Paged/Telenotifications System WHERE TO REPORT: Emergency Operations Facility REPORT TO: Recovery Manager OVERALL DUTY:
Act as a technical resource for plant data -and information, performing assessments to support dose projections, protective action recommendations and emergency c1assifications.
MAJOR TASKS: TAB: REVISION:
Obtain information on plant status to support TABA '-I I. Q_
dose projections, protective action -,I-recommendations, emergency classifications. M.
and information dissemination.
Support dose assessment calculations, TAB B 5 communicating results to the Dose Assessment Staff.
Establish and maintain contact with the TAB C S Department of Environmental Protection/Bureau of Radiation Protection (Technical), Nuclear Regulatory Commission, and the Media Operations Center.
- A P4PAGE4K~~~~~~~~~~~~~~~~~~-OF.
GF 2 L ~~~~~~~~~~~~~~~~~Revision8 EP-PS-307 Page 3 of 3 SUPPORTiNG INFORMATION: TAB:
Emergency Organization TAB I NERO Technical Support Overview TAB 2 Emergency Classifications TAB 3 Public Protective Action Recommendation Guide TAB 4
REFERENCES:
As l( U 3 AA-rO r & ST S P/sr:I)6S NRC RTM 92, Nuclear Regulatory Commission Response Team Manual SSES Emergency Plan NUREG 0654, Planning Standards and Evaluation Criteria NUREG 0731, -Guidelines for Utility Management Structure and Technical Resources, Sept. 1980 NUREG 0696, Functional Criteria for Emergency Response Facilities NEDO 22215, Procedure for the Determination of the Extent of Core Damage Under Accident Conditions
TAB A LAFr- EP-PS-307-A Revision 1-t ) 2-PAGE 'S) F./? Page 1 of 5 MAJOR TASK:
Obtain information on plant status to support dose projections, protective action recommendations, event classifications, and information dissemination.
SPECIFIC TASK: HOW:
- 1. Log in upon arrival. 1a. Sign Ingress/Egress Log located at the entrance into the EOF.
l b. Clip-on the position specific name badge.
1c. Sign-in on board in conference area if you are the initial-responder.
- 2. Notify the Recovery Manager of your NOTE:
arrival. If the Recovery Manager Is delayed in arriving at the EOF, prepare the facility for turnover, (reference EP-PS-200, Recovery Manager Emergency-Plan-Position Specific Instruction), but do not accept turnover until his arrival.
- 3. Provide Engineering Support to the 3a. Only the Engineering Support Supervisor EOF Staff. is required for EOF activation.
3b. Obtain required engineering information from the TSC until arrival of additional engineering staff in GO/EOF.
3c. The following personnel are desired within 90 minutes:
(1) Systems Lead Engineer (EOF AND GO)
(2) Fuels Lead Engineer (EOF AND GO)
(3) Mechanical Engineer (EOF)
(4) Electrical Engineer (EOF)
PACEF.- : f TAB A P.A C'P Ed 0 F. Za.r, EP-PS-307-A Revision I- / 2J-Page 2 of 5 SPECIFIC TASK: HOW; 3d. Cal the General Office if you are the Initial responder. (Conference bridge telephone line may be used.)
Se. If additional support is required, request the EOF Support Supervisor or NEP Duty Planner to obtain needed disciplines.
- 4. Determine readiness of Engineering 4a. Verify engineering equipment Is Support Staff to support EOF operational (phones, PICSY terminals, functions for this event network terminals, Fax machine, etc.).
4b. Brief Engineering Support Staff as time permits. (Staff can be briefed after EOF activation.)
- 5. Obtain sufficient knowledge of event 5a. Review data posted In the Command to allow assumption of duties. - and Control, Site Support,: and Engineering'Support areas.
5b. Obtain event information from Recovery Mgr., TSC, or other accurate source.
Ensure knowledge of:
(1) Affected Unit (2) Emergency Classification-(3) Any Protective Action Recommendations (4) Source term size (5) Release flowpath (6) Review and understand status of unaffected unit.
27 N;AG- ______ OF TABA EP-PS-307-A fPAGE.4LOFb.: Revision :K 1-Page 3 of 5 SPECIFIC TASK: HOW:
- 6. Perform turnover of notification of f 6a. Contact the TSC Tech Support DEP/BRP Technical from the TSC Coordinator and obtain time that next Engineering Staff to the EOF. (This - notification is due. Accept responsibility
-can be done at any time but is for next notification of DEPIBRP REQUIRED at first notification after Technical. (REQUIRED at first TSCIEOF turnover). notification after TSCIEOF turnover).
6b.- DEP/BRP communications are due hourly.
6c. Transmit information from the ENR form.
6d Review anticipated questions list in anticipation of briefing HELP ANTICIPATED QUESTIONS LIST SEE TAB 5
- 7. Maintain ongoing awareness of plant 7a. Ensure an ongoing awareness.of at least status. the following:
(1) Status of Reactivity control (2) Decay heat removal (3) Backup heat removal capability (4) Integrity of fuel cladding, Rx vessel, primary containment, and secondary containment
_(5) Hydrogen generation (6) Status of rad release
- 8. Review plant status with the Recovery sa. Assign personnel to trend the following Manager. Assist in classification and data, immediately advise you of :
reclassification of the event, and in significant changes:
detenrining the need for Protective
- Action Recommendations. (1) The release path:
- a. Barriers breached
- b. Barriers threatened, (no decay
-heat removal, over pressurization, etc.)
- c. Mitigation in progress (2) Source term
- a. Type and amount of fuel
-damage Mitigation hi progress (3) Present classification and bases
- a. Potential for upgrade
t
~~AI-TAB A PAGLZ F,~-IUSwft EP-PS-307-A Revision W I 1-Page 4 of 5 SPECIFIC TASK: HOW:
- 9. Establish/maintain an Engineering 9a. Assign a staff member to maintain a list Support Priorites List. of Engineering Support Pnorities utilizing the white boards or easels in
- the Engineering Support Office, including:
(1) initial time (2) Xdisposition (open/closed)
(3) time of closure
- 10. Establishlmaintainalistof 10a. Ensure tracking ofconcurrent EAL's at current/concurrent EALs. all emergency levels.
10b. Provide information to Recovery Manager for downgrade discussions.
- 11. Update Recovery Manager as new 1a. Brief Engineering Support Staff information becomes available. personnel to:; - -
(1) Advise you immediately if they become aware of Information that could change the Emergency Classification or PAR.
(2) Advise you Immediately if you provide information believed to
-be incomplete or inaccurate in a briefing.
(3) Use three-part communications during exchanges of critical information.
I
- 3 /
'UA-TAB A PAGEO j EP-PS-307-A Revision 1W A Page 5 of 5 SPECIFIC TASK: HOW:
- 12. Succeed the Recovery Manager as 12a. If the Recovery Manager becomes required. - - - ; unable to perform his functions during I the emergency and another Recovery Manager is not present, assume the duties of Recovery Manager.
12b. Ensure a replacement Recovery Manager is immediately called to the
=- - EOF.
PAG3EIL-OFA ...
Tab 5 EP-PS-307-5 ANTICIPATED QUESTION LIST The following questions are Intended to provide an overview of the event that precipitated entry into the SSES EMERGENCY PLAN. They will be used by managers In the emergency response organization to better understand the situation and answer questions posed by offsite agencies and regulators.
QUESTION #1: (TECHNICAL SUPPORT COORDINATOR/ENGINEERING SUPPORT SUPERVISOR) X -
What is the status of all three fission product boundaries? Indicate what data supports each determination.
- b. Reactor coolant pressure boundary -
- c. Primary containment QUESTION #2: (TECHNICAL SUPPORT COORDINATORIENGINEERING SUPPORT SUPERVISOR)
For intact barriers, what threats exist to their continued integrity? For degraded barriers, what is the potential for further degradation? Indicate what data supports each determination.
- b. Reactor coolant pressure boundary
- c. Primary containment EP-AD-OO-404, Revision 5, Page 1 of 3
rCA!-£ PAGF //-LOF/2. -Tab 5 EP-PS-307-5 ANTICIPATED QUESTION LIST QUESTION #3: (TECHNICAL SUPPORT COORDINATORIENGINEERING SUPPORT SUPERVISOR)
- a. How is the core being cooled?
- b. How do you know that the cooling systemn(s) in service are adequately removing heat from the core?
- c. What backup cooling systems are available?
QUESTION #4: (TECHNICAL SUPPORT COORDINATOR/ENGINEERING SUPPORT SUPERVISOR)
- a. How do you know that the core is in a coolable configuration?
- b. What is the current estimate of core damage?
- c. What is the prognosis for further degradation?
QUESTION #5: (TECH SUPPORT COORDINATOR)
- a. How do you correlate the in-plant radiological data with the in-plant system parameter data to support your understanding of the situation?
- b. What is the status of off-site radiological releases?
EP-AD-000-404, Revision 5, Page 2 of 3
/CAk t PAG 0 Tab 5 EP-PS-307-5 ANTICIPATED QUESTION LIST
- c. If releases are occurring:
- 1) What is the release path?
- 2) Is the release monitored?
- 3) Is the release filtered?
- 4) What is the potential for increased release levels?. When?
- 5) What is the potential for termination of the release? When?
- c. If releases are not currently occurring:
- 1) What are the potentially releasable source terms?
- 2) What is the status of SBGTS?
QUESTION #6: (DOSE ASSESSMENT SUPERVISOR/RADIATION PROTECTION COORDINATOR)
- a. If releases are occurring, what are the off-site release consequences?
- b. What is the potential for the release to change and what would be the off-site consequences of the postulated release?
EP-AD-000-404, Revision 5, Page 3 of 3