ML20217Q733

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Informs That on 980317-18,NRC Staff Attended Severe Accident Mgt Implementation Demonstration at Bg&E NPP in Lusby,Md. List of Attendees & Agenda Encl
ML20217Q733
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 05/04/1998
From: Palla R
NRC (Affiliation Not Assigned)
To: Holahan G
NRC (Affiliation Not Assigned)
References
FACA, NUDOCS 9805110060
Download: ML20217Q733 (209)


Text

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NUCLEAR BEGULATOFN .COMMISS)ON wearem a me w,-

MEMORANDUM TO: Gary M. Holahan, Director Division of Systems Safety and Analysis Office of Nuc. lear Reactor Regulation THRU: Carl H. Berlinger, Chief hcJ.E Containment Systems and Severe Accident Branch Office of Nuclear Reactor Regulation

'FROM: Robert L. Palla, Sr. Reactor Engineer Md -

Containment Systems and Severe Accident Branch Office of Nuclear Reactor Regulation

SUBJECT:

SEVERE ACCIDENT MANAGEMENT DEMONSTRATION VISIT AT CALVERT CLIFFS, MARCH 17-18,1998 On March 17 and 18,1998, NRC staff attended a severe accident management (SAM) implementation " demonstration" at the Baltimore Gas and Electric (BG&E) Calvert Cliffs Nuclear Power Plant (CCNPP) in Lusby, Maryland. NRC staff included Robert Palla, Containment Systems and Severe Accident Branch; Falk Kantor, James O'Brien, and Serge Roudier, Emergency Preparedness end Radiation Protection Branch; David Desaulniers, Human Factors Assessment Branch; and David Silk, Region l Emergency Preparedness.

Rick Hasselberg, AEOD, attended the SAM table-top drill on the second day. Approximately 20 representatives from U.S. nuclear plant sites, the Nuclear Energy Institute (NEI), the Combustion Engineering and Westinghouse owners groups, and 3 representatives from foreign nuclear organizations also attended. A list of attendees is provided as Attachment 1. An agenda is included as Attachment 2. /

The purpose of the demonstration was to provide the NRC and visiting utility representatives nformation on BG&E's implementmion of severe accident management pursuant to the formal

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industry position contained in NEl 91-04, Revision 1. Implementation activities at CCNPP are in progress and scheduled to be completed by December 1998. The staffs objectives for the visit hg

- were to gain insights into the licensee's implementation process, including development and implementation of the plant-specific severe accident management guidelines (SAMG), use of

  • the SAMG during drills, and plans for providing and evaluating severe accident training. This information will be used to guide efforts to finalize a Temporary Instruction (TI) for evaluating Ty*/

licensee severe accident management programs. The CCNPP demonstration was (he fourth adustry-hosted demonstration, and the f;rst demonstration at a Combustion Enginegng-designed facility.

.The first day of the demonstration consisted of licensee presentations conceming site-specific SAMG development and impicmentation efforts. Topics addressed included: the BG&E SAM implementation philosophy and project plan; the existing nuclear organization, emergency operating procedure structure and emergency response plan organization; the Comoustion 1 9905110060 990504 PDR ADOCK 05000317 %rL d P

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- ' The TSC did not make a noticeable effort to trend plant parameters and assess the extent of core damage. As such, it was not clear whether the TSC understood the state of the core during the drill.-

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- The drill debrief was attended by all drill players, as well as evaluators and controllers, L

E thereby providing an opportunity for staff from the various ERO facilities to share perspectives. The discussions centered on the degree to which the various drill

objectives were met, and were at a high level given the impromptu nature of the l critique. A more in-depth evaluation and follow-up of technical aspects of drill l performance appears appropriate, since technical issues may be subtle and not l immediately obvious. A. limited number of weaknesses were discussed during the -

[ debrief, but no follow up actions appeared to be identified as part of the debrief. A more formal process for identifying areas for improvement and assuring that corrective actions are taken appears necessary.

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! Viability of the Demonstration Process l

  • The A/M demonstration visit met the established objectives of providing insights into the L SAM implementation process at one CE plant, and areas where changes to the draft Tl will

! be needed to accommodate the observed differences in implementation approaches.

!- However, the demonstration format does not allow sufficient time and flexibility to

[ thoroughly evaluate the licensee's implementation.

In closing comments, Fred Emerson, NEl, reminded participants of the importance of keeping the priority of SAM implementation in line with the priorities of more important plant activities.

L He stressed that utilities need to keep usources for SAM implementation and training in l perspective with other activities, but given the commitment to complete implementation as an

industry initiative, the industry has a responsibility to do this well, and in a way that carries out the mandate that industry set for itself.

! blSTRIBUTIOC Wl6ttachments:

SCSB R/F (2) Central Files PDR MModes, RI KBarr, Ril JCreed,Rlli BMurray, RIV DISTRIBUTION w/o Attachments.

TCollins RGallo DDesaulniers CMiller JO'Brien

. RBarrett . RHasselberg DMatthews DOCUMENT NAME: CALVERT.TRP -

Ts receive a copy of this document indcate in the bos: "C" = Copy without attachment / enclosure *E" = Copy with attachment / enclosure "N' = No copy OFFICE SCSB:DSSAfillR,,1 PERB:DFW)M l6 HHFB:DRCH , ln BC:SCSB: H)Jpgl l NAME RPalla:bw /T/AN- JO' Brier (/*4 g(meMDDesaulniers kW CBerlinge:LVM DATE f /3d98 f/ f /9ff (/4 /98 .$/ //98 / /98 OFFICIAL RECORD COPY

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2 Engineering' Owners Group (CEOG) products, including generic accident management

- guidelines, calculational Ods, and training mateuals; examination of CCNPP risk insights for inclusion in SAMG; development and review of plant-specific SAMG; integration of SAMG into

- the CCNPP Emergency Response Plan implementing Procedures (ERPIPs) and associated changes to the ERPIPs; training approach and training program development, including BG&E

' actions to address each element of the systems approach to training; and plans for future table-top and integrated drills for verification and self assessment. The generic and plant-specific guideline documents were made available for examination during the meeting. Presentation materials are provided as Attachment 3.

The principal activity on the second day was a three-hour tabletop drill demonstrating the use of the SAM ERPIPs by the Technical Support Center (TSC) and control room staff. The drill scenario was initiated by a tornado strike in the switchyard with subsequent failures of the Unit 1 diesel generators. Both turbine-driven auxiliary feedwater (AFW) pumps started, but tripped and could not be reset. A mechanical failure of a main valve in the fire water hook up line occurred, preventing the use of fire water for decay heat removal. The station blackout with total loss of feed water led to entry into the Functional Recovery Procedure (EOP-8),'

declaration of a Site Emergency, and staffing of the Emergency Response Organization (ERO).

The event progressed to steam generator (SG) dry out, reactor coolant system (RCS) pressurization to the safety valve setpoint, steam release to containment via the' quench tank rupture disk, and core uncovery. Drill play was initiated with the accident sequence in progress and the reactor vessel water level near the top of active fuel. The TSC staff used ERPIPs 601 through 611 (which contain the piant-specific SAMG) to assess plant status and evaluate potential recovery actions and associated challenges to the RCS and containment. This included evaluation of reinitiating AFW flow to the dried out SGs to avoid creep rupture of the tubes, using PORVs to depressurize the RCS and evoid high pressure melt ejection, and the threat of hydrogen bum associated with using containment sprays to depressurize containment.

The control room staff used ERPIP 611.(restorative guidelines) and supporting attachments to evaluate alternate electrical and water source lineups, including using the Unit 2 diesel

_ generator to energize a 4 kV bus and recover AFW, back feeding the (recovered) Unit i diesel generator through a 13 kV transformer to energize a 4 kV bus and recover high pressure safety.

injection (HPSI) and containment spray, and cross-connecting water sources to the contain-ment spray system. Actions to recover AFW, HPSI, and containment spray pumps were eventually successful, and these water sources were used for injection to the steam generators,  !

reactor vessel, and containment sprays. The drill was terminated at that time. Additional  !

information regarding the scenario is provided as Attachment 4.

The drill focussed on demonstrating the use of the SAM ERPIPs, and involved simulation of activities in the control room and TSC.' Staffing of the TSC was limited to the TSC Director and engineering / analyst positions (described later). The Operations Support Center (OSC) and the Emergency Operations Facility were not staffed but communications with these facilities were simulated. The control room and TSC players were located in opposite ends of a triple- ,

adjoining classroom. Drill observers were stationed in the area between the TSC and control room, but were able to move freely between the two facilities, thereby having the opportunity to

- observe the inter-facility communications and activities within each facility. Players were pre-  ;

staged in both facilities and activation of the TSC was not simulated. Communications between the control room and TSC, and the TSC and OSC were via a phone link and face-to-face.

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. A debrief / critique was conducted immediately following the conclusion of the tabletop drill at

.which time drill participants and evaluators prov ded thougnis about the' drill. ' An exit meeting was then held during which the licensee, NRC, NEl, and other participants provided their respective' observations.

Major staff observations were discussed at the exit meeting and are summarized below. The observations are based largely on information presented during the presentations, without the

. opportunity for staff follow-up, and should not be construed as conclusions:

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e. The process for implementing SAM at CCNPP appears to be well defined and effectively managed. The process includes modification of the ERPIPs to explicitly incorporate the plant-specific SAMG, identification of plant-specific insights from the IPE and IPEEE and incorporation of these insights into the SAMG, development and implementation of SAM training, and conduct of SAM table-top and verification drills.

! e The presentations were informative and addressed most of the topics discussed in l- previous A/M demonstrations. Based on the information provided in the presentations, the CCNPP approach and draft plant-specific guidance appears to be technically sound, and responsive to each of the A/M implementing elements in the formal industry position on

!: severe accident management (contained in Chapter 5 of NEl 91-04, Revision 1).

I Additional review of the materials and records in each of these areas would be needed to confirm these observations once the licensee has completed their implementation efforts.

Kev Annects of SAM imolementation at CCNPP e BG&E is implementing the plant-specific SAMG as explicit guidance within the CCNPP ERPIPs. Consequently,12 new ERPlPs will be added to the existing set of ERPIPs.

ERPIP 601 and 602 will contain guidance on initial diagnosis and verification of the plant damage condition, respectively. ERPIPs 603 through 610 will contain guidance and

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strategies for each of the 8 plant damage conditions defined by a 2x4 matrix of RCS/

containment conditions. ERPIP 611 will contain guidance on the restorative actions,

. including information on unique system alignments and cross-connects for CCNPP. In addition, the ERPIPs describing responsibilities for several ERO positions will be impacted by SAM implementation and will be modified accordingly.1The licensee does not plan to update the Emergency Response Plan (ERP) since at the level at which the ERP is written, the description of the ERO organization and position-specific responsibilities and assignments are not altered by the SAM implementation.

e The licensee intends to assign the responsibilities for SAMG implementation /use and severe accident decision making to the TSC. Within the TSC, the TSC Director will serve as the SAM " decision maker", and five technical staff will serve as " evaluators", i.e., three Reactor Core Engineers, the Operational Analyst, and the Technical Analyst. All BG&E staff that fill these positions will be trained on SAM as part of ERO training.

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e! The licensee has determined that no new ERO positions would be needed to implement )

the SAM ERPIPs. However, all duties and emergency responsa activities were not:

. simulated in the table-top drill. The licensee plans to conduct an inter-facility drill in the August 1998 time-frame to der.1onstrate that all responsibilities can be effectively carried 2 l . out, e- Consistent with the CEOG approach (but contrary to the approach taken by the other '  !

owners groups), the contrcl room operators will continue to uso the EOPs after the onset of

. core damage rather than exiting these ' procedures. However, in. view of the limitations of the EOPs for severe accidents, the operators are instructeddin the ERPIPs) to contact the

~ TSC for technical guidance and to implement procedures her TSC direction.

-e The licensee intends to utilize scenario templates for developing future drill scenarios. The

, , templates are being developed by the CEOG to provide a common basis for scope, .

I complexity and content of table-top drills, and consistency for self-assessment of SAM capabilities.

Develonment and Imsb.T.e.M;cn of Plant-Snecific SAMG l

l -* The licensee used the generic CEOG SAMG as a template for developing the CCNPP-l specific ERPIPs.- The CEOG process was followed directly with only minor differences in L the details. The differences include adding action blocks (in ERPIP 601) to incorporate

!' IPE/IPEEE insights, prioritizing the parameters for confirming plant damage conditions (in i ERPIP 602) based on perceived usefulness, organizing the CHl.As in the restorative actions section (ERPIP 611) based on last known information, and adding information on attemate mechanical / electrical alignments (in ERPIP 611) and modifying the other portions of the guidance (ERPIP 603-610) to include references to this information. Differences from the generic guidance will be documented in a plant-specific basis document.

  • BG&E performed a systematic examination of sequences in the current PRA and a review of IPE and IPEEE documentation to identify any additional insights that should be included ,

in the plant-specific SAMG. Approximately 20 plant-specific insights were identified, l L encomp ssing measures for core damags prevention as well as_ mitigation. These insights were factored into the plant-specific SAMG as either entries in the insights section (ERPlP

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601), enhancements to the CHLAs (typically in the Cautions section),- or alternative electrical and mechanical system alignments / success paths.

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  • BG&E intends to perform a screening evaluation of the SAM-related changes to verify that all associated activities are outside the plant's licensing and design basis, and that the ERPIP changes have not reduced the effectiveness of the emergency plan. The l alternative system alignments included as attachments to the ERPIPs will not be evaluated in advance, and will need to be evaluated on-the-fly prior to implementation during a drill or event. This approach appears consistent with the guidance provided in the staff's January 28,1998 letter to NEI concerning SAM implementation issues, but this would need to be ,

confirmed atter the licensee has completed this evaluation.

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5. i e The licensee does not intend that 50.54(x) and (y) be automatically invoked upon entry into the SAMG, or be invoked on a one-time basis for all severe accident-related actions.

Rather the applicability of 50.54(x) and (y) is expected to be considered for each major action, such as putting equipment in pull-to-lock position and cross-connecting /back feeding electrical equipment, and invoked as appropriate.. The use of 50.54(x) and (y) is expected to be entered in the shift managers log.. _

Severs Accident Training
  • _ BG&E outlined their approach for addressing each element of the systems approach to.

training. This approach includes: (1) confirming the applicability of the INPO generic

> training matrix for evaluators and decision makers, and making the task list and training -

objectives plant-specific, (2) evaluating the INPO lesson plans and computer-based _.

training material on phenomenology, and developing expanded, site-specific lesson plans based on the CCNPP leaming objectives, (3) providing classroom training and participation in a table-top training drill for all evaluators, decision-makers, and implementors, and (4) evaluating classroom training effectiveness and table-top training drill effectiveness using several mechanisms.

  • All SAMG training will be provided as part of the ERO training program. SAMG. training will not be provided to operators as part of the Licensed Operator Requalification training

' because: (1) no new responsibilities involving severe accidents are assigned in the EOPs, (2) no new responsibilities assigned in the SAMG, and (3) there is no " transition" from the EOPs to the SAMG with the CEOG approach. However, knowledge and information related to the operators' role as SAMG implementors will be included within the required ERO training program.

  • Because the SAMG is incorporated within the ERPIPs at UCNPP, SAM refresher training will be provided on an annual basis as part of the ERO training program. The licensee .-

expects the SAM training to be administered by subject matter experts (possibly the CCNPP staff that developed the plant-specific SAMG).

e As a last step in completing SAM implementation, E7&E plans to conduct an inter-facility SAM drill (with all facilities ruanned) to verify that the SAMG has been adequately .

integrated within the ERO. Thereafter, the licensee plans to conduct one SAM table-top drill every year, and to reassess the need for additional integrated SAM drills after 5 years.

. BG&E plans to evaluate classroom training effectiveness and the need for future training

' program changes based on feedback from trainee reaction forms, management oversight of training, and performance assessment. Table-top training drill effectiveness will be

- evaluated using the same mechanisms, as well as observations by controllers / evaluators, .

and self-critique by drill participants. _ lt is unclear if the planned drill frequency and

' feedback mechanisms will provide an adequate level of feedback regarding training effectiveness.

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AIM Drill Performance and Self-Assessment Process e Overall, the tabletop drill was useful in showing the use of SAMG by the TSC. TSC entry into the SAM ERPIPs was not apparent due to the manner in which drill play was initiated i in the table-top drill. Execution of the SAM ERPlF: and the. development of :

recommendations regarding strategy implementation appeared te 1ely, and did not result in undue delays in accident response,; The players appeared able to use the guidance effectively to assess plant status and develop recommendst5n:, on strategy implementation. - Based on the tabletop drill observations, no problems with workload were noted, however, all duties and emergency response activities were not simulated in the tabletop drill.

e. The degree of participation and staffing of the various emergency response facilities in the CCNPP drill, appears adequate for purposes of training and demonstrating the use of the SAMG, but insufficient for purposes of fully demonstrating: (1) the entry into SAMG, (2) the ability of TSC engineers to implement the SAM ERPIPs and other E-Plan responsibilities concurrently, and (3) communications between ERO facilities (i.e., the Operations Support Center and the Emergency Offsite Facility), since these aspects of response.were not fully represented in the tabletop drill. CCNPP staff indicated that they .

were considering conducting an integrated drill with full ERO staffing to more fully assess i the integration of SAMG responsibilities into the ERO structure.

e The drill package included a drill scenario time line and description of exp6 cted actions at i various times. This information was useful to observers in tracking the prcgress/ J performance of the TSC during the drill. The package also included a drill critique'-

observation form for use by the drill evaluators in assessing each of the drill objectives.

The degree to which TSC performance met the outlined expectations was discussed during the players debrief.

.* The licensee developed a CHl.A evaluation form to track results of technical assessments performed, and record review and approval of the results (3 signatures).

  • - L NRC staff offered a number of observations conceming drill organization and performance.

These are summarized below.

Limitations in drill scope led to several artificialities. For example, no TSC positions .

j other than the TSC director and engineering / analyst positions were staifed; the drill I players were directed to focus on the SAM ERPIPs and avoid spending time on other ERPIPs, emergency action levels (EALs), protective action recommendations (PARS),

and core damage assessments (CDAs); most bWr-facility communications were face-to-face rather than via phone links; and the status boards, safety papameter display system (SPDS), and other aids were not used during the drill. Full ERO staffing,

- execution of all_ assigned duties, and use of the ERO communication system could substantially alter TSC performance and the ability to effectively implement SAMG ERPIPs. A fully-integrated drill in the actual ERO appears necessary to confirm that SAMG has been properly integrated into the ERO.

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-, The TSC did not make a noticeable effort to trend plant parameters and assess the extent of core damage. As such, it was not clear whether the TSC understood the L

state of the core during the drill.

- . The drill debrief was attended by all drill players, as well as evaluators and controllers, thereby providing an opportunity for staff from the various ERO facilities to share .

- perspectives.' The discussions centered on the degree to which the various drill objectives were met, and were at a high level given the impromptu nature of the i critique. A more in-depth evaluation and follow-up of technical aspects of drill performance appears appropriate, since technicalissues may be subtle and not immediately obvious. A limited number of weaknesses were discussed during the debrief, but no follow up actions appeared to be identified as part of the debrief. A more formal process for identifying areas for improvement and assuring that corrective L

actions are taken appears necessary.

Viability of the Demonstration Process

  • The A/M demonstration visit met the established objectives of providing insights into the SAM implementation process at one CE plant, and areas where changes to the draft Tl will be needed to accommodate the observed differences in implementation approaches.

However, the demonstration format does not allow sufficient time and flexibility to thoroughly evaiuate the licensee's implementation.

In closing comments, Fred Emerson, NEl, reminded participants of the importance of keeping the priority of SAM implementation in line with the priorities of more important plant activities.

He stres' sed that' utilities need to keep resources for SAM implementation and training in perspective with other activities, but given the commitment to complete implementation as an industry initiative, the industry has a responsibility to do this well, and in a way that carries out the mandate that industry set for itself.

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! 7 The TSC did not make a noticeable effort to trend plant parameters and assess the li extent of core damage. As such, it was not clear whether the TSC understood the state of the core during the drill.

l The drill debrief was attended by all drill players, as well as evaluators and controllers, thereby providing an opportunity for staff from the various ERO facilities to share perspectives. The discussions centered on the degree to which the various drill objectives were met, and were at a high level given the impromptu nature of the critique. A more in-depth evaluation and follow-up of technical aspects of drill performance appears appropriate, since technical issues may be subtle and not immediately obvious. A limited number of weaknesses were discussed during the debrief, but no follow up actions appeared to be identified as part of the debrief. A more formal process for identifying areas for improvement and assuring that corrective actions are taken appears necessary.

Viabilltv of the Demonstration Process e The A/M demonstration visit met the established objectives of providing insights into the SAM implementation process at one CE plant, and areas where changes to the draft Tl will l be needed to accommodate the observed differences in implementation approaches. l However, the demonstration format does not allow sufficient time and flexibility to thoroughly evaluate the licensee's implementation.

In c!osing comments, Fred Emerson, NEl, reminded participants of the importance of keeping the priority of SAM implementation in line with the priorities of more important plant activities.

He stressed that utilities need to keep resources for SAM implementation and training in perspective with other activities, but given the commitment to complete implementation as an  !

industry initiative, the industry has a responsibility to do this well, and in a way that carries out the mandate that industry set for itself.

DISTRIBUTION w/ Attachments:

SCSB R/F (2) Central Files PDR MModes, RI KBarr, Ril JCreed,Rlli BMurray, RIV DISTRIBUTION w/o Attachments:

TCollins RGallo DDesaulniers CMiller JO'Brien RBarrett RHasselberg DMatthews DOCUMENT NAME: CALVERT.TRP

! Ta receivi e copy of this document, indicate in the box: "C* = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy

( OFFICE SCSB:DSSAfil3R,1 PERB:DF}f)M l f;. HHFB:DRCH , ln BC:SCSB:1)$$l l l NAME RPalla:bw /Y/A4M JO' Brier [/%. 9(pDDesaulniers MF CBerlingerl$/

f/ / /9ff DATE 1/3d98 (/4 /98 .5/ //98 / /98 OFFICIAL RECORD COPY

Attachment 1

) BGE Calvert Cliffs Nucl:ar Power Plant

Severa Accident Managemer.t D;.monstration  !

March 17* - 18*,1998

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Attachment 2 Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant Severe Accident Management Demonstration Iucuhn,m nhi f,19%

i dunction i enter TOPIC FACILITATOR TIME Welcome and Introductions .

BGE Management Comments Jim Lemons, Manager - NSSD 1:00 PM NRC Opening Comments Bob Palla, NRR NEI Opening Comments Fred Emerson, NEI Overview BGE Implementing Philosophy Tom Forgette, Director - EP 1:30 PM BGE Project Plan / Team Scott Henry, SAM Project Manager 1:40 PM Break 1:50 PM Evaluation of SAM Capabilities BGE Nuclear Program Scott Henry 2:00 PM BGE ERPERPIPsERO Greg Rudigier, Senior EP Analyst 2:10 PM CEOG GAMG Products / Process Scott Henry 2:35 PM Accident Management Training Scott Henry 2:45 PM IPE/IPEEE Considerations Bruce Mrmrca, PE - REU 2:50 PM Break ^ 3:00 PM Implementation of SAM Enhancements ~

SAMG Development Scott Henry 3:15 PM SAMG Interface with Site Processes Adapting GAMG to CCNPP ERPIPs Review ,

Training Assessment Approval Distribution Expected ERPERPIPERO Changes Greg Rudigier 4:00 PM Break 4:15 PM SAMG Maintenance 4:30 PM Training Josh Hardison, ERT Coordinator Drills Greg Rudigier Performance Assessment Lou Larragoite, Supy - OPSAU Day 2 Overview Greg Rudigier 5:00 PM Adjourn ' 5:30 PM

Baltimore Gas & Electric Company '

Calvert Cliffs Nuclear Power Plant Severe Accident Management Demonstration i

, n ednesda3, \ larch IN"',1998 Afeet at Education / Visitor Center 6:45 AAf Leavefor Office Training Facility (OTF) 7:00AAf Training Dri11 Activities - . Office Training Facility (OTF): Classrooms A,B,C Training Drill Brief 7:30 AM Training Drill 8:15 AM Debrief & Critique 10:15 AM

' Lunch: Edu::ation Center 'l1:30 AM -

i Closing Activities Education Center Discussion / Question & Answer Period SAAiTeam 12:30 PM Break ,

2:00 PM Closing Remarks 2:15 PM Guests NEI NRC BGE SAh! Team /BGE Afanagement Adjourn - 3:00 PM -

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. ERP ATTACHMENT 3-3 EMERGENCY ORGANIZATION Site Emergency Coordinator EOF Emergency Operations Centers (See Attch. 3-5)

Radiological Aaseemment Plant GeneralManager

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EOF T5C Off-Site Monitoring Team Security Coordinator EUF NSF 1 I Superintendent-Nuclear Ops TSC Director ShiA Supervisor. Reactor Core Engineers ShiA Tech Advisor Operations Analysis CR Staff Technical Analysis Plant Operators Computer Support CR TSC Chemistry Director - TSC Fire Brigade OSC Director TSC Vanous OSC l

I Radiation Protection Dir Engineering Director N Tm

""d""d"E**" On Site Monitoring OSC EWP Coordinator OSC Maintenance Teams Chemistry Teams Security Liaison First Aid Team NEF Director Assembly Area Leaders Fire Protection Spec.

Engineering Staff Assembly Areas Operations Team NEF Authority and Interface OSC j Position / Title location I

f I

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NITACHMENT 5-1 FACILITY FUNCTIONAL OBJECTIVES r;~ d. tn's~;_FACRJIY.

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3, . . 6, L Emergency Operations Facility (EOF) 1) Management of overall BOE response l

2) Coordmation of response activities with Federal, State and County agencies.
3) Coordmation of radiological and environmental assessment.
4) Determmation of rmi i.er.id protective actions.
5) Receipt and analysis of field ' monitoring data and coordmation of sample media.

Technical Support Center (TSC) 1) Provide plant management and analytical support to Operations personnel during emergency conditions.

2) Relieve reactor operators of peripheral duties and communications not directly related to reactor system manipulations.

l 3) Prevent congestion in the Control Room t

l

4) Perform EOF functions in Alert, Site and General l Emergency, until the EOF is functional.

Operational Support Center (OSC) 1) Provide and coordmate logistic support (i.e., maintenance, etc. to bring the plant to a safe, stable condition).

l l

2) Restrict Control Room access to personnel specifically I

requested by Shift Supervisor or General Supervisor Nuclear Operations.

l Nuclear Engineering Facility (NEF) 1) Provide and coordinate engineering support for OSC, TSC and EOF,

(

t Media Center 1) Provide media representatives with immediate access to l

accurate emergency related information, generated by all involved agencies.

2). Provide equipment for document reproduction, telecopying, communications, and television electrical connections.

Rev.22 m

BRP ',

ATTACHMENT 5-5 ,

CHARACTERISTICS OF TECHNICAL SUPPORT CENTER VS. EMERGENCY OPERATION (i.e. Control Room and Operational Suonort Center)

Control Room & Operational Support Center Technical Support Center

  • Activities performed by tramed, licensed operators
  • Activities performed by high level in the Control Room supported by OSC and NEF engmeering and management personnel.

staff. Supported by NEF staff.

  • Actions based on: * ' Actions based on:

- Specific procedures to assure success of safety - Accident management strategies derived functions (criticality control, core coverage, heat from likely paths to core melt and removal, containment) containment failure.

- Reaction to plant symptoms (flux, flows, - Anticipation of potential problems or pressures, temperatures) Phenomenon

  • Success-oriented (goal is to bring plan to a safe
  • Defensive strategy (do what is necessary to stable condition) save the core and contamment)
  • Limited number of options prescribed a Broad range of options in response to unfolding events
  • Strong incentives for adherence to procedures . Requires authority to overrule estabi':,hed procedures
  • Actions should be unambiguously beneficial
  • Actions may have negative side effects
  • Time for decisionmaking on order of minutes
  • Time for decisionmakmg on order of hours to days 1

Rev.22

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Attachment 4 CALVERT CLIFFS NUCLEAR POWER PLANT SEVERE ACCIDENT MANAGEMENT TABLE TOP DRILL FEBRUARY 19 THRU MARCH 18,1998 SEVERE ACCIDENT MANAGEMENT- 1

/ W 3/3/98 Gregory C.4(udigier Emergency Planmng Analyst i 'nt] 51318 Thomad E. Forgette Director-Emergency Planning

'M3 E Scoti A ' /

Nuclear Engineerin i Project Manager 3/13/98

  • O .

e.

SAM-1 TABLE-TOP DRILL i l

l Participating organizations (March 18th demonstration):

NEI NRC l APS

! BGE l~ CP&L l CPC FP&L I GPU l IP l NE l

NSP OPPD i PP&L l RG&E l SCE

. WEPCO 1 l Combustion Engmeering I Westinghouse

, NPP Goesgen I

Siemens l

L Drill Facilitators:

G. C. Rudigier Drill Coordinator ,

S. A. Henry TSC Controller / Evaluator M. L. Coon CR Controller / Evaluator l J. C. Kellum CR Controller / Evaluator l- C. G. Phifer Evaluator l C. J. Andrews Evaluator l

l L. D. Swindell Evaluator l

l Simulations:

All activities are simulated as a table top drill.

f 3/13/98

F 1 l

e SAM-1 TABLE TOP DRILL DRILL SCOPE The purpose of this drill is to provide members of the emergency response organization who are responsible for implementing Severe Accident Management ERPIPs the opportunity to practice the use of the procedures in a classroom setting under the  ;

direction of an instructor. l i

i l

The drill provides Implementes, Evaluators, and Decision-makers with an opportunity to develop skills needed to use the $/JJ ERPIPs in the event of a severe accident.

In this training setting, questions are encouraged and instruction and coaching are expected to take place. Participants are expected to work through the process and procedures discussed in the formal classroom setting that they attended prior to the table-top drill.

l The drill may be stopped at any time, as needed, by the controller / evaluators to provide instruction in a group setting where appropriate. .When the drill is resumed, the drill will proceed in scenario time to preserve the plant data sequence given in the time line.

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i 1-1 3/12/98

s l

SAM-1 TABLE TOP DRILL DRILL OBJECTIVES

1. Given access to SAM ERPIPs and given information and data specified in the scenario, the Evaluators will use the SAM ERPIPs to perform evaluations that are in turn provided to Decision Makers and Implementers for accident mitigation.
2. Determine which CHLAs are available and applicable under the scenario conditions.
3. Evaluate positive and negative aspects of applicable CHLAs and assess the effectiveness ofimplemented CHLAs.
4. Utilize effective communication techniques to coordinate emergency information among Evaluators, Implementers, and Decision Makers S. - Utilize effective command and control among Evaluators, Implementers and Decision makers.

1-2 3/12/98

)

1 SAM-1 TABLE TOP DRILL l PLAYER RULES

1. Licensed Operators document attendance on the LOR class roster, TSC and EOF

! members document attendance on LOR, ATTACHMENT 5 TRAINING COMPLETION

SUMMARY

2. Attendees fill out an ATTACHMENT C TRAINEE REACTION FORM to document l

l drill and process issues for SAM project resolution.

3. Linut conversation during the drill to task at hand while in the room. Peripheral conversations should take place in the hall to reduce noise factor. Avoid congregating at the refreshment table.

1

4. Only the SEC player should spend time on the EAL table and PARS. The SEC and the l EOF controller / evaluator may make up meteorological data for form completion.
5. Plant General Manager, TSC Director, Superintendent Nuclear Operations, and Shift Manager, players should avoid spending time on EALs, PARS and CDAs. Focus on the SAM ERPIPs. Do not spend time on other ERPIPs.
6. A participant at the Control Room table should make general announcements to all participants when it is appropriate to simulate a plant announcement.

l

7. The Control Room table should assign one player to handle phone communications on the Contrni Room phone and another on the TSC phone.
8. Participants that would not normally leave their post should communicate via the phone. Participants that leave their post may communicate face to face.

l l-3 3/13/98

.- -l e

SAM-1 TABLE TOP DRILL j PLAYER RULES

9. The training scenario is based on the IPE Summary report for Plant Damage State HRIF (Station blackout with total loss of main feedwater, isolated containment, no HPSI, no CS pumps, and no CACs ). Without mitigation, the core will melt through the vessel within three and a half hours. During the table top drill certain equipment l will be returned to service such that players can mitigate the consequences of the accident. 4
10. Ifit is prudent, the training drill may be interrupted by the Drill Coordinator for general discussion. The training drill will resume and follow the scenario time with a corrected clock (real time). If a player believes that a discussion is needed, notify the Drill Coordinator. These discussions should be limited to a maximum of ten minutes and should deal with the point or points at hand. The discussion should not be allowed to become a critique. The entire drill will be critiqued at its conclusion.

1-4 3/13/98

SAM-1 ASSUMPTIONS To create an exercise scenano, equipment malfunctions are requimd to facilitate the simulated accident.

Due to designed rehability and redundancy of safety systems, probable equipment malfunctions are difficult - 4

- to incorporate into a scenario, especially' where'they are needed to cause plant damage that leads to a severe j accident. M Updated Final Safety Analysis Report provides the analyzed capabilities of plant systems to maintain control over radioactive matenal within the plant during off-normal plant incidents. Thus, to incorporate malfunctions into a scenaric, ass ==aeinae must be made which are not consistent with design and analysis data. Public perception of an exercise scenario may lead to the belief that these events are probable, if the sequence of events presented in this scenario were probable, actions would be taken to rectify the situation.

.I In order to achieve a sequence of events forcing participant emergency response action, the following -

improbable events have been incorporated in the scenario design:

1. A station black out occurs.
2. The turbine driven auxiliary feed water system fails.
3. A mechanical failure of a main valve in the fire water hook-up line occurs.
4. Steam generators dry out.
5. Core uncovery occurs.
6. Severe core damage occurs.
7. Containment heat removal is initially unavadable.
8. High pressure safety injection is initially unavadable.

Reference- Calvert Cliffs Nuclear Power Plant Probabilistic Risk A + es =^

Section 4.3.8.2.3, Plant Damage State HRIF.

2-1 3/12/98

I f

SAM-1 GENERAL DESCRIPTION l

The scenario begms with Unit I at 100% power. Unit 2 is in Mode 6, day 35 of a 45 day refueling outage. 'Ibe National Weather Service has issued a tornado warnmg for the entire l Southern Maryland Region. Due to El Nino effects, potential tora =h are predicted to be severe. .

! j l Due to severe weather predictions, Calvert Cliffs has implemented ERPIP 3.0, T==~U=*a Actions l l

for Severe Weather. All actions are complete. 'Ihe TSC and other members of the ERO are I

staffed in accordance with ERPIP 3.0. Non<ssential personnel have been sent home.

2B DG is out of service due to inspection of its governor flyweight assembly. The inspection is a result of action taken on a vendor notice that states the governor flyweight assembly l may cause overspeed. IB DG is due for inspection following the retum of 2B DG to senice. 2A l l l has been inspected and found satisfactory. OC DG is out of service for parts removed to I A DG. l l

Parts for the OC DG are due from France next week. 33 AFW pump is tagged out of service and.

l disassembled for bearmg repla~maA Degraded packing was installed in 11 & 12 CS pumps. I1 l l l CS pump is tagged out of service for packmg replacement. 12 CS pump packmg was replaced but 12 CS pump failed to start for PMT. Electricians are investigating Disconnect 189-1106 is tagged open due to contact arm misalignment. The recently issued oil control manual listed the I wrong oil for the HPSI and Chargmg pumps. This was discovered when a bearmg on 13 Charging pump was wiped about I minute aAer start. 12 Chargmg pump oil has been changed. 12 HPSI is l

satisfactory. 11 and 13 Chargmg pumps and 11 and 13 HPSI pumps are currently tagged out of l service. 1I HPSI is due for oil change next.

l l

At scenario time -01:20, a severe tornado stnkes the switchyard and another strikes the SMECO tic line. All lines are down. I A DG starts and then shuts down on low lube oil pressure.

IB DG starts and then shuts down on overspeed A station blackout occurs on Unit 1. 11 & 12 AFW Pumps start and then trip on overspeed and will not reset. A mechanical failure of a valve in the fire water book up line occurs. Battery power is available to instruments. This event initiates a 3-1 3/13/98

i severe accident sequence on Unit I due to station blackout and total loss of feed water. 2A DG starts and loads.

At scenario time -01:05, Operations implements EOP-8, Functional Recovery Procedure.

The Site Emergency Coordinator in the TSC declares a Site Emergency for EAL, ESI-2, "EOP-8, Functional Recovery Procedure is implemented AND Station Blackout is ia*H by ANY of the following AND power is not restored to at least one safety related 4kV bus per unit within 15 minutes: loss of control room lighting on both Units,500 kV red and black bus power available light de-energized, diesel generators not loaded, all 4 kV unit bus power available lights de-energized." The EOF is staffed and operational.

At scenario time -00:50,11 and 12 steam generators go dry due to lack of feed water.

~

Steam generator level is sufficiently low such that heat transfer to the SG no longer will maintain -

RCS pressure below the safety valve setpoint. RCS pressure rises to safety valve set point. The safeties lift, the quench tank rupture disk fails, containment temperature, pressure and water level increase. Subcooling is at 0 degrees F. The concentration of steam in contamment increases.

Reactor vessel water level decreases rapidly to the top of the active fuel in the core.

At scenario time 00:00, the TSC enters SAM ERPIP 601 and begins evaluating the accident sequence in progress, the CETs indicate increasing core temperature. Contamment pressure rises to about 27 psig. There is no indication that containment failure has occurred during the event. Outside airborne radioactivity levels as measured by the Radiation Protection Director are normal. 'Ibe 1 A DG will become available in about 30 minutes.

3 3-2 3/13/98

1 i

I 1

l severe accident sequence on Unit I due to station blackout and total loss of feed water. 2A DG

! starts and loads.

l i-At scenario time -01:05, Operations implements EOP-8, Functional Recovery Procedure.

He Site Emergency Coordmator in the TSC declares a Site Emergency for EAL, ESI-2, "EOP-8, Functional Recovery Procedure is implemented AND Station Blackout is indicated by ANY of the following AND power is not restored to at least one safety related 4kV bus per unit within 15 minutes: loss of control room lighting on both Units,500 kV red and black bus power available i

hght deenergized, diesel generators not loaded, all 4 kV unit bus power available lights de-energized." ne EOF is staffed and operational.

At scenario time -00:50,11 and 12 steam generators go dry due to lack of feed water.

Steam generator level is sufficiently low such that heat transfer to the SG no longer will maintain i RCS pressure below the safety valve setpoint. RCS pressure rises to safety valve set point. The l safeties lift, the quench tank rupture disk fails, containment temperature, pressure and water level increase. Subcooling is at 0 degrees F. The concentration of steam in contamment increases.

Reactor vessel water level decreases rapidly to the top of the active fuel in the core.

At scenario time 00:00, the TSC enters SAM ERPIP 601 and begins evaluating the l accident sequence in progress, the CETs indicate increasing core temperature. Contamment pressure rises to about 27 psig. There is no indication that contamment failure has occurred during the event. Outside airborne radioactivity levels as measured by the RaAntion Protection Director j are normal. The 1A DG will become available in about 30 minutes.

3-2 3/13/98

s 4 CS pump by energizing 14 4kV bus may be substituted for 11 CS restoration. If 14 4kV bus is energized then 11 CS pump will not be available due to high radiation levels.

. He TSC staff and Operations will weigh the benefit of containment depressurization strategy by turning sprays on versus the likelihood of challenging the contamment integrity due to a potential hydrogen burn.

3-4 3/13/98

b-SAM-1 TIME LINE SCENARIO - EMERGENCY _

MESSAGE l TIME ' CLASS ~ ' EVENT DESCRIPTION: NUMBER

- (06:30) NONE - Present initial conditions to players 0

-01:30 Unit 1 is at 100% power.

- Unit 2 is in Mode 6, day 35 of a 45 day refueling outage.

Fuel shuffle completed.

A vendor notice has been issued that states the Woodward L governor flyweight assembly for the model used on the Fairbanks l Morse diesels may cause overspeed l

2B diesel is out of service for inspection of the governor flyweight assembly.

l . IB diesel is due for inspection of the governor flyweight assembly.

2A diesel has been inspected and found satisfactory.

OC diesel is out of service for parts removed to I A diesel. Parts for the OC diesel are due from France withm a week.

Disconnect 189 1106 is tagged open due to contact arm misalignment.

13 AFW pmnp is tagged out of service and disassembled for bearmg

_ replacement.

I1 and 13 Charging pumps are tagged out of senice (oil problem).

I 1 CS pump is tagged out of service for packmg replacement.

12 CS pump faded to start for PMT followmg packmg replacement.

I1 and 13 HPSI pumps are tagged out of service (oil problem). 1 The National Weather Service has issued a tornado warmng for all of Southem Maryland.

Severe weather preparations have been completed in acwid.se with

- ERPIP 3.0, Immediate Actions, Severe Weather Non-essential gic.ucsl have been sent home and told not to report to work until given notice.

_ All personnel have been recalled and assembled in accordance with ERPIP 3.0 LW=*a Actions, Severe Weather and are stationed l within safe areas of the plant.

l 4-1 3/12/98 l

SAM-1 TIME LINE SCENARIO: -EMERGENCY- . .

MESSAGE TIME #

CLASS 7 EVENT DESCRIPTION- NUMBER (06:40)

NONE The Technical Support Center (TSC) and Emergency Response

-01:20 c Orgamzation (ERO) is staffed in acevidi-ce with ERPIP 3.0, Imd** Actions, Severe Weather.

A tornado strikes the switch yard k= king down all transmission lines.

Reactor trips.

Loss of all feed water.

A second tornado strikes the SMECO tie line and knocks a line down.

, All offsite power lines are down.

l A diesel stans and then shuts down on low lube oil pressure.

IB diesel starts and then shuts down on overspeed.

2A diesel starts and picks up load.

I1 & 12 AFW pumps start and trip on overspeed and will not reset.

Any attempts to use fire water to feed the generators will not succeed due to a mechanical failure of valves in the fire water hook up alignment.

Battery power is available to instruments.

(06:55) SITE Station blackout and loss of feed water exists on Unit 1

-01:05 EMERGENCY Operations implements EOP-8, Functional Recovery Procedure.

The Site Emergency Coordmator relieves the control room of ERPIP responsibilities.

Expected Action: Declare Site Err igeq for ES1, EOP-8, Functional Recovery Procedure is implemented and station blackout is indicated by any of the following and power is not restored to at least one safety related 4kV bus per unit within 15 minutes: loss of control room lightmg on both units, 500 kV red and black bus power available lights d:-u~.4 zed, desel generators not loaded, all 4 kV unit bus power available lights de-energized.

Expected Action: EOF is~ staffed.

4-2 3/12/98

lt SAM-1 TIME LINE SCENARIO - EMERGENCY MESSAGE TIME - CLASS. - EVENT DESCRIPTION NUMBER

- (07:10) SITE RCS pressure increases to the safety valve set point.

1. -00:50 EMERGENCY I L 11 and 12 Steam Generators boil dry due to loss of all feed water j Quench tank rupture disk fails.

Containment pressure increases.

3 Contamment temperature increases.

Containment water levelincreases. I RCS level decreases and core uncovers (07:50) SITE Table top drill participants take their places, open procedures

-00:10 -EMERGENCY and prepare for drill to commence. Time 00:10 data is posted Time 00:00 data is not posted so as to allow adequate set-up time and orientation dikussion before data evaluations are required.

(08:00) SITE The TSC enters SAM ERPIP 601 and evaluates the accident 00:00 EMERGENCY in progress.

Outside airborne radiation levels are normal as read by the Radiation Protection Director (RPD).'

1 A diesel will be available in about 30 minutes.

(08:10) SITE RVLMS alarm at 10".

00:10 EMERGENCY CETs at 1075 Contamment High Range Radiation Monitor (CHRRM)at 2000 rem /h

- Expected Action: EOP-8, Safety function status checks.

4-3 3/12/98

/

SAM-1 TIME LINE SCENARIO.l ..-EMERGENCY- ..

MESSAGE

' TIME :

/ CLASS. 1 EVENT DESCRIPTION NUMBER (08:15) GENERAL Subcooled margin is at 0 degrees F.

00:15 EMERGENCY 4 CETs reach 1200 degrees F.

Outside radiation levels are nom as read by RPD. 1 Expected Action: Declare General Emergency for BGl, Loss of two fission product barriers and potential loss of a third barrier.

(08:25) GENERAL RVLMS alarm at 10" 00:25 EMERGENCY CETs at 1750 degrees F

' CHRRM at 7000 rem /h WRNGM at 2000 uCi/s ,_ ~ ,

Expected Action: Thr'ISC i:: p(nete the_use.of Auxiliary v Feed Water via]) AFJ pump (2A DG to'24, bus).'

s. 2 n v .,_m. . -

(08:40) GENERAL RVLMS alarm at 10".

00:40 EMERGENCY CETs at 2300 degrees F CHRRM at 30000 rem /h WRNGM at 2000 uCi/s Expected Action: The TSC and Operations will evaluate y feedmg the SG s with auxiliary feed water to mitigate SG tube creep rupture concerns. '

ppf5 (

.f 5.

py/] yfy s pt 4/

v g, y ., g /,

u .- n a Yc m' ,

}'b W /

90 11 g ,, s 'P ,

,p i "

@ p'i,

{ 0 tI '

qplv

, ,.,i,

}4 (p D 4-4 3/12/98

l SAM-1 TIME LINE ]

1 SCENARIO JEMERGENCY, MESSAGE  ;

TIME ' CLASS EVENT DESCRIPTION NUMBER 1

(08:46) GENERAL 1 A dieselis available. 2  ;

' 00:46 EMERGENCY PORV 402 opens when 11 bus is re-energized (unless prevented by operations).

I1 and 12 AFW pump repairs are completed, SGs are dry.

RVLMS alarm at 10" CETs at 2300 degrees F  !

CHRRM at 40000 rem /h WRNGM at 2000 uCi/s l- Expected Action: TSC and Operations will evaluate RCS depressurization strategy using the PORV to avoid a high pressure core melt ejection (HPME). 1 (08:47) 4 GENERAL PORV 402 is available; PORV 404 does not open.-

00:47 EMERGENCY l

(08:55) GENERAL RVLMS alarm at 10". ,

)

00:55 EMERGENCY CETs at 2300 degrees F CHRRM at 60000 rem /h WRNGM at 2000 uCi/s .

13 AFW expected back in about 10 minutes. 3 i

FWW Action: TSC and Operations evaluates alternate , -

electrical and water source line ups. ,

t t

4-5 3/12/98 x,

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SAM-1 TIME LINE 1 SCENARIO. EMERGENCY.. .

MESSAGE TIME -CLASS-EVENT DESCRIPTION NUMBER

! GENERAL- 13 AFW pump is available. 4 (09:07)?

. 01:07 EMERGENCY RVLMS alarm at 10" CETs at 2300 degrees F l -.

l CHRRM at 80000 rem /h l

i' WRNGM at 2000 uCi/s

. (09:10) GENERAL RVLMS alarm at 10".

01:10 EMERGENCY CETs at 2300 degrees F 4 l CHRRM at 90000 rem /h l

L WRNGM at 2000 uCi/s AFW flowis restored.

'~

l Expected Action: The TSC and Operations evaluates

initiation of feed flow.

j_ s Expected Action: Operations initiates auxiliary feed flow at a redu'ced rate since both SG s are dry.

(09:20) GENERAL 11/12 HPSI expected back in 30 minutes. 5 01:20 EMERGENCY (12 HPSI if attempting 13 kV backfeed)

RVLMS alarm at 10" CETs at 2300 degrees F CHRRM at 100000 rem /h Expected Action: TSC and Opesations will evaluate the use of 11/12 HPSI for RCS injection to facilitate core quench.

(09:35) - . GENERAL RVLMS alann at 10" 01:35 EMERGENCY CETs at 2300 degrees F CHRRM at 100000 ran/h WRNGM at 2000 uCi/s 46 3/12/98 1 l

c  :

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SAM-1 TIME LINE l SCENARIO : EMERGENCY. MESSAGE l ' TIME CLASS ' EVENT DESCRIPTION NUMBER (09:47) GENERAL 11/12 HPSIis available. 6 01:47 EMERGENCY RVLMS alarm at 10" l

! i i CETs at 2300 degrees F l CHRRM at 100000 rem /h l

!' WRNGM at 2000 uCi/s i

(09:50) GENERAL 11/12 CS pump expected to be returned to service in about 7 l 01:50 . EMERGENCY 15 minutes ( 12 CS pump will be available if 13 kV backfeed l option is used).

RVLMS alarm at 10" l

CETs at 2300 degrees F CHRRM at 100000 rem /h l

l WRNGM at 2000 uCi/s

! Expected Action: TSC and Operations will evaluate the use of containment spray to facilitate containment heat removal.

1 (10:07) GENERAL 11/12 CS pump is available. 8 02:07 EMERGENCY RVLMS alarm at 10" CETs at 2300 degrees F CHRRM at 100000 rem /h

WRNGM at 2000 uCi/s

_s

\

Expected Action: TSC and Operations will weigh the benefit of contamment depressurization strategy by turning sprays on

[versus the likelihood of challengmg the contamment integrity due ,

to a pwM hydrogen burn. -

m a- - - . . - , _ - ._

(10:30) GENERAL TERMINATE DRILL 02:30 EMERGENCY 4-7 3/12/98

SAM-1 TIME LINE

- NOTES -

1. ' Classification is given in scenario time line as an expected action at the time actual criteria exist for the l

appropriate EAL. The actual tmung of the performance of declaration of a classification is expected to occur sometime aAerwards due to the time required to rengnie the event, review the criteria, arrive at a l--

l conclusion and initiate documentation.-

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l 4-8 3/12/98 i

SAM-1 MESSAGES l

MMEwaa:gACTUAL;nc 6:30mmasssa e ,.ada , MESSAGE NOtadei .aamaa ,

D*?""'"? SCENARIOsf01i30T""*"""**""!CONTROLLERi~ Cisdinat6r '

TO: All Players LOCATION: Control Room , EOF, and TSC Tables 1

MESSAGE: Plant initial conditions from time line distributed. l Attached equipment status sheet distributed.

CONTROLLER NOTE: This informs. tion is distributed before the drillis conducted.

"" THIS IS A DRILL ""

5-1 3/12/98

V SAM-1 MESSAGES

TIME;L w,dACTUAL;6408;152assasu . ,auMESSAGE NO;sg
li. am.a ;u
yp sm*****SCENARIGF 00i150*""" """*" TCONTROLLERi 1TSCCin6eBsFi 3

/

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TO: TSC LOCATION: TSC Table MESSAGE: Upon request from TSC for outside radiation levels from the Radiation Protection Director.

Outside radiation levels are nonnal.

CONTROLLER NOTE: This information is applicable throughout the drill.

"" THIS IS A DRILL ""

5-2 3/13/98

~ l 1

SAM-1 MESSAGES TIMEL,agaAw OAL;adM;hn _, , waaaMESSAGE NO;m62;;a,s. . .m

~

F:P? ISCENARIOiW467^" " ' ""TCONTROLLERil" 3CR' Con 6sueE9 I

TO: Control Room l

LOCATION: Control Room Table MESSAGE: l A Diesel is available.

l CONTROLLER NOTE:

1 I

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"" THIS IS A DRILL ""  !

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5-3 3/12/98 l l

1

SAM-1 MESSAGES

!TIMEnd3CTUAL;;n08$5bnas;2,uguaaMESSAGE NOh:3 A;a u s s c a ss' pr 3epmeemp gggggpa-w" *?""TCONTROLLERi"ECR C$E6sBeFF TO: Control Room LOCATION: Control Room Table MESSAGE: 13 AFW pump expected back in about 10 minutes.

Bearing replacement has been completed Clearing tags.

CONTROLLER NOTE:

1

"" THIS IS A DRILL ""

5-4 3/12/98

{

SAM-1 MESSAGES

!TIMEGaudALTs)ALta2#:07ja uammag: MESSAGE N06JA2=usu.=eua . .

gmm9?E'MESCENARIOff01ie751****"*55CONTROLLERFCR"C6iisiillei""" "'

1 I

l TO: Control Room LOCATION: Control Room Table MESSAGE: 13 AFW pump is available.

l CONTROLLER NOTE:

i l

"" THIS IS A DRILL "" '

I I i

5-5 3/12/98

l l

l SAM-1 MESSAGES i

)

,Miega ; ACTUAL:lxt09:20L;t 5 ua # MESSAGE NO::;;;5;stu .m ee.,

ge<megnerggggggpy pe w, TCONTROLLERiFCR C aiifMF?"

TO: Control Room LOCATION: Control Room Table MESSAGE: 11/12 HPSI is expected back isi about 30 minutes.

(12 HPSI if attempting 13 kV';ackfeed)

CONTROLLER NOTE:

l l

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s

"" THIS IS A DRILL ""

\

5-6 3/12/98

SAM-1 MESSAGES 31MEmmdACTUAL:eg89:4bu, u iMESMGE.NO:g62cmo .uua m.e p"*""~ "'

""""SCENARIOi?'ellW'""""" "?CONTROLLERiTCR CoiissniBi" '

TO: Control Room LOCATION: Control Room Table l

MESSAGE: 11/12 HPSIis available. I l

)

CONTROLLER NOTE:

"" THIS IS A DRILL ""

5-7 3/12/98

SAM-1 MESSAGES TIME: ;m;;ACTUALuffo9,$02 acuc= laMESSAGENO: Aa - o mm , a

~

p w iSCENWFMs5fi~ ' ""*"*TCONTROLLERif'CR"CoashBiFF" ""

TO: Control Room LOCATION: Control Room Table MESSAGE: 11/12 CS pump expected back in about 15 minutes.

(12 CS pump will be available if 13 kV backfeed option is used)

CONTROLLER NOTE:-

"" THIS IS A DRILL ""

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5-8 3/12/98

I SAM-1 MESSAGES STIME:x utACTUAL:gg10:0L ,waue,asseMEMAGE.NO:118L s amm ,, maa pmen; #fMNh*MF "W?

  • FCONTROLLERi%CR CsideneF1" "^"

l TO: Control Room )

i LOCATION: Control Room Table

)

i MESSAGE: 11/12 CS pump is available. i i

Q i

i CONTROLLER NOTE:  !

l 9

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  • "* THIS IS A DRILL "" l l

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5-9 3/12/98

b EQUIPMENT STATUS SHEET (X) THROUGH THE COMPONENT NUMBER MEANS NOT AVAILABLE HPSI k 12 k

LPSI 11 12 CHARGING

[ 12 k

Arw X X X ==

CNTMNT SPRAY SALTWATER 11 12 13 SERVICE WATER 11 12 13 COND. 11 12 13 COND. BOOSTER 11 12 13 CCW 11 12 13 DGs K  % 2A k k 500KV HI LINES  %  % M 13KV P-13000-1 S P-13000-2 OUT OF SERVICE EQUIPMENT 13 AFW PUMP - BEARING REPLACEMENT 11 CNMNT SPRAY - PACKING REPLACEMENT 28 DG - GOVERNOR FLYWElGHT INSPECTION OC DG - PARTS USED FOR 1 A .

11 CHARGING PUMP - CHANGE OlL 13 CHARGING PUMP - BEARING REPLACEMENT >

11 HPSI PUMP - CHANGE OlL 13 HPSI PUMP - CHANGE OIL DISCONNECT 189-1106 - CONTACT ARM MISALIGNED 12 CS PUMP - FAILED TO START FOR PMT 1

I

SAM-1 OPERATIONAL DATA ,

SCENARIO TIME: 00:10 REAL TIME: 08:10 j PLANTPARAMETERS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 2475 psia CETs TI-131 A-D 1975 degrees F SUBCOOLING AI-11,12 0 degrees F RVIAtS LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE 11-106, 108 OOS degnes F CONTAINMENT PRESSURE PI-5307,5310 (WR) 27 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 257 degrees F CONTAINMENT SUMP LEVEL LI-4146,4147 8 inches l

CONTAINMENT RADIATION RI-5317 A, B 2000 run/h l CONTAINMENT HYDROGEN 0 AR-6527 0 percent

=

AUX FEED (e.g. FIC-4511A) 0 gym STEAM GENERATOR LEVEL LIC-1114C,1114D -400 inches STEAM GENERA 1DR PRESSURE PI-1013A-D,1023A-D 25 psig CST LEVEL LIA-5610,5611,5603 35 feet SI FLOW FI-351 0 gpm CHARGING FIDW FI-212 0 gpm RWT LEVEL LIA-4341,4342 39 feet

SAM-1 OPERATIONAL DATA SCENARIO TIME: 00:15 REAL TIME: 08:15 PLANT PARAMETERS VALUE UNITS ,

RCS PRESSURE PI-100 A-D, PI-103 2505 psia CETs TI-131 A-D 1200 degrees F SUBCOOLING AI-11,12 0 degnes F RVIMS LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,'108 OOS degrees F I CONTAINMENT PRESSURE . PI-5307,5310 (WR) 28 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 258 deg nes F CONTAINMENT SUMP LEVEL LI-4146,4147 8 inches CONTAINMENT RADIATION RI-5317 A, B 3000 rem /h CONTAINMENT HYDROGEN 0-AR-6527 0 percent AUX FEED (e.g. FIC 4511A) 0 gym STEAM GENERNIOR LEVEL LIC-1114C,1114D -400 inches STEAM GENERA'IOR PRESSURE PI-1013A-D,1023A-D 25 psig CST LEVEL LIA-5610,5611,5603 35 feet SI FIDW FI-351 0 gym CHARGING FIDW FI-212 0 gym RWT LEVEL LIA-4341,4342 39 feet' 1

h SAM-1 OPERATIONAL DATA i

SCENARIO TIME: 00:20 REAL TIME: 08:20 i PLANT PARAMETERS VALUE UNITS l

l RCS PRESSURE PI-100 A-D, PI-103 2495 psia CETs TI-131 A-D 1450 deg mes F SUBCOOLING AI-11,12 0 degrees F l

RVIAfS . LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F CONTAINMENT PRESSURE PI-5307,5310 (WR) 28.5 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 258 degrees F CONTAINMENT SUMP LEVEL LI-4146,4147 8 inches CONTAINMENT RADIATION RI-5317 A, B 5000 rem /h  !

CONTAINMENT HYDROGEN 0 AR-6527 0.5 percent AUX FEED (e.g. FIC-4511A) 0 gym STEAM GENERATOR LEVEL LIC-1114C,1114D -400 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 25 psig )

CST LEVEL LIA-5610,5611,5603 35 feet l SI FLOW FI-351 0 gym CHARGING FLOW FI-212 0 gym RWT LEVEL LIA-4341,4342 39 feet

SAM-1 OPERATIONAL DATA SCENARIO TIME: 00:25 REAL TIME: 08:25 PLANT PARAMETERS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 2500 psia CETs TI-131 A-D 1750 degnes F SUBCOOLING AI-11,12 0 degrees F RVIAfS LI-20A,20B 10"ON oft /ou PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F CONTAINMENT PRESSURE PI-5307,5310 (WR) 28.5 psig

^

CONTAINMENT TEMPERATURE TI-5309(DOME) 258 degrees F CONTAINMENT SUMP LEVEL LI-4146,4147 8 inches CONTAINMENT RADIATION RI-5317 A, B 7000 rem /h CONTAINMENT HYDROGEN 0-AR-6527 0.7 percent AUX FEED (e.g. FIC-4511A) 0 gym STEAM GENERA'IOR LEVEL LIC-1114C,1114D -400 inches STEAM GENERA'IOR PRESSURE PI-1013A-D,1023A-D 25 psig CST LEVEL LIA-5610,5611,5603 35 feet SI MDW FI-351 0 gpm CHARGING FIDW FI-212 0 gom RWT LEVEL LIA-4341,4342 39 feet l

o.

SAM-1 OPERATIONAL DATA I

1 SCENARIO TIME: 00:30 REAL TIME: 08:30 l PLANT PARAMETERS VALUE UhTrS l

l RCS PRESSURE PI-100 A-D, PI-103 2495 psia l CETs TI-131 A-D 2050 degrees F SUBCOOLING AI-11,12 0 degrees F RVIMS LI-20A,20B 10"ON off/on PORY TAIL PIPE TEMPERATURE TI-106,108 OOS degnes F l

CONTAINMENT PRESSURE PI-5307,5310 (WR) 29 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 260 degrees F CONTAINMENT SUMP LEVEL LI-4146,4147 8 inches CONTAINMENT RADIATION RI-5317 A, B 10000 nm/h CONTAINMENT HYDROGEN 0 AR-6527 1.2 percent AUX FEED (e.g. FIC-4511A) 0 gym STEAM GENERATOR LEVEL LIC-1114C, J114D -400 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 25 psig CST LEVEL LIA-5610,5611,5603 35 feet SI FIDW FI-351 0 gpm CHARGING FIDW FI-212 0 gpm RWT LEVEL LIA-4341,4342 39 feet

1

l l

SAM-1 OPERATIONAL DATA I SCENARIO TIME: 00:35 REAL TIME: 08:35 PLANT PARAMETERS VALUE UhTTS RCS PRESSURE PI-100 A-D, PI-103 2498 psia CETs TI-131 A-D 2300 degrees F SUBCOOLING AI-11,12 0 degnes F RVLMS LI-20A,20B 10"ON off/on FORY TAIL PIPE TEMPERATURE TI-106,108 OOS degnes F CONTAINMENT PRESSURE PI-5307,5310 (WR) 29 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 261 degrees F CONTAINMENT SUMP LEVEL LI-4146,4147 8 inches CONTAINMENT RADIATION RI-5317 A, B 20000 n m/h CONTAINMENT HYDROGEN 0 AR 6527 1.5 perrent AUX FEED (e.g. FIC-4511A) 0 gpm STEAM GENERATOR LEVEL LIC-1114C,1114D -400 inches STEAM GENERA'IDR PRESSURE PI-1013A-D,1023A-D 25 psig CST LEVEL LIA-5610,5611,5603 35 feet SI FLOW FI-351 0 gpm CHARGING FIDW FI-212 0 gym RWT LEVEL LIA-4341,4342 39 feet l

l l

___________m

54 SAM-1 OPERATIONALDATA SCENARIO TIME: 00:40 REAL TIME: 08:40 PLANT PARAMETERS VALUE USTrS RCS PRESSURE PI-100 A-D, PI-103 2502 psia l

CETs TI-131 A D 2300 degrees F l SUBCOOLING AI-11,12 0 degrees F RVIAfS LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F CONTAINMENT PRESSURE ' PI-5307,5310 (WR) 29 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 260 degries F CONTAINMENT SUMP LEVEL LI-4146,4147 8 inches CONTAINMENT RADIATION RI-5317 A, B 30000 rem /h CONTAINMENT HYDROGEN 0 AR-6527 1.7 pertent AUX FEED (e.g. FIC-4511A) 0 gpm STEAM GENERA'IOR LEVEL LIC-1114C,1114D -400 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 25 psig CST LEVEL LIA-5610,5611,5603 35 feet SIFLOW FI-351 0 gpm CHARGING FIDW FI-212 0 gym RWT LEVEL LIA-4341,4342 39 feet

SAM-1 OPERATIONAL DATA SCENARIO TIME: 00:45 REAL TIME: 08:45

]

PLANT PARAMETERS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 2495 psia CETs TI-131 A-D 2300 degrees F SUBCOOUNG AI-11,12 0 4wF RVIMS LI-20A,20B 10"ON off/on FORV TAIL PIPE TEMPERATURE TI-106,108 OOS degnes F CONTAINMENT PRESSURE PI-5307,5310 (WR) 29.5 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 261 degnes F CONTAINMENT SUMP LEVEL LI-4146,4147 8 inches CONTAINMENT RADIATION RI-5317 A, B 40000 n m/h CONTAINMENT HYDROGEN 0 AR-6527 1.9 percent AUX FEED (e.g. MC-4511A) 0 gym STEAM GENERATOR LEVEL LIC-1114C,1114D -400 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 25 psig CST LEVEL LIA-5610,5611,5603 35 feet SI FIDW M-351 0 gpm CHARGING FLOW FI-212 0 gpm RWT LEVEL LIA-4341,4342 39 feet

.. 1 SAM-1 OPERATIONAL DATA SCENARIO TIME: 00:50 REAL TIME: 08:50 PLANT PARAMETERS VALUE UNITS RCS 1RESSURE PI-100 A-D, PI-103 2095 psia CETs TI-131 A-D 2300 degnes F SUBCOOIJNG AI-11,12 0 degnes F RVLMS Il-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F l CONTAINMENT PRESSURE PI-5307,5310 (WR) 31 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 265 degrees F CONTAINMENT SUMP LEVEL LI-4146,4147 8.5 inches CONTAINMENT RADIATION RI-5317 A, B 50000 rem /h CONTAINMENT HYDROGEN 0 AR-6527 2.1 percent AUX FEED (e.g. FIC-4511A) 0 gym STEAM GENERATOR LEVEL LIC-1114C,1114D -400 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 25 psig CST LEVEL LIA-5610,5611,5603 35 feet SI FIDW FI-351 0 gpm CHARGING FIDW FI-212 0 gpm RWT LEVEL LIA-4341,4342 39 feet

SAM-1 OPERATIONAL DATA SCENARIO TIME: 00:55 REAL TIME: 08:55 PLANT PARAMETERS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 1495 psia CETs TI-131 A-D 2300 degnes F SUBCOOUNG AI-11,12 0 degrees F RVLMS U-20A, 20B 10"ON off/on PORY TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F CONTAINMENT PRESSURE PI-5307,5310 (WR) 33 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 268 degnes F CONTAINMENT SUMP LEVEL U-4146,4147 8.5 inches CONTAINMENT RADIATION RI-5317 A, B 60000 run/h CONTAINMENTIIYDROGEN 0-AR-6527 2.3 pertent AUX FEED (e.g. FIC-4511A) 0 gym STEAM GENERA'IOR LEVEL UC-1114C,1114D -400 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 25 psig CST LEVEL UA-5610,5611,5603 35 feet SI FLOW FI-351 0 gpm CHARGING FIDW FI-212 0 gpm RWT LEVEL LIA-4341,4342 39 feet

(:

SAM-1 OPERATIONAL DATA l

SCENARIO TIME: 01:00 REAL TIME: 09:00 PLANT PARAMETERS VALUE UNITS l RCS PRESSURE PI-100 A-D, PI-103 995 psia 1

CETs TI-131 A-D 2300 degreesF SUBCOOLING AI-11,12 0 degrees F l

RVIMS LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F CONTAINMENT PRESSURE PI-5307,5310 (WR) 35 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 270 degrees F CONTAINMENT SUMP LEVEL LI-4146,4147 8.5 inches CONTAINMENT RADIATION RI-5317 A, B 70000 run/h CONTAINMENT HYDROGEN 0-AR-6527 2.5 percent AUX FEED (e.g. FIC-4511A) 0 gpm STEAM GENERA'IVR LEVEL LIC-1114C,1114D -400 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 25 psig CST LEVEL LIA-5610,5611,5603 35 feet SI FLOW FI-351 0 gpm CHARGING FIDW FI-212 0 gym RWT LEVEL IJA-4341,4342 39 feet I

i

SAM-1 OPERATIONAL DATA I

i I

SCENARIO TIME: 01:05 REAL TIME: 09:05 PLANTPARAMETERS VALUE UhTTS l RCS PRESSURE PI-100 A-D, PI-103 600 psia CETs TI-131 A-D 2300 degreesF SUBCOOLING AI-11,12 0 degnes F RVLMS LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F CONTAINMENT PRESSURE PI-5307,5310 (WR) 37 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 272 degnes F CONTAINMENT SUMP LEVEL LI-4146,4147 8.5 inches CONTAINMENT RADIATION RI-5317 A, B 80000 nan /h CONTAINMENT HYDROGEN 0-AR-6527 2.7 pertent AUX FEED (e.g. FIC-4511A) 0 gprn STEAM GENERATOR LEVEL LIC-1114C,1114D -400 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 25 psig CST LEVEL LIA-5610,5611,5603 35 feet SI FIDW FI-351 0 gpm CHARGING FLOW FI-212 0 sprn RWT LEVEL LIA-4341,4342 39 feet 1

)

SAM-1 OPERATIONALDATA l

SCENARIO TIME: 01:10 REAL TIME: 09:10 PLANT PARAMETERS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 375 psia i CETs TI-131 A-D 2300 degnes F l SUBCOOUNG - AI-11,12 0 degrees F l

RVIMS U-20A, 20B 10"ON off/on i

! PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F j CONTAINMENT PRESSURE PI-5307,5310 (WR) 38.5 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 274 degnes F i

CONTAINMENT SUMP LEVEL U-4146,4147 8.5 inches 1 CONTAINMENT RADIATION RI-5317 A, B 90000 nun /h CONTAINMENT HYDROGEN 0 AR-6527 2.9 percent i AUX FEED - (e.g. MC-4511A) 150 gym STEAM GENERATOR LEVEL UC-1114C,1114D -395 inches .

l STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 600 psig  !

1 CST LEVEL UA-5610,5611,5603 35 feet l SIFIDW M-351 0 gym l CHARGING FIDW FI-212 0 gpm RWT LEVEL UA-4341,4342 39 feet i

i I

SAM-1 OPERATIONAL DATA SCENARIO TIME: 01:15 REAL TIME: 09:15 PLANTPARAMETERS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 300 psia CETs TI-131 A-D 2300 deg nes F 4 i

SUBCOOLING AI-11, 72 0 deg nes F RVIMS LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F CONTAINMENT PRESSURE PI-5307,5310 (WR) 40 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 277 degnes F CONTAINMENT SUMP LEVEL LI-4146,4147 8.5 inches CONTAINMENT RADIATION RI-5317 A, B 100000 nun /h CONTAINMENT HYDROGEN 0-AR-6527 3.1 percent AUX FEED (e.g. FIC-4511A) 550 gpm STEAM GENERATOR LEVEL LIC-1114C,1114D' -335 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 400 psig CST LEVEL LIA-5610,5611,5603 34.5 feet SI F7AW ,

FI-351 0 gpm CHAkG'AG FLOW FI-212 0 gpm RWT LEVEL LIA-4341,4342 39 feet

..___m..__... . . . . _ . _ _ . . . . . . _ -- - - - - - - + . - - - . . .

-. . = - . - . .. -- . . . . . - -

SAM-1 OPERATIONAL DATA l'

SCENARIO TIME: 01:20 REAL TIME: 09:20 PLANT PARAMETERS VALUE UNITS .

1 RCS PRESSURE PI-100 A-D, PI-103 320 psia CETs TI-131 A-D 2300 degnes F SUBCOOIJNG AI-11,12 0 degnes F RVLMS LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degnes F l CONTAINMENT PRESSURE PI-5307,5310 (MR) 40 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 278 degrees F CONTAINMENT SUMP LEVEL LI-4146,4147 8.5 inches CONTAINMENT RADIATION RI-5317 A, B 100000 n m/h CONTAINMENT HYDROGEN 0 AR-6527 3.3 pertent AUX FEED (e.g. FIC-4511A) 550 gym  !

l STEAM GENERATOR LEVEL LIC-1114C,1114D -275 inches j STEAM GENERATOR PRESSJRE PI-1013A-D,1023A-D 350 psig CST LEVEL LIA-5610,5611,5603 34 feet SIFIDW FI-351 0 gym ,

1 CHARGING FLOW FI-212 0 gpm  ;

RWT LEVEL LIA-4341,4342 39 feet  !

l l

SAM-1 OPERATIONAL DATA SCENARIO TIME: 01:25 REAL TIME: 09:25 PIANT PARAMETERS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 305 psia CETs TI-131 A-D 2300 degrees F SUBCOOLING AI-11,12 0 degnes F RVLMS LI-20A,20B 10"ON off/on PORY TAIL PIPE TEMPERATURE TI-106,108 OOS degnes F CONTAINMENT PRESSURE PI-5307,5310 (WR) 41 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 278 degnes F CONTAINMENT SUMP LEVEL LI-4146,4147 8.5 inches CONTAINMENT RADIATION RI-5317 A, B 100000 ran/h CONTAINMENT HYDROGEN 0 AR-6527 3.5 pertent AUX FEED (e.g. FIC-4511A) 550 gprn STEAM GENERATOR LEVEL LIC-1114C,1114D -215 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 300 psig CST LEVEL LIA-5610,5611,5603 33.5 feet SI FLOW FI-351 0 gpm CHARGING FIDW FI-212 0 gym  !

RWT LEVEL LIA-4341,4342 39 feet

SAM-1 OPERATIONAL DATA SCENARIO TIME: 01:30 REAL TIME: 09:30 l PLANT PARAMETERS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 295 psia l CETs TI-131 A-D 2300 degrees F l SUBCOOLING AI-11,12 0 degrees F RV1MS LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degnes F CONTAINMENT PRESSURE PI-5307,5310 (WR) 41 psig  !

l l

l CONTAINMENT TEMPERATURE TI-5309(DOME) 278 degries F !

l CONTAINMENT SUMP LEVEL LI-4146,4147 8.5 inches i i CONTAINMENT RADIATION RI-5317 A, B 100000 n m/h CONTAINMENT HYDROGEN 0 AR-6527 3.7 percent AUX FELD (e.g. FIC-4511A) 550 gym STEAM GENERATOR LEVEL LIC-1114C,1114D -155 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 300 psig CST LEVEL LIA-5610, 5611,5603 33 feet l

SI FIhW FI-351 0 gym CHARGING FIDW FI-212 0 gym RWTh2 VEL LIA-4341,4342 39 feet l

l 1

I

SAM-1 OPERATIONAL DATA I

SCENARIO TIME: 01:35 REAL TIME: 09:35 PLANT PARAME1TRS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 295 psia CETs TI-131 A-D 2300 degrees F SUBCOOUNG AI-11,12 0 degrees F RVIAIS LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degnes F CONTAINMENT PRESSURE PI-5307,5310 (WR) 41 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 278 degrees F CONTAINMENT SUMP LEVEL LI-4146,4147 8.5 inches CONTAINMENT RADIATION RI-5317 A, B 100000 run/h CONTAINMENT HYDROGEN 0 AR-6527 3.7 percent AUX FEED (e.g. FIC-4511A) 550 gpm STEAM GENERA'IDR LEVEL LIC-1114C,1114D -95 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 300 psig CST LEVEL LIA-5610,5611,5603 32.5 feet SI FIDW FI-351 0 gym CHARGING FLOW FI-212 0 gym RWT LEVEL LIA-4341,4342 39 feet

, I SAM-1 OPERATIONAL DATA SCENARIO TIME: 01:40 REAL TIME: 09:40 _

PIANT PARAMETERS VALUE UNITS ___

RCS PRESSURE PI-100 A-D, PI-103 298 psia CETs TI-131 A-D 2300 degnes F SUBCOOUNG AI-11,12 0 degrees F RVLMS U-20A, 20B 10"ON off/on PORV TAIL PIPE TEMnPERATURE TI-106,108 OOS degnes F CONTAINMENT PRESSURE PI-5307,5310 (WR) 41 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 278 degrees F CONTAINMENT SUMP LEVEL U4146,4147 8.5 inches CONTAINMENT RADIATION RI-5317 A, B 100000 rem /h CONTAINMENT HYDROGEN 0-AR-6527 3.7 percent AUX FEED (e.g. FIC-4511A) 550 gym STEAM GENERA'IDR LEVEL UC-1114C,1114D -35 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 250 psig CST LEVFl, UA-5610,5611,5603 32 feet SI FLOW FI-351 0 gym CHARGING FLOW FI-212 0 gpm RWT LEVEL LIA-4341,4342 39 feet

1 SAM-1 OPERATIONAL DATA ,

1 l

SCENARIO TIME: 01:45 REAL TIME: 09:45 PLANT PARAMETERS VALUE UNITS J

RCS PRESSURE PI-100 A-D, PI-103 295 psia CETs TI-131 A-D 2300 degries F SUBCOOIJNG AI-11,12 0 degreesF RVLMS LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F CONTAINMENT PRESSURE PI-5307,5310 (WR) 40 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 276 degrees F CONTAINMENT SUMP LEVEL LI-4146,4147 8.5 inches CONTAINMENT RADIATION RI-5317 A, B 100000 rern/h CONTAINMENTIIYDROGEN 0-AR 6527 3.7 pertent AUX FEED (e.g. FIC-4511A) 550 gpm STEAM GENERATOR LEVEL LIC-1114C,1114D -10 inches l

STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 250 psig CST LEVEL LIA-5610,5611,5603 31.5 feet SIFLOW FI .251 0 gpm l

CHARGING FLOW FI-2I2 0 gym RWT LEVEL LIA-4341,4342 39 feet l

l l

I J

SAM-1 OPERATIONAL DATA SCENARIO TIME: 01:50 REAL TIME: 09:50 PLANT PARAMETERS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 1000 psia CETs TI-131 A-D 2300 degreesF SUBCOOLING AI-11,12 0 degrees F RVIMS LI-20A., 208 10"ON off/ou PORY TAIL PIPE TEMPERATURE TI-106,108 OOS degswes F CONTAINMENT PRESSURE PI-5307,5310 (WR) 40 psig CONTAINMINr TEMPERATURE TI-5309(DOME) 276 degreesF CONTAINMENT SUMP EVEL LI-4146,4147 8.5 inches CONTAINMENT RADIATION RI-5317 A, B 100000 tim /h CONTAINMENT HYDROGEN 0-AR-6527 ' 3.8 percent AUX FEED (e.g. MC-4511A) 550 gpm STEAM GENERA'IOR EVEL LIC-1114C,1114D +5 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 400 psig CST EVEL LIA-5610,5611,5603 31 feet SI FLOW M-351 425 gpm CHARGING MDW M-212 0 gpm RWT EVEL LIA4341,4342 39 feet 4

1 SAM-1 OPERATIONAL DATA SCENARIO TIME: 01:55 REAL TIME: 09:50 PLANT PARAMETERS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 850 psia CETs TI-131 A-D 2300 degrees F SUBCOOIJNG AI-11,12 0 degnes F RVLMS Il-20A,20B 10"ON off/on l

PORY TAIL PIPE TEMPERATURE TI-106,108 OOS degnes F CONTAINMENT PRESSURE PI-5307,5310 (WR) 40 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 276 degmes F I CONTAINMENT SUMP LEVEL 1J-4146,4147 9 inches ,

l CONTAINMENT RADIATION RI-5317 A, B 100000 nm/h CONTAINMENT HYDROGEN 0 AR-6527 4.0 percent AUX FEED (e.g. MC-4511A) 220 gpm STEAM GENERATOR LEVEL IJC-1114C,1114D +5 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 450 psig CST LEVEL LIA-5610,5611,5603 30.5 feet SI FIDW FI-351 500 gym CHARGING FLOW FI-212 0 gpm RWT LEVEL IJA-4341,4342 38.5 feet

s.

SAM-1 OPERATIONAL DATA SCENARIO TIME: 02:00 REAL TIME: 10:00 ,

PIANT PARAMETERS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 600 psia CETs TI-131 A-D 2300 degrees F SUBCOO1JNG AI-11,12 0 degnes F l RVLMS Il-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degnes F CONTA mi PRESSURE PI-5307,5310 (WR) 41 , psig CONTAINMENT TEMPERATURE TI-5309(DOME) 278 degnes F CONTAINMENT SUMP LEVEL Il-4146, 4147 9 inches CONTAINMENT RADIATION RI-5317 A, B 100000 nun /h CONTAINMENT HYDROGEN 4AR-6527 4.2 percent i

AUX FEED (e.g. MC-4511A) 200 gym 4

STEAM GENERATOR LEVEL LIC-1114C,1114D +5 inches STEAM GENERA'IOR PRESSURE PI-1013A-D,1023A-D 500 psig CST LEVEL LIA-5610,5611,5603 30 feet SI M 4 W M-351 600 gym .

CHARGING FIDW M-212 0 gpm RWT LEVEL IJA-4341,4342 38.5 feet i

SAM-1 OPERATIONAL DATA

\

SCENARIO TIME: 02:05 REAL TIME: 10:05 PLANT PARAMETERS VALUE UNITS __

RCS PRESSURE PI-100 A-D, PI-103 550 psia CETs TI-131 A-D 2300 degrees F I

SUBCOOLING AI-11,12 0 degrees F RVIAfS LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F CONTAINMENT PRESSURE PI-5307,5310 (WR) 41 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 278 degnes F CONTAINMENT SUMP LEVEL LI-4146,4147 9 inches CONTAINMENT RADIATION RI-5317 A, B 100000 nm/h CONTAINMENT HYDROGEN 0-AR 6527 4.4 pertent

=

AUX FEED (e.g. MC-4511A) 200 gym STEAM GENERATOR LEVEL LIC-1114C,1114D +5 inches STEAM GENERAIDR PRESSURE PI-1013A-D,1023A-D 550 psig CST LEVEL LIA-5610,5611,5603 29.5 feet l SI FIDW

, M-351 600 gym CHARGING FIDW FI-212 0 gym RWT LEVEL LIA-4341,4342 38 feet

I 4

SAM-1 OPERATIONAL DATA SCENARIO TIME: 02:10 REAL TIME: 10:10 PLANTPARAMETERS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 550 psia CETs TI-131 A-D 2300 degrees F SUBCOOIJNG AI-11,12 0 desmes F RVIMS Il-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F CONTAINMENT PRESSURE PI-5307,5310 (WR) 39 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 276 degnes F CONTAINMENT SUMP LEVEL IJ-4146,4147 9.5 inches CONTAINMENT RADIATION RI-5317 A, B 100000 rern/h CONTAINMENT HYDROGEN 0-AR-6527 5.4 percent AUX FEED (e.g. MC-4511A) 200 gpm STEAM GENERATOR LEVEL LIC-1114C,1114D- +5 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 600 psig CST LEVEL LIA-5610,5611,5603 28.5 feet SIFIDW FI-351 600 gpm CHARGING FIDW FI-212 0 gym RWT LEVEL IJA-4341,4342 37 feet

l

/

SAM-1 OPERATIONAL DATA SCENARIO TIME: 02:15 REAL TIME: 10:15 PLANT PARAMETERS VALUE UNITS RCS PRESSURE H-100 A-D, PI-103 525 psia CETs TI-131 A-D 2300 degnes F SUBCOOLING AI-11,12 0 degnes F RVLMS LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F CONTAINMENT PRESSURE PI-5307,5310 (WR) 37 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 272 degnes F CONTAINMENT SUMP LEVEL LI-4146,4147 10 inches CONTAINMENT RADIATION RI-5317 A, B 100000 n m/h CONTAINMENT HYDROGEN 0-AR-6527 5.6 pertent AUX FEED (e.g. MC-4511A) 200 gym STEAM GENERATOR LEVEL LIC-1114C,1114D' +5 inches STEAM GENERA'IOR PRESSURE PI-1013A-D,1023A-D 650 psig CST LEVEL LIA-5610,5611,5603 28 feet SI M D W M-351 600 gym CHARGING MDW M-212 0 gpm RWT LEVEL LIA 4341,4342 36.5 feet

A SAM-1 OPERATIONAL DATA SCENARIO TIME: 02:20 REAL TIME: 10:20 PLANT PARAMETERS VALUF UNITS RCS PRESSURE PI-100 A-D, PI-103 525 psia CETs TI-131 A-D 2300 degrees F !

SUBCOOUNG AI-11,12 0 degrees F RVIMS U-20A, 20B 10"ON off/on PORY TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F CONTAINMENT PRESSURE PI-5307,5310 (WR) 34 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 267 degnes F CONTAINMENT SUMP LEVEL U-4146,4147 10 inches CONTAINMENT RADIATION RI-5317 A, B 100000 n m/h CONTAINMI:NT HYDROGEN 0 AR-6527 5.6 percent AUX FEED (e.g. FIC-4511A) 200 gym STEAM GENERA'IOR LEVEL UC-1114C,1114D +5 inches STEAM GENERA'IOR PRESSUIE PI-1013A-D,1023A-D 700 psig CST LEVEL UA-5610,5611,5603 28 feet i i

SI FLOW FI-351 600 gym l i

CHARGING FLOW FI-212 0 gpm RWT LEVEL UA-4341,4342 36 feet  !

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SAM-1 OPERATIONAL DATA SCENARIO TIME: 02:25 REAL TIME: 10:25 PLANT PARAMETERS VALUE UNITS RCS PRESSURE PI-100 A-D, PI-103 525 psia CETs TI-131 A-D 2300 degrees F SUBCOOIJNG AI-11,12 0 degrees F RVLMS LI-20A,20B 10"ON off/on PORY TAIL PIPE TEMPERATURE TI-106,108 OOS degrees F CONTAINMENT PRESSURE PI-5307,5310 (WR) 31 psig

< CONTAINMENT TEMPERATURE TI-5309(DOME) 258 degrees F CONTAINMENT SUMP LEVEL LI-4146,4147 10.5 inches CONTAINMENT RADIA110N RI-5317 A, B 100000 run/h CONTAINMENT HYDROGEN 0 AR-6527 5.6 perrent AUX FEED (e.g. MC-4511A) 200 gpm STEAM GENERATOR LEVEL LIC-1114C,1114'D +5 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 750 psig CST LEVEL LIA-5610,5611,5603 28 fat SI FIDW FI-351 600 gpm CHARGING FIDW FI-212 0 gym RWT LEVEL LIA-4341,4342 35 feet I

SAM-1 OPERATIONAL DATA SCENARIO TIME: 02:30 REAL TIME: 10:30 PLANTPARAMETERS VALUE UNITS RCS PRESSURE M-100 A-D, PI-103 525 psia CETs TI-131 A-D 2300 degrees F SUBCOOUNG AI-11,12 0 degrees F RVLMS LI-20A,20B 10"ON off/on PORV TAIL PIPE TEMPERATURE TI-106,108 OOS degries F CONTAINMENT PRESSURE PI-3307,5310 (WR) , 28 psig CONTAINMENT TEMPERATURE TI-5309(DOME) 252 degrees F CONTAINMENT SUMP LEVEL LI-4146,4147 11 inches CONTAINMENT RADIATION RI-5317 A, B 100000 run/h CONTAINMENT HYDROGEN 4AR-6527 5.6 percent AUX FEED (e.g. MC-4511A) 200 gpm STEAM GENERA 1DR LEVEL LIC-1114C,1114D +5 inches STEAM GENERATOR PRESSURE PI-1013A-D,1023A-D 750 psig CST LEVEL LIA-5610,5611,5603 28 feet SI FIDW M-351 600 gpm CHARGING MDW M-212 0 gym RWT LEVEL LIA-4341,4342 35 feet

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