ML20134K716
| ML20134K716 | |
| Person / Time | |
|---|---|
| Issue date: | 11/14/1996 |
| From: | Stewart Magruder NRC (Affiliation Not Assigned) |
| To: | Matthews D NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9611200001 | |
| Download: ML20134K716 (15) | |
Text
November 14, 1996 MEMORANDUM T0: David B. Matthews, Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Stewart L. Magruder, Project Manager Original Signed By:
Generic Issues and Environmental T'rojects Branch Division of Reactor Program Management 0'ifice of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF OCTOBER 30, 1996, MEETING WITH ABB COMBUSTION ER'INEERING REGARDING REVIEW 0F CENPD-137, SUPPLEMENT 2-P, 1 BREAK LOSS-0F-COOLANT ACCIDENT EVALUATION MODEL On October 30, 1996, representatives of ABB Combustion Engineering (ABB-CE) and Entergy Operations, Incorporated met with representatives of the Nuclear Regulatory Commission (NRC) at the NRC's offices in Rockville, Maryland. provides a list of meeting attendees.
The purpose of the meeting was to discuss ABB-CE's responses to the staff's request for additional information (RAI) dated October 1, 1996.
ABE-CF's proprietary responses to the RAI were submitted in a letter dated Octeer 24, 1996. ABB-CE's non-proprietary meeting presentation material is included as.
The meeting began with a long discussion of the first RAI question. ABB-CE presented some data from analysis performed in response to the question that ABB-CE claimed provided additional confidence in the overall conservatism of their model. The staff questioned ABB-CE about the assumptions used in the analysis. The staff was particularly interested in the values used for steam flow and rod power. ABB-CE committed to run the analysis again with different l
steam flow and rod power values and to update their response to RAI question i
1.b.
The group next reviewed ABB-CE's answers to the remaining RAI questions. The NRC agreed that ABB-CE's responses to questions 2, 4, 5, 7, and 8 were acceptable but that more time was needed to review the responses to questions 3 and 6.
With regard to the loop seal refilling issue, question 9, ABB-CE made a detailed presentation on the design of ABB-CE plants and the approach they are considering on taking in their response. The staff found the
/I) discussion very helpful and indicated that ABB-CE designed plants may not be
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subject to the phenomenon provided, among other things, they can show that n
l they are able to use safety grade equipment to perform a steam generator l
cooldown from the control room.
Attachments: As stated qViW cc w/atts:
See next page DISTRIBUTION:
See attached page Document Name: G:\\SLM1\\MSUM820.96 To receive a copy of this document, indicate in the box:
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November 14, 1996 MEMORANDUM T0: David B. Matthews, Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Stewart L. Magruder, Project Manager l
Generic Issues and Environmental ne~i N
. Projects Branch Division of Reactor Program Management l
Office of Nuclear Reactor Regulation
SUBJECT:
SlMiARY OF OCTOBER 30, 1996, MEETING WITH ABB COMBUSTION i
ENGINEERING REGARDING REVIEW 0F CENPD-137, SUPPLEMENT 2-P, l
SMALL BREAK LOSS-0F-COOLANT ACCIDENT EVALUATION MODEL On October 30, 1996, representatives of ABB Combustion Engineering (ABB-CE) l' and Entergy Operations, Incorporated met with representatives of the Nuclear Regulatory Commission (NRC) at the NRC's offices in Rockville, Maryland.
i provides a list of meeting attendees.
The purpose of the meeting was to discuss ABB-CE's responses to the staff's request for additional information (RAI) dated October 1, 1996. ABB-CE's proprietary responses to the RAI were submitted in a letter dated October 24, 1996. ABB-CE's non-proprietary meeting presentation material is included as.
The meeting began with a long discussion of the first.RAI question. ABB-CE-presented some data from analysis performed in response to the question that ABB-CE claimed provided additional confidence'in the overall conservatism of their model. The staff questioned ABB-CE about the' assumptions used in the analysis,. The staff was particularly.. interested in the values used for steam flow and rod power. ABB-CE committed to run the analysis'again with different steam flow and rod power values and to update ther response to RAI question 1.b.
j The group next reviewed ABB-CE's answers to the remaining RAI questions. The
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NRC agreed that ABB-CE's responses to questions 2, 4, 5, 7, and'8 were' acceptable but that more time was needed to review the responses to questions
[
3 and 6.
With regard to the loop seal refilling issue, question 9, ABB-CE made a detailed presentation on the design of ABB-CE plants and the approach they are considering on taking in their response. The staff found the i
discussion very helpful and indicated th st ABB-CE designed plants may not be i
subject to the phenomenon provided, amon., other things, they can show that they are able to use safety grade equipment to perform a steam generator j-cooldown from the control room.
j Attachments: As stated i
i cc w/atts: See next page
Distribution: MTG
SUMMARY
W/ABB-CE DATED November 14, 1996 Hard Cooy Central Files PUBLIC PGEB R/F ACRS OGC l
SMagruder l
E-Mail FMiraglia AThadani RZinunerman TMartin i
DMatthews EJordan l
TCollins F0rr EWeiss WJensen l
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NRC/ABB-CE MEETING ON SBLOCA EM REVISION LIST OF ATTENDEES October 30, 1996 4
M8ME ORGANIZATION Ernie Jageler ABB-CE i
Joe Cleary ABB-CE l
Ed Lee ABB-CE Dick Whipple ABB-CE Natalie Mosher Entergy (ANO)
Frank Orr NRC/NRR Stu Magruder NRC/NRR i
Walt Jensen NRC/NRR Dan Prelewicz Scientech i
Bill Arcieri Scientech Len Ward Scientech t
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SDLOCA Eh! REVISION NRC/ ADD hiceting 1000/96 l
NRC/ABB MEETING MEETINC DATE: WEDNE3 DAY. OCTOBEIL 30.1996 i
MEET!NC TIME.10.00 AM I4 CAT 10N; NRC CFTICES, WHITE FLDir. MD l
TIIIRD LICENSING REVIEW MEETING FOR ABB CE SBLOCA EM REVISION 1
COh!DUSTION ENGINEERING,INC.
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l SDLOCA Eh! REVISION NRC/ABB Sfecting 1000/96 AGENDA TIIIRD NRC/ABB LICENSING REVIEW l
MEETING FOR ABB SBLOCA EM REVISION l
WEDNESDAY, OCTOBER 30,1996 10:00 AM.
NRC OFFICES, WHrl'E FLINT, MD l
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- 1. Introduction and Meeting Purpose l
- 2. Status of Licensing Review Process and Schedule i
- 3. Overview of the NRC RAI on I
CENPD-137, Supplement 2-P l
- 5. Discussion of Loop Seal Refilling Issue - Actions I
Required for Resolution
- 6. Open Discussion and Planning / Meeting Wrap-up ARE
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SBLOCA EM REVISION NRC/ABB Meeting 10/30/96 INTRODUCTION AND MEETING PURPOSE l
+ CONTINUE THE PLAN FOR REVIEW AND APPROVAL OF ABB'S SBLOCA EM REVISION TOPICAL REPORT, CENPD-l 137, SUPPLEMENT 2-P, BEGUN AT JANUARY 23,1996 MEETING
- Acceptable to NRC
- Optimizes the Use of NRC Resources
- Approval for Generic Application Supports the Short Temi l
Needs of Utilities Depending on SBLOCA trnprovements for l
Operation
- Suppons Power Uprate for Waterford 3 Prior to Commitment of Major Capital Funds
+ PRESENT ABB RESPONSES TO TIIE NRC REQUEST FOR s
ADDITIONAL INFORMATION i
+ IDENTIFY ANY NEW CONCERNS OR ISSUES AND DISCUSS STRATEGIES FOR RESOLUTION
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+ FOCUS ON REAL CONCERNS OR ISSUES l
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SBLOCA EM REVISION NRC/ABB Meeting 10/30/96 Review Action Items from August 28,1996 Meeting Related to SBLOCA EM Revision t
Scientech completed technical review September
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16,1996; NRC issued RAI on October 1,1996 ABB-CE transmitted official response to RAI on
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October 24,1996 covering eight of nine questions
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Response to loop seal refilling issue introduced at
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August meeting in progress ABB.
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SDLOCA EM REVISION NRC/ABD Meeting 10SO/96 -
Project Plan and Status as of 10/30/96 l
ActJvity Que Date */s.Complett Meeting with NRC 1/23 100 %
Letter ofIntent to NRC 2'9 100 %
Proposalto Eo!
2/28 100 %
Submittal Analysis 5/10 100 %
DraA Submittal Preparation 5/15 100 %
Submittal Review and Revision 5/17 100 %
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Technical Review of Submittal 5/22 100 %
l Subndt EM Revision to NRC 5/23 100 %
KicLvirMeeting with NRC 6/10 100 %
Analysis Documentation 7/15 100 %
NRC !ssus Acceptance Review 7/19 100*6 Analysis Documentation QA 701 100 %
l Submit Response to NRC Acceptance Review t'9 100 %
Second Licensing Review Meeting with NRC
g 100 %
Response to RAI 10/24 90 %
Hird Licensing Review Meeting with NRC 10G0 Complete Response to LSR!ssue Final Documentation & QA 1231 65 %
1 NRC!ssue SER (4/1/97)
Issus FinalEMRevision (4/16/97) t f
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SDLOCA EM REVISION NRC/ABB Meeting 1000/96 1
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Overview of the NRC RAI Regarding the Supplement 2 SBLOCA Evaluation Model Topical Report Scientech identified 8 subjects where additional information is required 4
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- 4 questions related to the S2M changes j
- 2 questions related to the SIM l
- 2 questions requested text revisions to the report NRC requested resolution of I subject on generic SBLOCA behavior related to loop seal refilling ABB-
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i SBLOCA EM REVISION NRC/ABB Meeting 10/30/96 l
SUMMARY
OF 9 RAI QUESTIONS l
- 1. Application of ABB methodology to regulatory limit 1.a Margin analysis at higher temperatures
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1.b Benchmark against 336-Rod Bundle Tests
- 2. Radiationgeometricpathlength-futureimplementation
- 3. Steam emissivity at low temperatures -justification & sensitivity
- 4. Typographicalerrorinequation 2-9
- 5. Text revisions to show units on all equations
- 6. Basis for weighting factor in equation 2 clarification
- 7. Flag value for return to transition boiling - explanation
- 8. STRIKIN-IIinterface - explanation
SBLOCA EM REVISION NRC/ABB Meeting 1000/96 I
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SDLOCA EM REVISION NROABB Meeting 10/30/96 List of Teroporary Code Changes Response to Acceptance Review THTF FRS Physical Properties (Heat Capacity) i Option for closed form calculations of steam heat transfer model
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Edit axial distributions at the time of PCT Per time step edit of steam flow rate and minimum heat transfer logic j
Optional multiplier on geometric path length j
Response to RAI
- G2 FRS Physical Propenies (Heat Capacity) l ABB l
SBLOCA EM REVISION NRCABB Meeting 10/30/96 1.
Application of ABB methodology to regulatory limit 1.a Margin analysis at higher temperatures Response; Additional sensitivity studies performed with both SIM & S2M Metal-water reaction option turned off Increased decay heat multiplier to elevate PCT near 2200*F Margin between Sl M and S2M at higher power level and higher temperatures is the same as reponed in the topical repon Margin between decay heat multiplier of 1.2 and 1.0 is several hundreds ofdegrees greater at the higher power level than reponedin the topicalrepon Results show that the S2M maintains an appropriate amount of overallconservatism 1
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l SDLOCA EM REVISION NRC/ ADD Meeting 10/30/96 l
l 1.b Benchmark against 336-Rod Bundle Tests
Response
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Integral comparisons ruade to the 336-Rod Bundle G2 Tests Two G2 tests were selected: Test 721 and 722 Comparisons justify the adequacy of the S2M by conservatively simulating observed behavior l
- Ir.,egral comparisons show adequacy of PARCH / REM i
l icpresentation ofinterrelationship between convection and l
radiation at different temperature levels and different steam l
heating lengths i
- PARCH / REM predictions match bundle average data well These results establish the adequacy of the S2M by i.
benchmarking against the best available data closest to the temperature range ofinterest
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ABB i
i SDLOCA EM REVISION NRC/ABD Meeting 10/30/96 1
2.
Radiat!on geometric path length -justification l
Response
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A temporary code change was made in order to perform a j
l sensitivity study
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The limiting NSSS case PCT increased by only 2'F i
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l Further review of the reference materials indicate that no strong justification exists for the use of 0.85 times the l
hydraulic diameter for a square lattice of fuel rods I
i Prefer to stay with the methodology documented l
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- 3. Steam emisshity at low temperatures -justification &
sensitivity j
Response
Hottel data base covers the SBLOCA condition of pure steam I
High pressure adjustment to Hottel data compares j
favorably to Ferriso data at low temperatures i
Sensitivity studies indicate that the effect of emissisity differences between Hottel and Ferriso are insignificant to PCT 1
The results indicate that the S2M method for pressure dependent emissivity at low temperature is adequate for l
SBLOCA applications 1
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J SDLOCA EM REVISION NRC/ABB Meeting 10/30,96
- 4. Typographical error in equation 2-9 1
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Response
This correction will be incorporated in the final Version of the S2M topicalreport e
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- 5. Text revisions to show units on all equations l
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Response
Text revisions will be incorporated in the final version of l
the S2M topical report including units for all of the equations I
The heat generation rates in equation 2 12 are on a per unitlengthbasis ABB l
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l SDLOCA EM REVISION NRC/ABB Meeting 1000/96 6.
Basis for weighting factor in equation 2 clarification P.esponse:
The formulation is a continuous approximation for spatial variations using a discrete noding scheme Method isjustined by the transient G2 test comparisons j
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Method has negligible impact on NSSS PCT evaluations
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- 7. Flag value for return to transition boiling - explanation
Response
Vectors 101-121 preserve the nodal heat transfer history calculated by the STRIKIN-II code - as required by AppendixK This question is not related to the char),'es implemented for
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the S2M ABB
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SBLOCA EM REVISION NRCABB Meeting 1000/96 I
- 8. STRIKIN IIinterface-explanation i
Response
Initial temperatures for PARCH / REM wt te taken from the STRIKI6 II licensing basis calculations of record documented in Reference 3-1.
This question is not related to the changes implemented for the S2hi ABB
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Response
I Response to this question is being devrioped l
Issue not directly related to S2M model changes The 52M adequately addresses 10CFR50.46(b) l requirements for ABB CE designed (or fueled) plants i
through inherent and required conservative methodologies j
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SDLOCA Eh! REVISION NRC/ABB hiceting 1000/96 I
SUMMARY
l All 8 questions regarding the SBLOCA EM Revision 1
have been addressed Proposed model changes contain conservatism relative l
to other models and test data over the full range of applicability Clarifications and text revisions for the S2M topical report will be implemented after receipt of the SER Loop seal refilling issue response is on-going a
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I CE OWNERS GROUP cc:
Mr.-Gordon C. Bishoff CEOG Project Manager ABB Combustion Engineering M.S. 9615-1932 1000 Prospect Hill Road Windsor, CT 06095 Mr. David Pilmer, Chairman CE Owners Group i
Southern California Edison Irvine Operations Center Room 109C 23 Parker Street Irvine, California 92718 i
Mr. Charles B. Brinkman, Director Nuclear Systems Licensing ABB-Combustion Engineering, Inc.
Post Office Box 500 1000 Prospect Hill Road Windsor, CT 06095 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations ABB-Combustion Engineering, Inc.
12300 Twinbrook Parkway, Suite 330 Rockville, MD 20852 j