ML20137D233
| ML20137D233 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1985 |
| From: | Paulson W Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8601160572 | |
| Download: ML20137D233 (12) | |
Text
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D:cember 31, 1985 LICENSEC: B&W Owners Group SUB.1ECT:
SUMMARY
OF DECEMBER 3, 1985 MEETING WITH THE BAW OWNERS GROUP ANALYSIS COMMITTEE On December 3, 1985, the NRC staff met with representatives of the BAW Owners Group (R&WOG)AnalysisCommitteeinBethesda, Maryland.
The purpose of the meeting was to discuss the status of the RAWOG analysis program.
is a list of attendees. Copies of the handouts are also enclosed (Enclosure ?).
The DAWOG has two RELAPS benchmarking efforts underway to address two open items in the staff's SER on the Abnormal Transient Operating Guidelines (ATOG).
The RELAPS computer program will be sent to the NRC as a topical report about April 1, 1986. This version will not be an ECCS methodology topical; rather, it is intended to seek an NPC SER on the application of RELAPS to AT0G, at this time. The Owner's Group also indicated that there is no commitment to include the University of Maryland and SRI test data in the benchmarking effort.
They did indicate that they would look at the test data.
The Analysis Conrnittee is evaluatinq (1) operator actions to restore natural circulationsand(?)HPIcooling.
The schedule for these subtasks are shown in Enclosure 2.
The Analysis Coninittee is revising the large break 1.0CA evaluation model (BAW-10104).
Change pagos to Revision 5 of RAW-10104 will be submitted I
reficcting the changes, in addition, the computer progran FLECSET is being revised.
The Owners Group plans to submit the revised evaluation model by l
about March 31, 1986.
The BAWOG indicated that they plan to do only one calculation (0.07 fts i
break) in response to the rerlirements of TM! Action Plan item II.K.3.31
" Plant-Specific Calculations to Show Compliance with 10 CFR part 50.46."
The staff indicated that one calculation may not be enough to demonstrate compliance.
The chanqes to the small break model could require calculations for l
additional break areas, ug*gt $2% W Walter Paulson, Project Manager PWR Pro,iect Directorate #6 Division of PWR Licensing 0 8
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- Copies also sent to those people on service (cc) list for subject plant (s).
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EJordan RGrimes ACRS-10 NRC Participants WPaulson GVissing GEdison MRubin F0rr i
WRegan RJones NLauben DLangford i
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ATTENDANCE LIST OFCFMBER 3, 1985 MEETING NRC AND RATT)WNERS GROUP ANALY5IT COMMITTEF NAME ORGANI7ATION Walt Paulson NRC Guy Vissing NRC Gordon Edison NRC Charles Turk APAL - Chairman Analysis Com, j
Robert Schomaker RAW Alan Hosler Washington Public Power Suppl. Sys. DAW Mark Prubin NRC Frank Orr NRC William Regan NRC Pobert Jones NRC Norm Lauben NRC Dave Langford NRC f
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Enclosuro 2 I
07 S/ E_A3 3 ~NCr VAR (.sG 2202AA - C0k30S ",E tis"
- ANALYSIS COMPLETE
- DRAFT REPORT COMPLETED
- ISSUE TYPED DRAFT 12/15
- ISSUE FINAL REPORT 1/15 t
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- a C00_ NG "iS"
- MODEL INITIAllZED
- ANALYSIS COMPLETED 1/15
- DRAFT REPORT 2/15
- REPORT ISSUED 3/1 j
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EVA_JA" Os OF 0?. ERA ~0R s
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RA_ C RCs E 0,s 3
A. Open Head Vents and High Point Vents
- 8. Reactor Coolant Pump Bump C. Decrease Steam Generator Secondary Side Pressure l
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E TASK SCOPE A. Evaluate impact of High Point Vents I
B. Decrease in SG secondary pressure j
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C. RC Pump Bump - Postponed until core I
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SUBTASKS l
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- 1. Develop 177FA SBLOCA RELAP5 model l
BC heat transfer
- 3. Evaluate impact of RCS venting on E
reestablishment of natural circulation cooling I
- 4. Evaluate impact of increasing SG secondary level and decreasing secondary pressure on reestablishing natural circulation
- 5. Documentation
- 6. Technical Bases Document' update
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V. TECHNICAL BASES FOR EMERGENCY OPERATING PROCEDURES ANALYSIS C0ftHITTEE MEETINGS + Q Q
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I D. EVALUATION OF OPERATOR ACTIONS TO RE-ESTABLISH NATURAL CIRCULATION HODEL TRANSFER SUBTASK i - MODEL
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DEVELOPMENT SUBTASK 2 - BASE CASE x
SUBTASK 3 - RCS VENTING SUBTASK 4 - SG LEVEL a
a SUBTASK 5 - DOCUMENTATION g
z SUBTASK 6 - TBD UPDATES Y
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Figure 1 HPI COOLING SUBIASK LOGIC DIAGRAM (RIVISION 1)
Prepa re RELAP Hodel Subtask i HPI Cooling
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Subtask 4A HPI Cooling W/LOFW p,
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Low DK Heat l Saturated 2 WI 5
subcooled P>M55V High System System Setpoint Probability Subcooled Saturated I'5 Subtask 2D Throttle
[ Subtask 28 pg ~
HPI HPI Cooling HI DK Heat l
HPI Cooling l
I Hi DK Heat Stop
_ Cooldc<=n limits 2 HPI 2 HPI l
[aceeded =htle Stop PORV Opened
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Saturated Subcooled l Saturated L___
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$GTR p (nog W/ Saturated HI DK Heat Systen 2 HPI Man F/8 Plant
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V. TECilNICAL BASES FOR EMERGENCY OPERATING PROCEDURES ANALYSl5 COMMITTEE MEETlHG5
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I E. EVALUATION Of HPI C00LlHG Als U BM-MODEL e
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CASE 20 x
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SCOPE:
k REVISE FLECSET TO ENSURE CONSERV'ATIVE BENCHMARKS OF REFLOODING HEAT TRANSFER PERFORM NRC REQUESTED BENCHMARKS E
CONFIRM PRESENT KW/FT LIMITS l
REVISE LBLOCA EM (BAW 10104) 8 l
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BENC;-MAR (S COMPLETED 1/15 L
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(W/ T CONF RMED 2/15 4
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EVALUATION V0 DEL U? DATED 3/31 si FOR SU3k'TTAL TO NRC
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