ML20249A638

Summary of 980604 Meeting W/Listed Attendees in Rockville,Md to Discuss Containment Analysis for Extended Power Uprate for Plant,Units 1 & 2.Licensee Slides Encl

ML20249A638
Person / Time
Site:	Hatch
Issue date:	06/15/1998
From:	Olshan L NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
TAC-M99393, TAC-M99394, NUDOCS 9806180032
Download: ML20249A638 (55)

Text

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! p 4 UNITED STATES L g NUCLEAR REGULATORY COMMISSION wAsHINeToN, D.C. seseHept h Jgf

\***,+ June 15, 1998 LICENSEE: Southem Nuclear Operating Company, Inc.

FACILITY: Edwin 1. Hatch Nuclear Plant, Units 1 and 2

SUMMARY

OF JUNE 4,1968, MEET lNG TO DISCUSS CONTAINMENT ANALYSIS FOR THE EXTENDED POWER UPRATE (TAC NOS. M99393 AND M99394)

On June 4,1998, members of Southem Nuclear Operating Company, Inc. (SNC/ licensee) and General Electric Corporation (GE) met with the U.S. Nuclear Regulatory Commission (NRC) sta# in Rockville, Maryland, to discuss the containment analysis for the extended power uprate l for Edwin 1. Hatch Nuclear Plant, Units 1 and 2. Enclosure 1 is a list of the meeting attendees.

i Enclosure 2 is a copy of the slides presented during the meeting.

l l By Encl|letter dated August 8,1997]], the licensee submitted an amendment request to increase the -

l power level for both Hatch units from 2558 megawatts thermal (MWt) to 2763 MWt. The staff

requested additional information by letters dated February 10 and March 27,1998. By letters dated March 9 and May 6,1998, the licensee provided responses to all questions except Questions 56,59, and 60. The meeting was held to discuss these three questions.

l In response tc Question 56, the licensee provided the results of an analysis in which the SHEX l

. code (a code not approved by the staff) was benchmarked against the model previously reviewed and accepted during the Hatch licensing process. The staff agreed that the temperature results were sufficiently similar to justify use of the SHEX code, but asked for an explanation of the difference in the secondary peak pressure. The licensee agreed to provide this explanation in its response.

The licensee also provided the results of its containment analysis, using the SHEX code, for the extended power uprate conditions. The ANS 5.1 curve for boiling water reactors (BWRs), with an added 2 sigma, was used for the decay heat model. The staff members present at the meeting were not aware that ANS 5.1 provided different decaf heat models for BWRs and

, pressurized water reactors (PWRs). The staff said it would explore the acceptability of using the l- BWR decay heat model, which gives less conservative results. The licensee stated that it would consider using the PWR decay heat model that is familiar to the staff in order to save ,

staff review time.

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June 15,1998 The licensee said it expects to respond to the three questions within 2 to 3 weeks. The licensee would like the staff to approve the extended power uprate amendment in sufficient time so that it could be implemented during the fall 1998 refueling outage of Unit 2.

ORIGINAL SIGNED BY:

Leonard N. Olshan, Senior Project Manager Project Directorate ll-2 Division of Reactor Projects -1/il Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366

Enclosures:

1. List of Attendees

2. Licensee's slides cc w/encis: See next page E-Mail w/eo.cL1 Hard Coov w/all encls.

SCollins/FMiraglia MTschiltz, EDO Docket File BBoger LPlisco, Ril PUBLIC JZwolinski PSkinner, Ril PD 11-2 Rdg.

HBerkow LOlshan LBerry OGC TMartin ACRS ZAbdullahi Licensee & Service List CBerlinger RGoel KKavanagh JKudrick To receive a copy of this document, Indicate in the box: "C" = copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy OFFICEj fM:PDil-2 LA:PDil-h NP D:P,EMl-D l l NAME" LOlshan:cn LBerry XT HBerRok DATE 'e /t Z/98 le/YV98 '\ 6 /6/98 / /98 / /98 / /97 DOCUMENT NAME: G:\ HATCH \MTG.604 OFFICIAL RECORD COPY

t' I

2- '

The licensee said it expects to respond to the three questions within 2 to 3 weeks. The licensee would like the staff to approve the extended power uprate amendment in sufficient time so that it could be implemented during the fall 1998 refueling outage of Unit 2.

_l

-[(/dv Leonard N. Olshan, Senior Project Manager Project Directorate ll-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366

Enclosures:

1. List of Attendees

2. Licensee's slides cc w/encis: See next page I

l l

• ..?,

Edwin 1. Hatch Nuclear Plant cc: Charles A. Patrizia, Esquire Mr. Emest L. Blake, Jr. Paul, Hastings, Janofsky & Walker Shaw, Pittman, Potto 10th Floor l and Trowbridge 1299 Pennsylvania Avenue 2300 N Street, NW. Washington, DC 20004-9500 Washington, DC 20037 Chairman Mr. D. M. Crowe Appling County Commissioners Manager, Licensing County Courthouse Southem Nuclear Operating Baxley, Georgia 31513 l Company, Inc.

P. O. Box 1295 Mr. J. D. Woodard

! Birmingham, Alabama 35201-1295 Executive Vice President Southem Nuclear Operating l Resident inspector Company, Inc.

! Plant Hatch P. O. Box 1295 l 11030 Hatch Parkway N. Birmingham, Alabama 35201-1295 Baxley, Georgia 31531

, Mr. P. W. Wells Regional Administrator, Region ll General Manager, Edwin 1. Hatch U.S. Nuclear Regulatory Commission Nuclear Plant Atlanta Federal Center Southem Nuclear Operating 61 Forsyth Street, SW, Suite 23T85 Company, Inc.

Atlanta, Georgia 30303 U.S. Highway 1 North P. O. Box 2010 l Mr. Charles H. Badger Baxley, Georgia 31515 Office of Planning and Budget Room 610 Mr. R. D. Barker 270 Washington Street, SW. Program Manager Atlanta, Georgia 30334 Fossil & Nuclear Operations i Oglethorpe Power Corporation Harold Reheis, Director 2100 East Exchange Place Department of Natural Resources P. O. Box 1349 205 Butler Street, SE.. Suite 1252 Tucker, Georgia 30085-1349 Atlanta, Georgia 30334 Mr. H. L. Sumner, Jr.

Steven M. Jackson Vice President - Nuclear Senior Engineer- Power Supply Hatch Project t

Municipal Electric Authority Southem Nuclear Operating of Georgia Company, Inc.

1470 Riveredge Parkway, NW P. O. Box 1295 Atlanta, Georgia 30328-4684 Birmingham, Alabama 35201-1295 f

l L__-_-- - _ - - - - - - - _ _ . _ - - - - - - - - . - - - - - - - - - - A

_s s k n

• l MEETING ATTENDEES j I

MEETING TO DISCUSS THE CONTAINMENT ANALYSIS FOR THE HATCH EXTENDED POWER UPRATE JUNE 4,1998 j l

NAME ORGANIZATION Z. Abdullahl NRC/NRR l C. Berlinger NRC/NRR R. Goel NRC/NRR K.Kavanagh NRC/NRR J. Kudrick NRC/NRR L. Olshan NRC/NRR -

J. Brannum SNC T. Long SNC D. Read SNC S. Walker SNC D. Pappone GE C. Stoll GE 1 I

i l

Enclosure 1

p- A SOUTHERN NUCLEAR OPERATING COMPANY l PROPOSED MEETING AGENDA l

NRC MEETING FOR JUNE 4.1998 l

L l

l 9:00 - 9:15 Purpose / Introduction Leonard Olshan (NRC) 9:15 - 10:00 Oversiew issues / Current Submittal Tim Long (SNC) 10:00 - 10:15 Break 10:15 - 11:30 Benchmarking Dan Pappone (GENE)

-2a Approach Unit Specific Impacts i

Results t

11:30 - 12:30 Lunch 12:30- 1:30 Other impacts

Jeff Branum (SNC) i NPSH ECCS Suction Strainers Conta

.sment Coatings i-l e

1:30 - 2:30 Open Discussion All l

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a. 4 LPCI,1 CS,2 HX,WITH SPRAY

b. 2 LPCI,1 CS,1 HX, CTH SPRAY i

c. 11 PCI,1 CS,1 HX, WITH SPRAY

d. 1 LPCI,1 CS.1 HX, WITHOUT SPRAY Z

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lt ' .mg %%?.?f LONG TERM, RECIRCULATION BREAK, EDYVIN 1.HArCH Georgia Power 1 ~uctun etaur _ unir TEMPERATURE RESPONSE FIGURE 6.2-29

%O40

Suppression Pool Temperature SHEX-04V Benchmark for Hatch NP-Unit 2 Long-Term Containment Analysis, FSAR Case C 250 l l i

E 200

. 0 2

2

=

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@ 150 t ,

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+? +

l 250 8 i . _ _ _ _ . _ _ .

l

a. 4 LPCI,1 CS,2 HX,MTH SPftk '

I to 2 LPCI,1 CS,1 HX,MTH pptAY /

c. 1 LPCI,1 CS,1 HX, MTH SPftAY

d. 1 LPCI,1 CS.1 HX.MTHOUT SPflAY k .

$)igy\

- - 200 - - O E

\

2 d b.c '

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9 y 150-E m-a 100 _

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i l

i I

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LONG TERM, RECIRCULATIONBREAK,l g CALCULATED SUPPRESSION POOL Georgia Power d ,~,ucu,,a,,nur,,u,cg - um n TEMPERATURE RESPONSE l FIGURE 6.2-29 l 1

um

t 4 4 1 a i e .

a. 4 LPCI,1 CS,2 HX,WITH my e 15- -

• * ' "** *IN EY

c. 1 LPCf.1 CS.1 HX, WITH MtAY -

d. 1 LPCf.1 CS,1 HX.WITHOUT SPftAY g

k'

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b a

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LONG TERM, RECIRCULATION BREAK, EDWIN f. HATCH i Georgia Power d ~uctExa etaur _ unit : RESPONSE I FIGURE 6.2-27 )

J604-0 l

Wetwell Airspace Pressure b

SHEX-04V Benchmark for Hatch NP-Unit 2 Long-Term Containment Analysis, FSAR Case C l  ! i 15 O l ,  :

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TIME (SEC)

'm LONG TERM, RECIRCULATION BREAK

. EDWIN O. HATCH Georgia Power d sucum uur-unir RESPONSE FIGURE 6.2-27 l naa o

r .

GE LONG-TERM CONTAINMENT j

,, ANALYSIS APPROACH FOR LOCA PREVIOUS CURRENT EVENT APPROACH APPROACH IIE (1970'S) (1980'S & 1990'S) t

. BREAK n ,,

M3CPT e cc-2.o533 mm - (0310 INITIATION 0F "  !

P0OL COOLING SHEX XXSIZ meo-M33 gge wr t l PEAK POOL l

TEMPERATURE v v SHEX IS PRIMARILY BASED ON M3CPT

"+

DOCUMENTATION OF SHEX 0 SHEX USES MECHANISTIC MODELS OF M3CPT O

DOCUMENTATION OF M3CPT MODELS IS GIVEN IN PREVIOUS LTRs o REACTOR PRESSURE VESSEL (NED0-20533, SECTION 2) o BREAK FLOW (NED0-20533, SECTION 2) o DRYWELL (NED0-20533, SECTION 3) o VENT SYSTEM (NED0-20533, SECTION 4)

SHEX VENT CLEARING MODEL DOES NOT INCLUDE INERTIA EFFECTS o SUPPRESSION CHAMBER AIRSPACE (NED0-20533, SECTION 7) o SUPPRESSION POOL (NED0-20533, SECTION 7)

MECHANISTIC MODELS IN SHEX ARE DOCUMENTED IN PREVIOUSLY REVIEWED LTR NED0-20533

. \

e

~ '~

4e.

SNEX COMPARFn TO M3CPT AND HXSIZ IMil ILE21 ale 0 KEY COMP 0NENTS o RPV SIMPLE MECHANISTIC SIMILAR TO h3CPT o BREAK FLOW EQUAL TO ECCS FLOW MECHANISTIC " ' '

o DRYWELL l T = Taev nuto MECHANISTIC SIMILAR TO M3CPT P=Pu o VENT FLOW EQUAL TO BREAK FLOW MECHANISTIC SIMILAR TO M3CPT (WITH VENT (SIMPLER VENT CLEARING MODEL) CLEARING MODEL) o SUPPRESSION P00L MECHANISTIC MECHANISTIC SAME AS M3CPT (CONSTANTMASS) o SUPPRESSION T = Tron MECHANISTIC $1MILAR TO M3CPT CHAN8ER o- MXILIARY SYSTEMS LIMITED LIMITED COMPREHENSIVE (RNR. ECCS, i UPPER P00L.

ETC.)

SHEX USES MECHANISTIC MODELS OF PREVIOUSLY REVIEWED M3CPT TO REMOVE LIMITATIONS OF HXSIZ i

i

, SHEX APPLICATIONS SUBMITTED TO NRC 0 HOPE CREEK FSAR O

RESOLUTION OF "HUMPHREY ISSUES" FOR PLANTS WITH MARK III CONTAINMENT O

ANALYSES FOR PLANTS WITH MARK I CONTAINMENTS TO l

COMPLY WITH NUREG-0783 LOCAL POOL TEMPERATURE LIMIT i i

o O DRYWELL TEMPERATURE E-Q PROFILES 0~

POWER UPRATE EVALUATIONS l

i l

1 i

SHEX RESULTS FOR A BROAD RANGE OF APPLICATIONS HAVE BEEN SUBMITTED TO NRC

~ ' '

'" HILC DOCUMENTS CITING GE LTRs (NED0-20533 AND NEDO-10320) o NUREG-0800 (STANDARD REVIEW PLAN) o NUREG-0588 (INTERIM STAFF POSITION ON ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT) o NUREG-0661 (SAFETY EVALUATION REPORT FOR MARK I CONTAINMENT LONG-TERM PROGRAM) o NUREG-0487 (MARK II CONTAINMENT PROGRAM LEAD PLANT PROGRAM LOAD EVALUATION AND ACCEPTANCE CRITERIA) o NUREG-0808 (MARK II CONTAINMENT PROGRAM LOAD EVALUATION AND ACCEPTANCE CRITERIA) o NUREG-0978 (MARK III LOCA - RELATED HYDRODYNAMIC LOAD DEFINITION)

SUMMARY

0 SHEX USES MECHANISTIC MODELS OF PREVIOUSLY REVIEWED M3CPT CODE TO IMPROVE CAPABILITY TO ANALYZE CONTAINMENT LONG-TERM RESPONSE O

KEY MODELS IN SHEX ARE DOCUMENTED IN PREVIOUSLY REVIEWED LTRS NED0-10320 AND NEDO-20533 I

O MANY APPLICATIONS OF SHEX HAVE BEEN SUBMITTED TO THE NRC 1 MM SUBMITTALS TO NRC BASED ON SHEX P. AVE DEFENDABLE ANALYSIS BASES AND SHOULD CONTINUE TO BE ACCEPTABLE TO NRC l

,, M3CPT 0

USED.TO MODEL SHORT-TERN CONTAINMENT PRESSURE AND TEMPEP.ATURE RESPONSE O

MODELING DESCRIBED IN NEDD-20533 AND NED0-10320 0 HAS THE FOLLOWING KEY COMPONENTS

~~

o RPV o DRYWELL '

o VENT SYSTEM o SUPPRESSION CHAMBER AIRSPACE o SUPPRESSION POOL 0

HAS DETAILED VENT CLEARING AND VENT FLOW MODELING TO MODEL HIGHLY TRANSIENT PHENOMENA IMEDIATELY FOLLOWING INITIATION OF LOCAs 0 QUALIFIED EXTENSIVELY AGAINST TEST DATA 0 REVIEWED EXTENSIVELY BY NRC l

[

M3CPT IS THE GE COMPUTER CODE FOR SHORT-TERM CONTAINMENT PRESSURE AND l

TEMPERATURE RESPONSE AND IS THE PRIMARY MODELING BASIS FOR SHEX >

,,, XXSIZ 0

USED TO MODEL LONG-TERM CONTAINMENT PRESSURE AND TEMPERATURE RESPONSE FROM MID TO LATE-70's O DESCRIBED IN NEDO-20533 SUPPLEMENT 1, SEPTEMBER 1975 i

. O HAS THE FOLLOWING KEY COMPONENTS o REACTOR PRESSURE VESSEL (RPV) o DRYWELL (DW) o SUPPRESSION CHAMBER AIRSPACE (SC) i o SUPPRESSION POOL (SP) l O '

APPLIED FOR TIMES FOLLOWING HEAT EXCHANGER INITIATION 0 MAKES THE FOLLOWING SIMPLIFYING ASSUMPTIONS o A..uc =

Accci (RPV WATER LEVEL REMAINS CONSTANT) o kun = Annux o T. = Tn o Pic = P.

o Tu = T, O

INTENDED FOR ANALYSIS OF RECIRCULATION LINE BREAK HXSIZ IS GOOD FOR LIMITED APPLICATIONS

~ ~ ~

eee REASONS FOR INTRODUCTION OF SHEX 0

TO ANALYZE DRYWELL AND SUPPRESSION CHAMBER AIRSPACE RESPONSE MECHANISTICALLY 0

TO LOCA.

ANALYZE EVENTS OTHER THAN DBA RECIRC BREAK

'FOR EXAMPLE:

o COMPLETE SPECTRUM OF LOCAs

~ ~

BREAK SIZES BREAK TYPES o RPV ISOLATION o ALTERNATE SHUTDOWN o SORY TRANSIENTS o

RPV CONTROLLED DEPRESSURIZATION o DRYWELL BYPASS LEAKAGE o STATION BLACKOUT 0

TO INCORPORATE OPERATOR ACTIONS.FOR EXAMPLE:

o CONTROL OF RPV WATER LEVEL o

ACTUATION / TERMINATION OF CONTAINMENT SPRAYS SHEX CAN BE USED TO MODEL A WIDE VARIETY OF ACCIDENTS / TRANSIENTS

SHEX AUXILIARY SYSTEMS l

0 SHEX HAS BUILT-IN CAPABILITY TO MODEL THE FOLLOWING ADDITIONAL FEATURES ,

o MAIN STEAM LINE

! o SRVs

! o RHR (LPCI, SHUTDOWN COOLING, POOL COOLING,

! STEAM CONDENSING, DRYWELL SPRAY, WETWELL SPRAY, UPPER POOL REFILL) o ECCS (HPCI/HPCS,LPCS) i o FEEDWATER

! o RCIC

o RWCU o ISOLATION CONDENSER o CRD o l l REACTOR BUILDING o j DRYWELL-TO-WETWELL BYPASS LEAKAGE er o REACTOR BUILDING-TO-SUPP CHAMBER VACUUM BREAKERS-o SUPP CHAMBER-TO-DRYWELL VACUUM BREAKERS i o CONDENSATE STORAGE TANK SHEX MODELS MOST . - , , . . . ,

[ BWR AUXILIARY SYSTEMS

VALIDATION OF SHEX ee O INDEPENDENT CALCULATIONS o NASS AND ENERGY BALANCE FOR EACH COMPONENT A RPV A DRYWELL A SUPPRESSION POOL A SUPPRESSION CHAMBER AIRSPACE FOR DIFFERENT EVENTS FOR DIFFERENT CONTAINMENT TYPES A MARK I A MARK II A MARK III .

o CHECK ON FLOW RATES. EXAMPLES: . . . .

BREAK FLOW- .

l -

VENT FLOW l

o CHECK ON HEAT TRANSFER. EXAMPLES:

l HEAT TRANSFER RATE TO SERVICE WATER VIA HEAT EXCHANGER HEAT TRANSFER RATE TO CONTAINMENT STRUCTURES i

a 0

??f yJLIDATION OF SHEX 0

COMPARISON-0F RESULTS WITH M3CPT/HXSIZ RES o

OTHER INDEPENDENT EVALUATIONS CHECKS ON CALCULATIONS o MASS AND ENER.GY BALANCE o FLOW RATES o HEAT TRANSFER RATES .

CHECKS ON SYSTEM LOGIC EXTENSIVE VERIFICATION HAS BEEN.

PERFORMED FOR SHEX w-------_--.--_.__.__.__._ . - . - _

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