ML20155A565

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Summary of 880914 Meeting W/Ge Re Postulated All Pump Trip for Advanced BWR Design.List of Attendees & Viewgraphs Encl
ML20155A565
Person / Time
Site: 05000605
Issue date: 09/28/1988
From: Scaletti D
Office of Nuclear Reactor Regulation
To: Chris Miller
Office of Nuclear Reactor Regulation
References
NUDOCS 8810060008
Download: ML20155A565 (15)
v • d • e


Text

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p* *nouq'o UNITED STATES

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NUCLEAR REGULATORY COMMISSION n

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i WASMGTON, D. C. 20656 September 28, 1988 c....

Docket No. STN 50-605 MEMORANDUM FOR:

Charles L. Miller, Acting Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects !!!,

IV, Y and Special Projects FROM:

Dino C. Scaletti, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects

SUBJECT:

MEETING

SUMMARY

RELATED TO POSTULATED ALL RIP TRIP, ABWR On September 14, 1988, a meeting was held with members of General Electric Co.

(GE) to discuss the postulated ALL-Pump-Trip (APT) for the ABWR design. This meeting was requested by GE to determine the staff's position related to classification of the APT; presently classified as an operational transient.

1 GE was exploring the possible reclassification of the APT as an accident. The GE presentation slides and the list of attendees are enclosed.

Presently the ABWR design employs MG sets as pass through energy devices on six ofthetenReactorInternalPumps(RIP). The MG sets, powered from two separate electrical distribution systems, are utilized to slow the coast down of two groups of three RIPS, thus eliminating the potential for DNB on an APT.

RemovaloftheMGsetswouldresultinabriefperiodinwhichDNBwouldogcur and the peak cladding temperature (PCT) would approach approximately 1000 F.

CreditforrewetwouldreducgthePCTtemperagurepresentlycalculated,by approved NRC methods, by 200 F to the 800-900 F range.

The topics pursued at the meeting were; how to obtain regulatory credit for rewet, what would be the af ter-event fuel inspection criteria, and what type of test data would be needed for an NRC review.

In the discussions that followed:

1. The staff agreed that they would be amenable to consider rewet.
However, even without rewet, preliminary analyses show that the cladding does not appear to reach a limiting temperature.

1

2. Integral tests varying starting power, power shapes, starting CPR, power coast down, flow coast down, subcooling would be some of the tests required.
3. If the transient occurred monitoring offgas and water chemistry would be required to check for failed fuel.

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.. September 28, 1988

4. Although the staff staff believes that justification for reclassification for the ABWR could be achieved, a request at this time would have a very low priority due to limited resources. Also, because DNB is the design basis for fuel failure, Comission approval may be required.
5. GE does not plan to request changes at this time.

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_ wac3 A Dino C. Scaletti, Project Manager i

Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects

Enclosures:

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September 28, 1988 2-

4. Although the staff staff believes that justification for reclassification for the ABWR could be achieved, a request at this time would have a very low priority due to limited resources. Also, because DNB is the design basis for fuel failure, Comission approval may be required.
5. GE does not plan to request changes at this time, original signed by Dino C. Scaletti, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects !!!,

IV, Y and Special Projects i

Enclosures:

As stated i

,0ISTRIBUTION:

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NRC PDR MHodges PDSNP Reading OGC-Roc kville EHylton EJordan DScaletti BGrimes NRC Participants ACRS(10) l (8d/k PDSNPfp SRX a

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e NRR/GE Meeting All Reactor Internal Pump Trip NAME AFFILIATION TELEPHONE Dino Scaletti NRR/PDSNP 301 492-1104 Les Rubenstein NRR/ADR4 301 492-1335 George Thomas NRR/SRXB 301 492-0892 Wayne Hodges NRR/SRXB 301 492-0835 Gerald Potts GE/ Fuel Engineering 408 925-6368 L. S. Gifford GE/ Licensing 301 770-9650 B. S. Shiralkar GE/BWR Technology 408 925-6889 C. D. Sawyer GE/ABWR 408 925-4143 Ashok Thadani NRR/ SAD 301 492-0774 Charlie Miller NRR/PDSNP 301 492-1118 l

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e POST-BOILING TRANSITION HEAT TRANSFER AND REWETTING APPLICATION o

LOW PROBABILITY EVENTS E.G., ABWR ALL-PUMP TRIP o

RAPID TRANSIENTS WHICH "DIP" IN AND OUT OF BOILING TRANSITION o

ddORT DURATION TEMPERATURE RISE (a-1000 F Fon 10 seconds) i i

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STEADY STATE POST BOILING TRANSITION HEAT TRANSFER DATA 15 rod BUNDLES DouGALL-RoHSENoW CORRELATION ADEQUATE FoR FILM BOILING AT BWR CONDITIONS CONSERVATIVE IN TRANSITION BOILING o

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16 AND 64 rod BUNDLE SIMULATION Or VARIous TRANSIENTS PUMP TRIP DBA FRONT END TURBINE TR.tp WITHouT BYPASS o

INTEND TO BOUND SPECIFIC TRANSIENTS WITH FULL SCALE DATA.

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TYPICAL TRANSIENT DATA WITH REWET AIA NO, or RODS TYPE or TRANSIENT i

28 16 PUMP TRIP (FLOW AND POWER DECAY) 40 16 DBA FRONT END SIMULATION (FLOW DECAY, POWER DECAY) i 44 16 FLOW "WINDOW" AT CONSTANT POWER 35 64 POWER RAMPS 56 64 TURBINE TRIP WITHOUT BYPASS 65 64 TURBINE TRIP WITHOUT BYPASS i

TLTA 4906 49 LOCA SIMULATION 6414 64 HIGH POWER BUNDLE LOCA SIMULATION i

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CURRENT LOCA MODELS ALREADY PREDICT POST BOILING TRANSITION i

HEAT TRANSFER AND REWET CRITERIA BASED ON WALL TEMPERATURE AND THERMAL MARGIN (CRITICAL QUALITY) o MINOR REFINEMENTS FOR MORE ACCURATE PREDICTIONS REWET QUALITY, PRECURSORY COOLING i

0 BOUND UNCERTAINTIES NO "CLIFF" TEMPERATURE LIMITED BY FAIRLY HIGH FILM BOILING HEAT TRANSFER COEFFICIENTS l

o REWETTING NOT PRECLUDED UNDER NEW ECCS RULE, 1

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ABWR ACCIDENT ANALYSIS s

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ALL PUMP TRIP (APTA) 10 PUMPS ON 4 SEPARATE POWER DISTRIBUTION SYSTEMS VERY LOW PROBABILITY OF SIMULTANE0US TRIP 4

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CLASSIFIED AS AN ACCIDENT USING EXISTING NRC APPROVED METHODS, PCT 0

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ABWR ACCIDENTS 4

REALISTIC RESUL,IS 1

o REWET TEST DATA AND CORRELATIONS EXIST I

o CONFIRMATORY INTEGRAL TESTS AND ANALYSIS INDICATE 0

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