ML022820139
| ML022820139 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 09/27/2002 |
| From: | Forbes J Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| Download: ML022820139 (17) | |
Text
NMC)
Committed to Nuclear Excellence Monticello Nuclear Generating Plant Operated by Nuclear Management Company, LLC September 27, 2002 10 CFR 50, Appendix E Section V US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Emeraency Plan Imolementinq Procedures Furnished with this letter is a revision to the Monticello Nuclear Generating Plant Emergency Plan Implementing Procedures. The following procedures are revised:
Procedure A.2-805 Procedure Title Technical Support in the EOF Revision 5
Please post changes in your copy of the Monticello Nuclear Generating Plant Emergency Plan Implementing Procedures. Superseded procedures should be destroyed. This revision does not reduce the effectiveness of the Monticello Nuclear Generating Plant Emergency Plan.
Please contact Douglas A. Neve, Licensing Manager, at 763-295-1353 if you require further Jeffrey S. Forbes Site Vice President Monticello Nuclear Generating Plant c:
Regional Administrator - III, NRC (wI two copies of enclosure)
NRR Project Manager, NRC (w/o enclosure)
Resident Inspector, NRC (w/o enclosure, EPIP dist. by Monticello Document Control)
Minnesota Dept. of Commerce (w/o enclosure)
J \\L!CENSE*NRC Misc CorrespondenceE-rnergency Plan\\EPIPR09-29-02 EPIP letter A2-805 doc 2807 West County Road 75
- Monticello, Minnesota 55362-9637 Telephone: 763.295.5151
- Fax: 763.295.1454
-A045
MONTICELLO NUCLEAR GENERATING PLANT A.2-805 TITLE:
TECHNICAL SUPPORT IN THE EOF Revision 5 I*
Page 1 of 16 EMERGENCY PLAN IMPLEMENTING PROCEDURE -TABLE OF CONTENTS SECTION Pi PURPOSE.............-
APPLICABILITY ORGANIZATION AND RESPONSIBILITIES...........................
DISCUSSION........................
PRECAUTIONS..................
INSTRUCTIONS.......................................
6.1 Initial Activation and Staffing 6.2 Technical Support Supervisor Recordkeeping..................
6.3 Technical Support Group Shift Scheduling.......................
6.4 EOF Status Updates 6.5 General Instructions....................
I.......................
6.6 Operational Assessment......................................
6.7 Engineering Assessment 6.8 Technical Support Supervisor Shift Turnover.....................
6.9 Event Termination or Recovery................
6.10 SPDS/ERIS Vax Instructions.....
,GE 2
2 2
3 3
3 3
6 7
8 9
11 13 14 15 16 Prepared By:,
Reviewed By:.
OC Review Req'g:" YES 0C Meeting Number:
2 Date :,ji Approved By:
Date:
_,.%FIRAhDfINISTRATIVEVS y
This revision incorporates Volume F Memos:_______
3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:
D5Z -
2.3 11 1.0 2.0 3.0 4.0 5.0 6.0 I/mab Resp Supv:
EP I Assoc Ref. A.2 -
lA: N IFre'* l,,rl
,. I ARMS:
A.2-805 IDoc Type: 1060 1 Admin Initials:
U Date: -i I q I f
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MONTICELLO NUCLEAR GENERATING PLANT:
'A.2-805 TITLE:
.TECHNICAL SUPPORT IN THE EOF, Revision 5 Page 2 of 16 1.0 PURPOSE -
- 1.
This procedure provides instructions and guidance for the activities of the Technical Support Group under the direction of the, Technical Suppo4t Supervisor in the Emergency Operations Facility (EOF) diiring an emergency. '
2.0 APPLICABILITY' 2.1 An Alert has been declared at the Monticello plant and the EOF has been activated and staffed.
3.0 ORGANIZATION ANDIRESPONSIBILITIES 3.1 The Technical Supogrt Supervisor is responsible for-3.1.1 Direction and coordination of EOF-'Technical Support group activities inclbiding trending, accident assessnrient and engineering/operational support of the EOF.,
3.1.2 Coordinate establishing 24,hour ERO shift schedule for the EOF "Technical Support group if the event is protracted.
3.1.3 Implementation-of this procedure.
3.2 The EOF.Technical Support Staff is responsible for:
3.2.1 Proactive evaluation of the overall event including forecasting trends, anticipating adverse, trends,, and making recommendations to the Emergency Manager, (aPd TSC Engineering staff) regarding avoiding or mitigating accident consequences.
3.2.2 Advising the EmergencyManager on the engineering and operational aspects of the event.
3.2.3 Trending of critical plant parameters related to Contain'ment integrity and source term and advising the Radiation Protection Support Supervisor (Rad Prot Sup Supv) on matters related to actual or potential release duration and core damage.'
3.2.4 Support the Technical Support-Center with technidal information
"-* including replacement equipment and component specifications,'
off-site vendor support and logistics.
S3.3,The EOF-TSC-CR Technical Communicator is responsible for:
3.3.1 Manning and maintaining a communications link between the Control I
.. 'Room, Technical Support Center, OSC, and.EOF for the purpose of I
"obtaining technical and oj~erational'information.
3.3.2 Maintaining the Operational. Status Board in the EOF Command Center, '.
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MONTICELLO NUCLEAR GENERATING PLANT -
A.2-805 TITLE:
TECHNICAL SUPPORT INTHE E Revision 5 Page 3 of 16 3.4 The EOF-JPIC Technical Communicator is responsible for:
3.4.1
'-Manning :and "mainrtaining a com munications link betweenthe Joint Public InformationpCenter and EOF fortheFPurpose'of keeping JPIC personnel informed.
4.0 DISCUSSION
'This procedure provides instructions for the coordination of EOFQTechnical Support Group activities. The primary responsibility of the EOF Technical Support staff is to provide technical advice and support to~the Emergency. Manager and EOF staff. This responsibility includes activities such as trending of critical plant parameters (related to source term and containment integrity) in support of the Rad Prot Sup Supv.
Secondary responsibilities include rnmintaining a "broad engineering perspective" of
.the event and functioning as engineering "liaison" between the site and off-site technical services (e.g. equipment or component vendors).
This procedure structures the response of the EOFTechnical Support group to an emergency by recommending a variety of accident assessment and evaluation activities that may be undertaken depending on the emergency situation. These activities include the trending of critical path parameters, assessment of inoperable systems or components and general-problem-solving for the purpose of advising the K
Emergency Manager and Radiation Protection Support Supervisor on technical and operational matters related to the event.- In addition.the efforts of the Technical Support group may also supplement the efforts of the TSC Engineering group.
"Dueto the wid' spectrurfpossib eaccident scenarios the guidance provided in this procedure is general in nature and designed to aid the Technical Support group in assisting the EOF (and TSC) staffs'inaccomplishing accident mitigation objectives.
The term mitigation objectives refers to those objectives, identified by the Emergency Manage- (and Emergency Direct6r),'which are intended to mitigate or minimize the consequences of the particular accident at hand and may include cooling the reactor, maintaining or regaining containment integrity and terminating or reducing any radioactive release to the environment.
5.0 PRECAU~TIONS None 6.0 INSTRUCTIONS 6.1 Initial Activation ind:Staffing I
46.1.1,:Upon arrival in the EOF refer to the.EOF Tag Board and determine the
-initial Technical Suppbrt Superyisor (TSS) assignment as follows:
A.
"If no-one has assumed the TSS position, turn the TSS tag and sign in as TSS.-
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B.
If theTSS position is already staffed, refer to other EOF positions (for which you're qualified) to determine staffing need in those areas., If unfilled positions exist,.turn the applicable tag and assume that position. If not, report directly to the TSS.
6.1.2 Assume the'duties of Technical Suppiort Su'pervisor (TSS) and initiate "Form 5790-805-01 (TECHNICAL SUPPORT SUPERVISOR ACTIVATION CHECKLIST).
6.1.3 Initiate the Technical Support Supervisor Log Book and maintain the log and record 'significant information in accordance with Section 6.2.
6.1.4 Assess Technical Support: Group staffing and augment as necessary by contacting additional group personnel by telephone. Request the assistande of EOF Support Group personnel (if present).
NOTE: Form 5790-001-01 (EMERGENCY RESPONSE ORGANIZATION) contains the list of qualified EOF Engineering Group And EOF.Emergency Communicators. The "Monticello and Prairie Island Nuclear Emergency PreparednessTelephone
-Directory contains home/pager telephone numbers for all ERO personnel.
6.1:5 For off-hours activatiohs,'as-Technical Support Group personnel report, verify their fitness-for-duty through questioning and/or during initial EOF Command Center status announcements (conducted by the EOFrCoordinator). The fitness-for-duty of individuals should be assessed prior to their engaging in emergency response activities.
The assessment should include, at a minimum, a determination of whether individuals have consumed alcohol within the last five (5) hours...
"6.1.6, Monitor Technical Support-Group staffing and, as personnel become available, assign individuals to perform the following activities:
" A A.
Assign one Technical Communicator (individuals who are licensed, formerly, licensed, certified, formerly certified, or who have three years of technidal/oierational experience) to man the EOF-TSC-CR-OSC communications link and maintain the EOF Operational Status Board with information obtained over the link and from SPDS.
B.
Assign one Technical Communicator (individuals who are licensed, formerly'iensed, certified, formerly certified, or who have three years of technical/operational experience)'to man the EOF-JPIC communications link.-
C.
Assign one (or more) gr'oup members (individuals who are "licensed, formerly licensed, certified,formerly certified, or who have three years of te6hnical/opbrational experience) to operate the SPDS terminal for critical plant variable trending and
-" Transient Reporting Analysis (TRA).- --(If SPDS terminal fails, see section 6.10 for SPDS Vax instructions.)
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MONTICELLO NUCLEAR GENERATING PLANT A.2-805 TITLE:
TECHNICALoSUPPORT IN THE EOF,,
Revision 5 Page 5 of 16
.D.
Assign one (or more) group members to trend and plot critical plant variables that are identified by the EOF Group Leaders as being significant to the event.-.,
E.
Assign available group personnel to perform engineering and
- -operational evaluations of the event in their respective areas of
'e'ertise. Their evaluations should include the assessment of inoperable systems or components critical to accident mitigation "and the determination of corrective actions or alternative
-methods necessary to restore those capabilities.
-~ 6.1.7-F.
Assign one Technical Communicator (individuals who are licensed, formerly licensed, certified, formerly certified, or who have three years of technical/operational experience) to man the Emergency.Notification System (ENS) and maintain'an open communications link with-the NRC (as directed by the NRC).
Verify sufficient Operations Manuals, Technical Manuals, and other reference materials are moved from the Training Center Library to Classroom -10 (or the EOF Command Center) for Technical Support Group use. Contact the EOF Coordinator for assistance with reference material relocation. -Reference materials that should be
-available include: -
A.-
USAR"- -"
B.-
Technical Specifications
=-C P
A a
A C.
Plant ACDs and AWls D.
' o0efations Manual(s)
E.
Plant Logic and flow diagrams F.
"Controlled'Drawing Index
- 1 G:
Aperdure Card File (located in EOF Fax Room)
S... -N1ACDs and N1AWis
- 1.
EOP Flowcharts (controlled set)
'j~:
Design BPisis Document K.
Severe Accident Management Guidelines c-.
Technical Support Guidelines "6.1.8 Establish contact-wilth the Engineering Group Leader (or Engineering Coordinator),in tieJTSC.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-805 TITLE:
"TECHNICAL SUPPORT IN THE EOF Revision 5 Page 6 of 16 6.1.9 When all Technical Support group positions are filled, communication "links established, and technical resource information available, inform the Emergency Manager and EOF Coordinator that Technical Support Grdup staffing is complete.
6.1,10 Complete Form 5790-805-01, (TECHNICAL SUPPORT SUPERVISOR
" ACTIVATION CHECKLIST):
6.1.11 Evaluate available data'and information relative to the event to determine the actual and potential implications of the event from an engineering and operational perspective in accordance with the applicable-sections of this procedure.>
-6.2
-Teclinical Support Supervisor Recordkeeping 6.2.1 Upon activatioin, initiate the Technical Support Supervisor Log Book.
6.2.2 Record evehts, data, t'rends and'other infor-mation 6f engineering or
.operational significance in the log in accordance with the following guidance:-
A.-.,Significant events and the time(s) which they occur including changes in plhtconditions, radiological releases, and plant parameter trehds.'
B.
Failures of plant systems, components, or equipment crucial to achieving accident mitigation objectives and the time(s) those failures occur:
C.
Summarize the results of engineering evaluations and/or recommendations made to the Emergency Manager or TSC Engiheering'staff.,.
D.
Record key operational decisions and strategies developed (or "implmented)-.,
E.
L'og contacts'wit',0ff-site tebhnical vendors, contractors and
'consultants whose seivices have been requested including status reports of their response to the site.
6.2.3 Initiate the following forms (as appropriate):.
A.
Form 5790-805-01 (TECHNICAL SUPPORT SUPERVISOR ACTIVATION CHECKLIST).
B.
Form 5790-805-02 (TECHNICAL SUPPORT SUPERVISOR STATUS UPDATE CHECKLIST),.
C.;,. ; Form 5790-802-04-(ERO SHIFT SCHEDULE - EOF TECHNICAL SUPPORT GROUP)..:.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-805 TITLE:
-TECHNICAL'SUPPORT INTHE EOF-.,
Revision 5 I
'1 Page7of16 1
'D.,
-Checklist 3195 (NRC EVENT NOTIFICATION FORM).
3 E.
'Formn5790-602-0 '(RECOVERY ACTION ITEM LIST).
6.2.4 Periodically monitor the distribution of completed forms in the Technical Support area (of theEOF) to ensure accurate, consistent, approved information is used by Technical Support personnel.
6.2.5
-When directed by the E*i'ergency Manager compile short and o10ng-term recovery action item lists using Form 5790-602-01
"(RECOVERYACTION ITEM FORM)."'
6.2.6 Ensure all completod forms are file'd in the appropriate container provided and retained asemergency records.
6.3 Technical Support Group Shift Scheduling 6.3.1 If the duration of the event could exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, evaluate Technical
.Support group staffing required to suprport 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage.
-6.3.2 I If andjwhen requested by the EOF Coordinator, coordinate the assignment of ERO shifts'foe the group by completing Form 5790-802-04 (EROSHIFT SCHEDULE - EOF TECHNICAL SUPPORT GROUP) and forwarding the completed schedule to the EOF Coordinator.
6.3.3 If 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage is required, cbordinate the departure of "next shift" Technical Support group personnel as follows:
A.
Ensure'EhR pErsG6nel'are'informed of their next ERO shift in accordance with the ERO Shift Schedule.
B.
Ensure personnel are instructed to contact the EOF if their final destination, after departing the site, is a location other than their
-.permanent. residence.; In this case, they should provide a telephone number at which they can be reached if needed sooner than their next scheduled shift.,
6.
C.- _- Ensure ERO personnel are instructed to carry their company ID card to regain access to the site (in the evernt road blocks are
-establishe.d by off-site authorities).,
3.4 Next shift ERO personnel should depart the EOF as follows depending on the situation:
A.
If no releases (above Tech Spec limits) are occurring and no "off-sit& protectiVe actions are in effect, personnel may depart the EOF and site'as'noimal.
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MONTICELLO NUCLEAR GENERATINGPPLANT A'.2-805 TITLE:
TECHNICAL SUPPORT IN THE EOF,
Revision 5 I
Page 8 of 16 B.
If significant releases are occurring and/or off-site protective actions are in effect, coordinate the departure of next shift ERO "personnel with the local county, authorities (Sheriff Dispatcher or County EOC).- The -departure roiite should take personnel upwind of any releases.-
EOF Status Upates 6.4.1 When notified of an EOF status update, use Form 5790-805-02 (TECHNICAL SUPPORT SUPERVISOR STATUS UPDATE CHECKLIST)' to prepare for the Technical Support portion of the update. Record the date and time of the status update in the spaces provided on the form.
6.4.2 During EOF updates; the Technical Support Supervisor should provide a status of the following topics using Form 5790-805-02 as a guide:
A.
Review the status of' eactor health, core cooling systems operability, primary and secondary containment integrity, status of threatened systems and systems or components approaching or exceeding their design lirnits.
B.
Revievý inoperable' cmnponents and systems, critical to mitigation "6bjdctives and 'a statue of the efforts~to return the system to an operationalstatus'or alternative systems/methods to accomplish mitigation objectives.
C Review release paths,-estimated release duration, source term and potential for changes'in the magnitude of the source term.
D.
Review any trends or-graphs developed by the group and the significance ofthose, trends to the accident mitigation effort
. including predicting. operational consequences of the trends.
E.
Review the potential for emergency classification changes (escalations) based on plant conditions.
I I
F.
-Review the status of engineering evaluations in progress and any items referred to the EOF Technical Support staff by the TSC and the status of those items:
6.4.3 If the NRC is present (in the EOF),,your NRC counterpart should provide input immediately after the TSS, portion of the status update.
6.4.4 On Form 5790-805-02 note significant items reviewed during the Rad Prot Sup Supv, EOF Coordinator, and EM portion of the status update.
6.4.5 Upon completion of the status update, note the time of the next status update (if established, by, the EM).. -
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MONTICELLO NUCLEAR GENERATING PLANT A.2-805 TITLE:
- TECHNICAL-SUPPORT IN THE-EOF,,
Revision 5 S....
- Page 9 of 16 6.5 Genreralinstructions 6.5.1 Conrtinuously assess plant conditions and provide engineering and operational adviced'tbthe Emergency Manager (and other EOF Group Leaders) in accofdahice With the applicable section of this procedure.
6.5.2 Ensure the technical communicati6ns link is'continuously manned throughout the event to obtain operational and technical information.
The informationobtained over the link,'along with data from the SPDS terminal; should be"used to maintain the Operational Status Board.
6.5.3 Ensure the technical coini'nunications link is continuously manned throughout the event to pass operational and technical information onto the Technical Resource Person and/or NMC Executive j
Spokesperson at the JPIC.
6.5.4-: Coordinate the manning of the Emergency Notification System (ENS) link with the TSC'and Control Room.- Ensure the ENS is continuously manned -(as requested by the NRC) in accordance with the applicable section of A.2-803 (EMERGENCY COMMUNICATIONS AT THE EOF).
.1 NOTE: Notification of the NRC must be completed no later than 1-hour after an emergency classification change. When staffed, the ENS Communicator is responsible for the completion of Form 3195.' Assistance may be provided by "others in the EOF Technical'Support area or Radiation Protection Support area.
6.5.5
'if changes in emergency classification occur (escalation or "termination), ensure Form'3195 iý completed. If necessary, refer to "4 AWI-04.08.02 (1 OCFR50.72 'and 10CFR73.71 IMMEDIATE NOTIFICATION) for instructiohs on'completing Form 3195. The
.completed Form'3195 SHALL be"reviewed and signed by the Emergency Marager prior to communicating the information to the
- NRC. Communicate the classificatiorn change to the NRC via the ENS link.
- 6.5.6 Ensure the Operati0nal Status Board in the EOF is continuously updated throughout the event with information obtained from the Technical Communication link and SPDS.
6.5.7 Serve as the "point-of-contact" with off-*site vendor and contract technical services requested by the EOF or TSC (e.g., General Electric, etc.). Request off-site vendor/technical services in accordance with the instructions in A.2-804 (EOF SUPPORT AND S- -
LOGISTICS)...
6.5.8 Interface with"NRC technical analysts (e.g., Reactor Safety Coordinator, Reactor Safety Assistant, etc.) present in the EOF (or by telephone if the NRC site incident responseteam is not present) as necessary..
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MONTICELLO NUCLEAR GENERATING PLANT, A.2'-805 TITLE:
-TECHNICAL SUPPORT IN THE EOF
.-'Revision 5
Page 10 of 16 6.5.9 As problems arise (or when requested by the TSC), assess~the engineering and operational aspects of.the, problem according to its
'importance to accomplishing accident mitigation objectives. Provide input to the Emergency Manager (or.TSC Engineering Group) on possible solutions oralterative mitigation possibilities.
65.10 Respond to requests for techhical supp'ort from the TSC. The followingare examples of. itehis that' may be referred to the EOF fwchnicalSupport G'roupforalbationdepenrding onTSC and EOF
~ ~resources:.,*.,-,.-
A.
The evaluation' of inoperablecom onents"0r systems that may or may. n6t be immediately required to accomplish accident "mitigation'objectives and that cobld be identified as short or "long-term recovery items.
B..
Assistance with assessment of major engineering problems S*
which arise during the event (i.e., facility, system or component
- design specification, etc.) which may require more detailed evaluation th'an the TSC staff can perform.
C.
-Technical "liaison"'with bff-site technical vendor support on
-.',equipment or component needs' and specifications (e.g., General Electric Emergency Support Program).
D.. The operational (and engineering).analysis of postulated accident scenarios (ile., what ifs) on the plant simulator to determine plant response characteristics for known (existing)
- ~~simulator modes.c i,°.
16.5.11 In cboberation with-the TSCfdetermrine if off-site utility organizations
- (e.g., Substation -crews, corporate, engineering, core analysis, etc.) are required to assist in engineering assessment efforts. If so, coordinate contacting these organizations with the TSC Engineering Group and the EQF Coordinator.-.
6.5.12 As the Technical Support staff make recommendations to the Technical Support Supervisor (or Emerg-en'cy Manager), the recommendations should be reviewed with-thedTSC Engineering Coordinator (or Engineering Group Leader). Thie discussion of the EOF Technical Support group's recommendations should include:
" A."
Consideration'of the'recommendati6ns in the overall emergency Sresponse and mitigation effort.
B..
A determination 6f whiich corre6tive action recommendations should be pursued imrnbediately' (accident mitigation) and which may be deferred (recovery action list).,
C.
Prioritize the action to be taken in terms of other emergency response actions planned and available resources.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-805 TITLE:
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"- 6.5.13 Continuously re-evaluate priorities for the Technical Support group and
'redirect the group's-effort as necessary.,_.
6.6 Operatil Asses NOTE: The Technical Support Guidelines (TSGs) describe enhancements (additional information and methods to support decision making)-to technical support activities that are normally undertaken by theERO staff in support of the Control Room. TSGs should be utilized bythe EOF Technical Support Staff.
The TSGs consist of four interrelated assessments Which address these enhancements in the following functions:
A.7-TSG-02 (CONTROL PARAMETER STATUS ASSESSMENT): obtaining and processing appropriate plant data' in the ERO.*
A.7-TSG-03 (PLANT STATUS ASSESSMENT): assessing current conditions in
'-various areas of the plant where needed instruments or equipment are located.
A.7-TSG-04 (sYSTEM STATUS ASSESSMENT):evaluating the availability of systems neededto implement the EOPs and SAMGs.
A.7-TSG-05 (EOP/SAMG ACTION STATUS ASSESSMENT): prioritize system restoration and action timing as indicated by accident management strategies.
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6.6.1, Throughout the event, continuously obtain SPDS data and information applicable to theevent and:
A.,
-Provide data-f6r the trending of critical plant variables to identify adverse trends and attempt to forecast (predict) significant events that could adversely affect the plant or accident mitigation "effoffs underway *or planned.
I
",1 t,
- i-
,, 'B. -.' Provide parameteý trends for comparison with Emergency
--. Operating Procedure (EOP) implementation to aid in predicting upcomingoperatiohal transients or6e*olutions.
C. ',immediatelyreport'significant adverse trends(or data) to the Te6hnfical Support Supervisor'and/or Emergency Manager.
D.
"Periodically (or when significant trends are identified) obtain "hardcopy print-outs and distribute to all EOF Group Leaders for review.
E.
When the irrimeliate emergency has been mitigated, trend selected plant parameters for the duration of the emergency phase-to 6id in the evaluation of the entire event.
.5 S
'.
'-(S S'5Ž I
I.,,.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-805_
ITITLE:
JTECHNICAL SUPPORT INTHE EOF Revision 5 I
Page 12 of 16 6.6.2' Continuously remain aware of plant conditions and critical parameters.
Periodically, and as significant changes occur,,compare plant
-copditions/parameters with the Emergency Action Levels (EALs)
"contained in EPIP X2-101i(CLASSIFICAr*ON OF EMERGENCIES).
Make recommendations' r6garding classification changes to the Emergency Manager. Plant condition§/parameters to review include:
-.A.
Fission product barrierintegri.y SB-B Containment integrity (e.g.; pressure, temperature, cooling capability,etc),..
C.
Release rate, source term and the potential for changes in source term magnitude.
D.
ECCS system availability and operability.,
6.6.3 In' cobperation with the TSC, evaluate plant systems and/or components that become inoperable todetermine their impact on achieving accident mitigation objectives and:
A..
Prioritize (may be determined by.the TSC) the systems or
",components in order of importance to accident mitigation objectives.
B.
Evaluate corrective actions required to restore needed capabilities or determine alternative. methods to accomplish the mitigation objective.
C.
For crucial mitigation objectives that rely on alternate (i.e.,
backup) systems or-rethods develop a contingency plan to manage the consequences associated with a failure of the backup system'or method.
6.6.4 If Emergency Operating Procedures (EOPs) or Severe Accident Management Guidelines (SAMGs) are implemented assign a member "of the Technical Suppo'rt Staff (an Operations instructor qualified as a SAMG Decision Maker, seeý Form'5790-001"-01) to follow the implementation of the EOPsjSAMGsl"Tlie objectives of EOP/SAMG "following are:
A.
TO predict significant operational evolutions (e.g. venting primary containment) that may be imminent or.required and to advice the EOF Staff (Emergency Manager, Radiation Protection Support Supervisor) of these predictions.
B
-Toprovide updates to the" EOF Staff on the status of EOP/SAMG
". implementation and'the effects these may have on overall "accident mitigation:.
C.
Toverify proper, EOPiSAMG implementation. Providing feedback to the Technical Support Supervisor or the TSC Engineering Staff if the EOP/SAMG implementation is improper.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-805 TITLE:
TECHNICAL SUPPORTIN THE EOF,_.
Revision 5 Page 13 of 16 6.7 Engineering Assessment.
6:7.1
'Continuoubslyeyvaludate th'eevent fr6m a-broad engineering perspective and 'advise the' Emergenhcy Manager arid Radiation Protection Support Supervisor (Rad Prot Sup Supv) on m'atters related to reactor health, containment integrity and actual or potential source term (e.g.,
expected release duration based on containment pressure and leak rate, etc.).
6.7.2 Trend critical'plant parameters (related'to the event) to aid in accident analysis and identification of adverse trends. Parameter trends should include if applicable:
NOTE: Critical plant variable trend charts should be used for trending parameters related to'the event.. -
A.-
Reactor power, level and pressure (display 011 on SPDS).
B.
-Torus water level, temperature and pressure (display 021 on SPDS)..
C.
Drywell temperature and pressure (display 022 on SPDS).
D., Stack dnd Vent release rates, ([tCi/Sec from displays 112 or 000 on SPDS).'
E..
Other criti6cl.plant parameters as deter-mined by the event.
6.7.3 As system or component failures occur, evaluate the system or component (as requested by the TSC) from an engineering perspective to determine:
NOTE: -Classroom 10, located immediately adjacent to the EOF Command Center Technical Support, area should be used by EOF technical support personnel for detailed engineering evaluations that need otbe accomplished in the Command Center proper.
SA..
The system or component's relative importance to achieving accident mitigation objectives.
B.,
The reason for thelfailure and what action(s) may be required to 4,return the system or component to a functional status (e.g.,
'component repair, replacement, etc.).
C.,
.If.component'repair/replacement is necessary, assist the TSC
,:-engineering~staff (as requested) in determining replacement component, designspecifications and requirements.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-805 TITLE:
TECHNICAL SUPPORT IN THE'EOF.
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Systems or components that are not immediately crucial to accident mitigation, or which may require detailed investigation, should be evaluated, on an as:time-allows basis and/or identified on the Short-Term, or Long-Term Recovery Item List.
6.7.4 :+Throughout the event, maintain a listing of systems and/or components
+"
-' "that become inoperable during the event.
6.7.5 In cooperation with the TSC engineering staff, serve as the "point-of-contact" with off-site vendors/parts supplierswhen procuring replacement parts or. omponents.
6.7.6 As reqUested by the Emergency Manager (or TSC Engineering group) activate General Electric's Emergency Support Program in accordance "with A.2-21 0 (ENGINEERING SUPPORT INTHE TSC).
6.8 Technical Support Supervisor Shift-Turnover 6.8.1 Upon a rrival at the EOF, the on-coming Technical Support Supervisor should review the:
A.
Chronological Events Flipchart to become familiar with key
,.events that have occurred.
+
B.
The Technical Support Supervisor Log book entries (for the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if applicable).*,:
6.8'2 Review the following information with the existing Technical Support Supervisor. If the NRC is present include the TSS counterpart (Reactor Safety Coord) in the turnover review if possible:
A. '-Review the status of current Technical Support Group staffing and future staffing needs.
B.
-',Review the currentfplant status including the extent of radioactive releases, reactor status and other operational issues related to the event (e.g., core damage estimates,- etc.)..
C.
The status of EOP/SAMG implementation (if applicable) and a other operational information related to the event (i.e., releases, containment venting, etc.).
D..
- The status of any technical engineering evaluations in progress (or requested by the.TSC):,
E.
The trend charts of critical plant variables.
"F.
The status of any technical vendor, contractor and/or A/E support requested.
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MONTICELLO NUCLEAR GENERATING PLANT A.2-805 TITLE:
TECHNICAL SUPPORT IN THE EOF,*.,
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G.
The status of communications links (ENS, etc.) and off-site
-agency interface-(e.g., NRC incident response, etc.).
6.8.3 If theEmdrgency-Manager is'conducting a turnover briefing attend the EM briefing as requested.
6.8.4 The on-coming TSS should contact the Engineering Group Leader (in the TSC) to review the current status and determine any assistance EO F technical support group can provide.
6.8.5 Upon completion Of the turnover discussions the on-coming Technical Support Supervisor should formally assume the duty and note the turnover in the TSS Log Book.
6.8.6 Informthe' Emnergency Manager the TSS turnover is complete.
6.8.7 Make an announcement inthe EOF Command Center regarding the turnover of TSS responsibilities.
6.9 Event Termination or Recovery 6.9.1 -Evaluate plant condition' throughout the event. When the conditions "listed in A.2-811 (EVENT TERMINATION OR RECOVERY IN THE EOF) are met advise the Emergency Manager that the event may be terminated or-the transition to Recovery made.
6.9.2 When directed by the Emergency Manager compile a list of systems and/or components affected by.the event which require repair or evaluation to return themto their pre-accident condition as follows:
A.
Use Form 5790-602-01 to compile the list of systems/components that require repair or evaluation.
B.
Refer to A.2-81 1, Section 6.2, to identify items to consider when compiling theRecovery Action Item list.
C.-
Coordinate'the development of the Recovery Action Item list with the Engineering Group Leader (in the TSC).
D.
Gather the-Recovery Action Items lists from the other EOF (and TSC group leaders) and compile all the lists into one master list.
SE.'
On the'Recovery Action Item list include a description of the action reuqLired for each item to return that system/component/area to a preaccident state.
6.9.3 Submit the completed Recovery Action Item list to the Emergency Manager for review and inclusion in the turnover to the Recovery Manager.
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Page 16 of 16 6.9.4 Participate in the transition to recovery and turnover discussions as requested by the Emergency Manager.
6.10 SPDS/ERIS Vax Instructions:
6.10.1 Using any VAX terminal, energize the terminal using the ON/OFF switch.
6.10.2 Log onto node LARRY (by responding to the LOCAL> prompt or SERVICE NAME = prompt for multi-session terminals).
6.10.3 Respond to the USERNAME: prompt by typing HQEC and pressing RETURN.
6.10.4 Respond to the PASSWORD: prompt by typing HQEC and pressing RETURN.
6.10.5 Respond to the FILE NUMBER: prompt by entering the number of the desired display (1-28).
6.10.6 Review the data display for desired information. Ensure the status code (displayed on the right of the screen), is code 1 indicating the data is good. If not, the accuracy of the data is questionable.
6.10.7 To change display screens (select other data), enter CTRL Y and respond to the WOULD YOU LIKE TO SELECT ANOTHER FILE:
prompt by entering Y and pressing RETURN.
6.10.8 -To exit the system, enter the CTRL Y and respond to the WOULD YOU LIKE TO SELECT ANOTHER FILE: prompt by entering N and pressing RETURN.,
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