ML19310A897
| ML19310A897 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/18/1980 |
| From: | Conner E Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-11348, TAC-11561, TAC-12505, TAC-42846, NUDOCS 8006300652 | |
| Download: ML19310A897 (29) | |
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JUN 181900 y
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Docket No. 50-336
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LICENSEE: Northeast Nuclear Energy Cgspany (NNECO);,,_,.
FACILITY: Millstone Nuclear',&ower $ti} tion., Unit No,2, __,,,___,..,_,__,.,_..'.
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SUBJECT:
SUf95RY OF EETINs~ HELD.ON. MARCH.18,.1980,0N MILLSTONE, UNIT.NO.,2,.,,
C.CLE 4 RELOAD W{TH WESTINGHOUSE. FUEL...,,,,,..... _.,.,,,...
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The meeting was requested by.NNECO to.present the status of_the _ Cycle.4, reload,,
of Millstone-2 with Westin$ouse (9), design.idfuel 2.A,11st,9f spetjng attendees,
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^
is presented in: Enclosure L..,...,,;,_,,,,,.,,, n _,,,,,,..,..<;
After intmdu5tions 'and openGg remarkspresented the agenda a
'the NRC Conner)y Mr. Cass of NNECO J~
the refueling outage and the iutiedtd1' dites has redentli, slipped atioit ons 7'F'"
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nonth. Mr. Kacich then presented.theiFprop6jed~jchedule,(Ifnclofuf,3)?.lAs,~
of this date, 93 EFPD remain in the,0ycle 3 core. - This means the coast dow 9
t could begin on about June'20[1980 andjhi;90% sndtd6wfhower.]evel" reached *'. ' ~
about July 1,1980.
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Mr. Cass presented the EncloiGre,4 set qf,eight,vjewgraphg,gn_the, basic safety * ' h report (BSR). TheNRCC(Weissl tioned the yse of XEND and Rosenthit r."
about difference between CE and
'f,aliilitioni fpFi:6Llo~
flailiacci ".7' p6' stirted'twoSeir(s],id'_~;
-Mr. Hills,of79tEC0.responde[,
t,,dnti.'traisajsil6n to 61o.c The ygsuljs ago and all important parameters we 6een und si of t W calculations wC1.have a qualijy',ijsifenii]g,, ei y'@hElj { b i. ' ~~'y~ ;rE~E" 7
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6,1g W, demonstration Mr. Hills presented the 11' phy ynder;Encigs e
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.jn 3 i,ygmirTpleal deilgn tests results and,Be n;n}@d fdr TS test, four bepered full'a area. The staff questfoned
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4 Millstone 2..... _.. 3/18/80 Mtg. The NRC (Weiss) suggested that.ot.he._r.me.9ti.n.gs. m.ay be n. eede.d.on..v.ar.io.us.r.e..l.oad....., review areas. NNECO agreed.....-.... _...- ~ odstnal dened d .~.
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-. E. L.. Conner Project Manager...,,. ,~ ~. '_ '. Operatin.g Reactors B..r,anch #3. .. o.. 4 + Division of Licensing'
Enclosures:
s 1. List of Attendees 2. Meeting
- 2... -
Cycle 4 L censing Schedule,. u.... ~ 43. - gst_.~ r,. ye. < -...~.. r....... s ~, r .,. -.ene wr.w e>+,. e.G .N... ~ ~- .s-k,-$g, bk(@ ,i. - cn c--" v. cw,le 2. Inspections v., 6~ - Qc . ~ h. w m .m
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l. MEETING SUPHARY DISTRIBUTION Licensee: Mr. W. G. Counsil, Northeast Nuclear Energy Company ?.
- Distribution with Enclosures 1-5, all other w/ enclosures 1-2 H. Denton E. G. Case Docket File
- NRC POR L PDR RPurple TERA NSIC
. ORB!4 Rdg NRR Rdg DEisenhut RTedesco TNovak Glainas ORB Branch Chiefs (5) ORB Project Manager -MCenner* ORB Licensing Assistant OELD AE00 IE-3 RFral ey, ACRS-16 Prcgram Support Branch Meeting Sumary File NRC Participants Jack Rosenthal* Norm Lauben* Jocelyn Mitchell* Margaret Chatterton* S. H. Weiss
- Bob Riggs*
DPowers* RMeyer* DFieno* LXopp* LPhillips* SDiab* JMazetis* ^ ~ ~
!aPinDo, UNITED STATES NUCLEAR REGULATORY COMMISSION {c-I wAsmNGTON, D. C. 20086 %,, m+..../ June 18, 1980 Docket No. 50-336 LICENSEE: Northeast Nuclear Energy Company (NNECO) FACILITY: Millstone Nuclear Power Station, Unit No. 2 {
SUBJECT:
Sul9%RY OF MEETING HELD ON MARCH 18, 1980 ON MILLSTONE UNIT NO. 2 CYCLE 4 RELOAD WITH WESTINGHOUSE FUEL The meeting was requested by NNECO to present the status of the Cycle 4 reload of M111 stone-2 with Westinghouse (W) designed fuel. A list of meeting attendees is presented in Enclosure 1. After introductions and opening remarks by the NRC (Conner), Mr. Cass of NNECO presented the agenda and an introduction.(Enclosure 2). He indicated that both i the refueling outage and the submittal dates have recently slipped about one month. Mr. Kacich then presented their proposed. schedule (Enclosure 3). As of this date, 93 EFPD remain in the Cycle 3 core. This means the coast down could begin on about June 20, 1980 and the 907, shutdown power level reached about July 1, 1980. Mr. Cass presented the Enclosure 4 set of eight viewgraphs on the basic safety report (BSR). The NRC (Weiss) questioned the use of KEN 0 and (Rosenthal) wondered about difference between CE and W calculations for the loss of flow accident. Mr. Hills, of NNECO, responded teat data transmissions to W started two years ago and all imortant parameters have been made available. The results of the E calc'Jlations will have a quality assurance review by NNECO. cations ((TS). Conner) questio.'ad the type of limits to be in the Technical Specifi-The NRC Mr. Hills responded that NNECO set up the ground rule to stay with the CE type of limits. Mr. Kacich discussed the LOCA analysis and the proposed schedule (Enclosure 5)- The NRC (Conner) asked about bounding of the small break LOCA analysis for Cycie 4 by the CE analysis for Cycle 3. Mr. Xacfd n'/, he knows no reason why this cannot be done. The NRC LOCA reviewer (Lanben) expounded on what he needs and Mr. Kacich said he understands and will provide. Mr. Hills presented the 11 viewgraphs under Enclosure 6. The W demonstration test, four bumpered full assemblies, will be placed in a symetrical high wear. a rea.. The staff questioned the bumper design. tests results and the need for TS surveillance requirements on this problem. In the. conclusional statemer.t. Mr. Xacich comitted to: 1. Provide the small break LOCA justifications for the Cycle 3 analysis,
- 2. ' Investigate TS surveillance requirements for the guide tube wear problem, 3.
Provide g bumper design test data. -L
4 Millstone 2 3/18/80 Mtg. The NRC _(Weiss) suggested that other meetings may be needed on various reload review areas. NNECO agreed. $wM E. L. Conner, Project Manager Operating Reactors Branch #3 Division of Licensing
Enclosures:
1. List of Attendees ~ 2. Meeting Agenda 3. Cycle 4 Licensing Schedule 4. BSR 5. Sm. Break LOCA 6. Cycle 2 Inspections e '~ ~~ .I,.. ?
MILLSTONE-2 CYCLE 4 RELOAD WITH W FUEL March 18, 1980 MEETING ATTENDEES ' NRC W NUSCO Monte Conner Ken Ferguson Mike Cass Jack Rosenthal Bob Steitler Richard Kacich Norm Lauben John Rawley Mike Hills Jocelyn Mitchell Gary Jacobs Byron Maddox Margaret Chatterton Roger Stover S. H. Weiss Bob Riggs i l l e e e m 9 &-4-'-
Enc 1csure 2 MILLSTONE UNIT NO. 2 MEETING AGENDA NNEC0/W/NRC MEETING, 1980 REFUELING ~ MARCH 18, 1980 I. AGENDA / INTRODUCTION MIKE CASS s II. LICENSING SCHEDULE RICK KACICH III. BASIC SAFETY REPORT - OVERVIEW MIKE CASS IV. GUIDE TUBES M,IKE HILLS CYCLE 4 SLEEVE DESIGN SPECIAL TEST ASSEMBLIES V. SMALL BREAK LOCA ANALYSIS RICK KACICH VI. GENERAL DISCUSSION VII. CONCLUSIONS g ^ --r - - ~ ~ ~
INTRODUCTION e NRC/NNEC0/W MEETING 2/14/77 ~ PROVIDED INFORMATION OPENED DIALOGUE OBTAIN FEEDBACK e NRC/NNEC0/W MEETING 1/26/79 PROPOSED SCHEDULE PRESENTED DESIGN APPROACH PRESENTED TEST RESULTS LOCA/NON-LOCA ANALYSIS APPROACH LICENSING APPROACH e SCHEDULE TO DATE e PURPOSE TODAY PRESENT BSR CONTINUE DIALOGUE CONFIRM SCHEDULE FOR SUBMITTALS AND NRC REVIEW en l l
MILLSTONE UNIT NO. 2 CYCLE ^ LICENSING SCllEDULE CURRENT SCHEDULE PRE-SUBMITTAL MEETINGS WITH NRC (ECCS MoDELS) 3/15/79 & 5/1/79 SUBMIT H ECCS MODELS TO NRC (WCAP-9528) 10/15/79 SMALL~ BREAK MODEL ADDENDUM TO WCAP-9528 6/11/79 NRC REVIEW COMPLETION DATE (LARGE & SMALL BREAK MODELS) 3/31/80 BASIC SAFETY REPORT (BSR) 3/6/80 PROP.OSED MEETING HITH NRC STAFF 3/18/80 i LARGE AND SMALL BREAK ECCS ANALYSIS SUBMITTAL 4/15/80 BSR ADDENDUM - NUCLEAR UNCERTAINTIES 5/1/80 RELOAD SAFETY EVALUATION 5/1/80 CYCLk4 CRITICALITY 9/1/80 g' i m i
MILLSTONE UNIT NO. 2 BASIC SAFETY REPORT e SERVES AS A REFERENCE FUEL ASSEMBLY AND SAFETY ANALYSIS ~ REPORT FOR'THE USE OF WESTINGHOUSE FUEL IN MILLSTONE UNIT N0. 2 e BASED ON STANDARD WESTINGHOUSE RELOAD DESIGN METHODOLOGY AS DESCRIBED IN WCAP-9272 (PROP.) AND 9273 (NON-PROP.) " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY" - DESCRIBES MODIFICATION OR SUPPLEMENTS TO THAT METHODOLOGY - DEMONSTRATES APPLICABILITY OF THE METHODS TO MILLSTONE UNIT NO. 2 e SERVES AS THE REFERENCE DOCUMENT FOR SAFETY REVIEWS OF i SPECIFIC CYCLE RESULTS ~ i ~ l ( J
SECTION 2.0 MECHANICAL DESIGN e PRESENTS A DETAILED DESCRIPTION OF THE FUEL ASSEMBLY AND FUEL R0D DESIGN e PRESENTS FUEL ASSEMBLY AND FUEL R0D DESIGN BASES e DEMONSTRATES COMPLIANCE WITH THE FUEL ASSEMBLY AND FUEL ROD DESIGN BASES e DEMONSTRATES MECHANICAL COMPATIBILITY WITH RESIDENT FUEL e SUMMARIZES TESTS USED TO CONFIRM DESIGN ADE00ACY 7 "w. 4 I.
n SECTION 3.0 - THERMAL AND HYDRAULIC DESIGN e PRESENTS THE THERMAL AND HYDRAULIC DESIGN BASES USED TO ASSURE CORE PERFORMANCE AND SAFETY CRITERIA ARE MET e DEMONSTRATES HYDRAULIC COMPATIBILITY BETFEEN THE WESTINGHOUSE RELOAD FUEL ASSEMBLIES AND THE CURRENT MILLSTONE UNIT NO. 2 CORE DESIGN METHODOLOGY HYDRAULIC TESTING e DESCRIBES THERMAL AND HYDRAULIC CALCULATIONAL METHODS J O ' ee -m ' erem me n o wn,:-- e. s
SECTION 4.0 - NUCLEAR DESIGN ~ e DESCRIBES NUCLEAR DESIGN METHODS AND MODELS 1 e QUALIFIES USE OF METHODS AND MODELS FOR MILLSTONE UNIT j : N0. 2 APPLICATION - MANY MEASURED VERSUS PREDICTED COMPARISONS GOOD AGREEMENT e DESCRIBES METHOD OF P0tER DISTRIBUTION CONTROL e PRESENTS PRELIMINARY CYCLE 4 RELOAD NUCLEAR DESIGN t e. p. -,--ps e p. .rv + <r-
SECTION 5.0 - ACCIDENT ANALYSIS c e PRESENTS A RE-EVALUATION OF ALL DESIGN BASIS EVENTS (DBE's) i e JESCRIBES THE ANALYSIS METHODS EMPLOYED BY WESTINGHOUSE FOR ACCIDENT ANALYSIS CALCULATIONS FOR MILLSTONE UNIT NO. 2 e ESTABLISHES A REFERENCE UPON WHICH TO BASE STANDARD WESTINGHOUSE RELOAD METHODOLOGY IN FUTURE RELOADS e CONCLUDES THAT IN ALL CASES PLANT SAFETY CRITERIA AND TECHNICAL SPECIFICATION LIMITS ARE MET r y ~
MILLSTONE UNIT NO. 2 TRANSIENT ANALYSES CONDITION 1-CONTROL ELEMENT ASSEMBLY WITHDRAWAL BORON DILUTION ? STARTUP 0F AN INACTIVE REACTOR COOLANT PUMP i EXCESS LOAD LOSS OF LOAD LOSS OF FEEDWATER FLOW EXCESS HEAT REMOVAL DUE TO FEEDWATER MALFUNCTION-REACTOR COOLANT SYSTEM DEPRESSURIZATION LOSS OF COOLANT FLOW CONDITION 2 LOSS OF COOLANT FLOW FULL LENGTH CEA DROP PART LENGTH CEA DROP PART LENGTH CEA MALPOSITICHING TRANSIENTS RESULTING FROM MALFUNCTIONING OF ONE STEAM GENERATOR u CONDITION 3 CEA EJECTION STEAM LINE RUPTURE STEAM GENERATOR TUBE RUPTURE ~ SEIZED ROTOR
SECTION16,0 - OVERPOWER AND DNB PROTECT 703 METHODOLOGY le DESCRIBESANALYSISMETHODOLOGYUSEDTODETERMINEiHELSSS ~AND LC0'S WHICH PROVIDE 0VERPOWER (KW/FT) AND DNB CORE PRO-TECTION DURING ANTICIPATED OPERATIONAL OCCURRENCES }.- e DESCRIBES METHODS USED TO OBTAIN THE LIMITING RADIAL AND AXIAL POWER SHAPES-e DESCRIBES THE DNB ANALYSIS PERFORMED TO ANALYZE THE POWER SHAPES AND DETERMINE THERMAL LIMITS e DESCRIBE 3 THE PROCEDURE FOR CONSTRUCTION OF THE SETPOINTS BASED ON CORE POWER SHAPES AND DNB ANALYSIS INCLUDING THE APPLICATION OF UNCERTAINTY ALLOHANCES TO THE TRIP FUNCTIONS 9 e
CONCLUSIONS .e THE WESTINGHOUSE MILLSTONE UNIT NO. 2 RELOAD FUEL ASSEMBLY IS MECHANICALLY COMPATIBLE WITH THE CURRENT MILLSTONE UNIT NO. 2 FUEL ASSEMBLIES, CORE COMPONENTS, REACTOR INTERNALS { INTERFACES, AND FUEL HANDLING AND REFUELING EOUIPMENT e THE WESTINGHOUSE MILLSTONE UNIT N0. 2 RELOAD FUEL ASSEMBLY IS HYDRAULICALLY COMPATIBLE WITH THE CURRENT MILLSTONE UNIT NO. 2 CORE e PREVIOUSLY REVIEWED AND LICENSED SAFETY LIMITS ARE MET e A REFERENCE IS ESTABLISHED UPON WHICH TO BASE STANDARD WESTINGHOUSE RELOAD METHODOLOGY IN FUTURE RELOADS ?
SMALL BREAK LOCA e W SMALL BREAK MODEL SUBMITTED OCTOBER 15, 1979 r o PLANT SPECIFIC RESULTS - APRIL 15,.1980 C~ e REANALYSIS OF LIMITING SMALL BREAK ~ e COMPARABLE RESULTS EXPECTED e REMAIN LARGE BREAK LIMITED V a ?
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,( MILLSTONE UNIT NO. 2 CYCLE 2 INSPECTIONS PROGRAM e -NON-DESTRUCTIVE EXAMINATI6N OF 10 BUNDLES 1 e VISUAL EXAMINATIONS OF 15 BIINDLES ~ e NON-DESTRUCTIVE EXAMINATION OF'10 CEA's e DESTRUCTIVE EXAMINATIONS ON ONE SLEEVE RESULTS e NON-DESTRUCTIVE AND VISUAL EXAMINATIONS CONFIRMED SATISFACTORY PERFORMANCE e HOT CELL WORK CONFIRMED THAT CHROME PLATING WAS NOT PENETRATED j e HOT CELL EXAMINATION REVEALED NO CREVICE CORROSION ON ID OF ZIRCALOY GUIDE TUBE e NO CEA WEAR NOTED e ( . _.. ~.... -
WESTINGHOUSE PROGRAM e 68 0F 72 BUNDLES TO BE SLEEVED 4 BUNDLES WILL UTILIZE INSET DESIGN e INSPECTION' PROGRAM COMPARABLE TO CE CYCLE 3 PROGRAM ) DETAILS NOT FIRM YET ~ COMBUSTION ENGINEERING PROGRAM - CYCLE 3 e SLEEVE 32 ADDITIONAL BUNDLES e NON-DESTRUCTIVE EXAMINATION OF APPR0XIMATELY 6 BUNDLES e NON-DESTRUCTIVE EXAMINAT!nN OF APPROXIMATELY 2 CEA'S 4 e ~ ' ~ ~ * * '., ~~ . me
COMPARISON OF GUIDE TUBE-SLEEVES GUIDE TUBE CE WESTINGHOUSE OD 1.115 1.111 ID 1.035 1.035 WALL 0.040 0.038 -3 i SLEEVE MATERIAL TYPE 304 SS TYPE 304 SS-OD 1.025 1.024 ID (U!lPLATED) 0.997 ~ 0.994 WALL 0.014 0.015 PLATING 0.001 0.0003/0.0007 SLEEVE /GT GAP 0.000-0.005 0.0055 DESIGN FEATURES - CRIMP AT BOTTOM CRIMP INTO POST AT TOP - FREE AT TOP FREE AT BOTTOM - SLEEVE /GT TAP WATER SLEEVE /GT GAP WATER COMMUNICATION VIA 6 COMMUNICATION VIA 17 HOLES PLUS 15 SLOTS SLOTS 9 y e,g, ,,4 mgw- +h e
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GUIDE TUDE SLEEVE MATERIAL: CHRCME PLATED 304 STAINLESS STEEL I h j: JPPER END TAPERED TO PATCH UPPER END FITTING POST I i 0.0. = 1.025 INCHES I.D. = 0.995 INCHES I \\ ( LENGTH = 22 INCHES FIFTEEN (15) 1/16" WIDE BY 1/2" LONG SLOTS OVER A 7-1/2" LENGTH i 1 I CHRCME PLATED I SIX (6) 0.093" OIAMETER HOLES 5-1/4 to 7-1/4 -INCHES FROM t THE BOTTOM .k l _. =. =
FUEL ASSEMBLY WEAR SLEEVES ( CONICAL SECTION i I ] SS END POST h, ~ I ~ SS SLEEVE FIFTEEN (15)2" I/16" WIDE BY 1/ LONG SLOTS OVER A 7-1/2" LENGTH ,e - ANNULUS q I (NOT TO SCALE) g i I ( p p i k I SIX (6) 0.093" OIAMETER HOLES NO GAP 5-1/t' to 7-1/4" l FRCM THE BOTTOM 1 I ZIRCALOY GUIDE TUBE ,\\ EXPANDED SECTION (NOT TO SCALE) / ( .,.,---,,.i.em m
StP. 9 8 e O 9 e e N0ZZLE PIN EXTENSION THINE E RATE _N ~~ ~ / . f. n I1 - 1 ] ~ (1 . 9 h N ) i t ( .- i em. l THINE TO TOP f022LE SE JOINT i e. l .?' ' ~ ~ ~ y
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