ML20023D732
| ML20023D732 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/17/1983 |
| From: | Leech P Office of Nuclear Reactor Regulation |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| TAC-51351, NUDOCS 8306020642 | |
| Download: ML20023D732 (26) | |
Text
h.
M Q
h hg^ Y i
l MAY' 17 1993 p05 M10/@
DocketNo.Eh-33G
\\
I'EMORANDUti FOR: Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing FR0!!:
Paul 11. Lecco, ?roject Manager Operating Reactors Branch #3 Division of Licensing
SUBJECT:
f'EETING Oft fIILLSTONE 2 STENi GEflERATOR SLEEVI!:G, MAY 4, 1983 On May 4,1983, reprhIentatives of Northeast huclear Energy bompany (NNECO) and Westinghouse Electric Corporation met with several members of the NRC staff at Gethesda, Marfland to present their plans for sleeving about 3,00' stean generator tubes during the Millstone Unit 2 cycle 6 refueling outage scheduled to begin on May 28, 1983.
Attachnen)fthetopicsdiscussed.1 ts an attendance list for the necting and Attachment 2 a sumary o Details of the sleeving process are not included here since they are regarded by Westinghouse as proprietary.
Prior to initiation of sleeving about mid-July, NMECO plans to inspect nore than 3 percent of the 17.038 tubes, including larger samples in certain areas such as those typifying that where a leaking tube was found during March 1983. A requ6st for technical specifications changes relative to operation with sleeved tubes is expected by June 1, 1983.
Original signed tar Paul 11. Leech, Project Manager Operating Reactors Branch #3 Division of Licensing Attacim nts:
As stated cc: -See next page 8306020642 830517 PDR ADOCK 05000336 P
~
l o,nc,p OR,B,0 D
,gR,k),y,0,(,,,,,,,g P..M..K..r.
6....z..e..r......
..P l.e.e c..h../..p n.....
6./.k../.O..........
[.8.3,,,,,,,,,,,5/,y,/,8,3,,,,,g' one>
l me ronu sis tio-so> mcu o24o OFFICIAL RECORD COPY usom inei--sas-
MEETING SUMARY DISTRIBUTION Licensee:
Northeast Nuclear Energy Company
- Copies also~sent to those people on service (cc) list for subject plant (s).
Docket File NRC PDR L PDR NSIC ORB #3 Rdg ORBf3 Summary File JHeltemes BGrimes RAClark Project Manager PMKreutzer 0 ELD ELJordan JMTaylor ACRS-10 NRC Participants 2
~
.Q x.
s
\\
s
.a k
(
\\
\\.
s
+
\\
4===
'b%
%k l
'v f
'._,s[
i m
i e
)Y r
3 -.
- 4
~
N:rtheast Nuclear Energy Company cc:
William H. Cuddy, Esquire Mr. John Shedlosky Day, Berry & Howard Resident Inspector / Millstone
' Counselors at Law c/o U.S.N.R.C.
One Constitution Plaza P. O. Drawer KK Hartford, Connecticut 06103 Niantic, CT 06357 Mr. Charles Brinkman Regional Administrator Manager - Washington Nuclear Nuclear Regulatory Commission, Region I Operations Office of Executive Director for Operation C-E Power Systems 631 Park Avenue Combustion Engineering, Inc.
King of Prussia, Pennsylvania 19406 7910 Woodmont Avenue Bethesda, MD 20?l4 John F. Opeka System Superintendent Mr. Lawrence Bettencourt, First Selectman Northeast Utilities Service Company Town of Waterford P. O. Box 270 Hall of Records - 200 Boston Post Road Hartford, Connecticut 06101 Waterford, Connecticut 06385 Northeast Nuclear Energy Company ATTN:
Superintendent Millstone Plant Office of Policy & Management Post Office Box 128 ATTN:
Under, Secretary Energy Waterford, Connecticut 06385 Division 80 Washington Street 4
l Hartford, Connecticut 06115 l
U. S.' Environmental Protection Agency s
' Region I Office ATTN: : Regional Radiation
~
Representative
]
John F. Kennedy Federal Building Boston, Massachusetts 02203 j
Northeast Utilities Service Company l,
ATTN: Mr. Richard T. Laudenat, Manager s
- s. -
Generation Facilities Licensing l
\\ P. O. Box 270
Hartford, Connecticut 06101 I
l' l
\\
V S
-~
V' 7
sq n W
h
y 3 _
/b y
g :::
.iIf ' h
~
iy..
v:
, a }. !;
f
/
Attachment;I
'ATTEN3ANCE LIST e
' Meeting on Sl eving Steam Generator Tubes scar'
,j i
Millstone Nuclear Power Station Unit 2,May 4, 1983 p
.y
.i
.'ns t.,,.
/
g -
'y s l' fjortheast Nuclear Energy Company
'/.
k.Kupinski
_ ' A. J. Silvia
- P. R. Habicht
'A M. P. Cass J
'W. H. Stairs R. Tl Blanchard, Jr..,
j,' Westinghouse Electric Corporation R.S.Gripm,^Jsl.
'f J'
,~,
- ,,G. P. Airey i.
s r.
1
. /l ],/ ' 1f',.7 i
G. S. Chekrabarti i
Harry Clark i
<l Hal Keller M 'I R. N.;EasterlinL' A. R. Vaia r= !',,
~'
t.
e, I
Nuclear Regulatoiy Commission,'
,f N John Minns
- h
H. F. Conr'd
. I a
'l James Wing
/
B.D.Liaw-)+
~ ' '
r'.
' Bernard Terolin-(
Paul 1.eech r
r, 4
y "
/'
ef.
S
+
/J
't f
3 b
y 4 ^
/"
d
/
,/)
<sy i
+
t ac d-J k*
I
.y g
.y
[
s.+
l l> g
? :f,.
- 'j'
/
' 1 y
,t-,
q f'
r 1
__i. 'f;%
7; Millstone Nuclear Power Station pags 1 of 22 Unit 2 - Sleaving Steam Generator Tubes j
BACKGROUllD/1900STRY AND MP2
'A.
STATUS OF MP2 STEAM GENERATORS 17,038 CE-fiSSS/2-SG'S/ TOTAL NO, OF IUBES
=
e TO.DATE, A TOTAL OF 1,507 TUBES PLUGGED e
0 PRE DECEMBER 1981 " - 800 TUBES PLUGGED / PR
~
DENTING AN AS PREVENTATIVE MEASURE DECEMBER 1981 OUTAGE - 700 tubes PLUGGED 0
0-10" ABOVE TUBESHEET A IUBE SLEEVING AS A RESULT OF THE DECEMBER 1981 FINDINGS, e
CONTINGENCY FOR DEFECTS IN A LIMITED REGION A WAS DECIDED TO BE IMPERATIVE.
e t
O O
l l
p page 2 of 22 3.
INDUSTRY' EXPERIENCE TUBE SLEEVING OF DEGRADED STEAM GENERATOR TUBES WAS e
DONE AT.SEVERAL OPERATING UNITS.
ADDITIONAL MAJOR SLEEVE INSTALLATIONS ARE SCHEDULED e
DURING 1983, TUBE SLEEVING USED PRIMARILY AS CORRECTIVE MEASURE e
FOR IUBE DEFECTS IN LIMITED REGION ABOVE IUBESHEET.
THEREFORE, Tube SLEEVING PRESENTS A VIABLE ALTERNATIVE e
FOR CERTAIN DEGRADED IUBES IN LIEU OF PLUGGING.
O MINIMIZES PLANT PERFORMANCE DEGRADATION O
EXTENDS STEAM GENERATOR LIFETIME i
w
page 3 of 22 C.
PROPOSED I4P2 TUBE SLEEVING CONTINGENCY PROGRAM TUBE SLEEVING CONTINGENCY REQUIRED FOR 1983 REFUELING OU
, dean
.t- (mg n ud d-[h e
~
M WILL PROVIDE AND INSTALL IUBE SLEEVES e
CORROSION AND MECHANICAL QUALIFICATION O
O BIMETALLIC TUBE SLEEVES: (INCO 625/690)w/.wuL.sm d }cnIs O
AUTOMATIC INSTALLATION / USED IN OTHER PROGRAMS CONTINGENCY PROGRAM INCLUDES BOTH TUBE SLEEVING AND TUBE e
PLUGGING OPTIONS e
SLEEVING PREPARATION TO SLEEVE ~ 3,000 TUBES INCLUDES CONTINGENCY FOR 1,000 TUBES (2,000 PLUGS) e PLUGGING SAFETY ANALYSIS REDONE / SUBMITTED TO NRC/ ALLOWS PLUGGING UP TO 2,500 TUBES (1.E. 1,000 ADDITIONAL TUBES)
DECISION I'lATRIX WILL BE USED TO DETERMINEPLUG vS. SLEEVE e
INSTALLATION BASED ON:
0 'ALARA 0
OPERATIONAL FLEX 1BILITY 0
SAFETY ANALYSIS 0
ACCESSIBILITY 0
POWER DERATE-a
~ _ -. ~. _
-..~.-.-.--.:-...~...
~ _ ---.
page 4 of 22 MP2 SLEEVING PROGRAM' DESIGN CRITERIA i
A.
SLEEVE DESIGN e
ASME SECTION III NB-3200, ANALYSIS NB-3300, SIZING IEST e
ORIGINAL EQUIPMENT SPECIFICATION
^
REGULATORiGulDE1.83 S/G TUBING INSPECTABILITY s
REGULATORY GUIDE 1.1 1 PLUGGING MARGIN e
B.
SLEEVE MATERI AL e-ASME SECTION II MATERIAL COMPOSITION ASME SECTION III, NB-2000, IDENTIFICATION, TESTS AND e
EXAMINATIONS s
CODE CASE N-379 C.
SLEEVE JOINT 10CER100 PLANT TOTAL PRIMARY - SECONDARY AND SECONDARY -
e PRIMARY LEAK RATE e
MILLSTONE. TECHNICAL SPECIFICATIONS D.
AUM f
l l-
~
MILLSTONE UNIT 2 PITTING CHARACTERISTICS 0
REENTRANT CROSS SECTibN I
0 DARK CHROME - RICH 0X1DE VEINED WITH METALIC COPPER 0
OXIDE NOT READILY SOLUBLE 0
-GRAIN BOUNDARY ETCH'ING AND MICR0 PITS ON GRAIN FACES I
//
5 i
PIT MORPHOLOGY SIMILAR TO INDIAN POINT 3 l
)
EXTENT OF PITTING LESS THAN INDIAN POINT 3 m
=
i.
l
[
PITTING' MECHANISM O
SYNERGISTIC ELECTROCHEMICAL REACTION OF BOTH CHLORIDES AND SULPHUR COMPOUNDS 0
COPPER OXIDES PROVIDE OXIDIZING ENVIRONMENT 0
CHLORIDES AND SULPHATES AVAILABLE FROM CONDENSER LEAKAGE AND POLISHER SLIPAGE O
SULPHATES ALSO AVAILABLE FROM POLISHER REGENERATION CHEMICALS AND RESIN BREAKDOWN.
O COPPER OXIDES COME FROM CORROSION OF COPPER BASE ALLOYS IN FEEDTRAIN O
e W
cn
-h Rs
LABORATORY STUDIES ELECTRO CHEMISTRY AT B & W 0
PITS SIMILAR TO MP-2 PITS PRODUCED AT OPERATING TEMPERATURES IN COPPER CHLORIDE / SODIUM SULPHATE I
l l
l ISOTHERMAL CAPSULE IESTS AT CE O
PITS SIMILAR TO MP-2 PITS PRODUCED IS0 THERMALLY AT OPERATING TEMPERATURr*'
COPPER SULPHATE / COPPER CHLORIDE
~ ~
~-
l n
j TUBE SLEEVE ALLOY
)
O INCONEL 625 OD - PITTING RESISTANCE
-l 1
1
\\
l INCONEL 690 ID - THERMALLY IREATED - OPTIMUM RESISTANCE TO S.C.C.
l 0
8 e
e 9
w n
BIMETALLIC INCONEL 625/690 TUBE FABRICATION l
l (j
INCONEL alloy 625 eRmOveo eOnoeR 8
EXTRUSION p
<J y
j 1
=aa = ="
,Ncow,,, eee NiLWT SUBSTR ATS BILLET COLD WORKED ZE V
O CAN N
page 10 of 22-E!"ITALLIC ;ROCESSIN^
CONVENTIONAL THIN WALL TUBE MANUFACTURING TECH e
STARTING TREX (TUBE REDUCED EXTRUSION) e EVALUATED FOR B0:10 INTEGRITY, OD AND ID SURFACE CONDITION AND CLAD UNIFORMITY TECHNIQUES USED ULTRASONIC FOR BOND INTEGRITY ID BORESCOPE OD FLUORESCENT DYE
- METALL0 GRAPHY FINISHED TUBING (SLEEVING) e UT AND EDDY CURRENT INSPECTED, REQUIREMENTS OF SB-513 M WITH NOTCHES ON THE OUTSIDE DIAMETER OF THE CL ON THE INSIDE DIAMETER OF THE PRESSURE RETAIN HYDRO TEST FLARE TEST METALL0 GRAPHIC SECTIONS FOR CLAD UNIFORMITY TENSILE TEST, CLAD. REMOVED TO VERIFY PRESSURE RETAINING MATERI AL MEETS TENSILE PROPERTY REQUIREMENTS, YIELD STRENGTH AND 30% MIN. ELONGATION I.E., 40 TO 6S KSI N
page 11 of 22 E::ET:,LLiC !EI ALLw.Gy PROCESSING PARAMETERS SELECTED TO BE C THE INDIVIDUAL REQUIREMENTS OF INCONEL 625 e
INCONEL 690 MILL ANNEALING PARAMETERS OPTIMIZED IES OF INCONEL 625 WHILE NOT LOWERING TH s
OF THE INCONEL 690 BELOW SPECIFICATION HARDNESS MEASUREMEST TENSILE TESTS BURST TEST
- FREE EXPANSION METALL0 GRAPHY
- SCC TESTING THERMAL TREATMENT PARAMETERS EVALUATED e
REFERENCE THERMAL TREATMENT CYCLE FOR WAS AND INCONEL 690, I.E.,1300 F FOR 15 HOURS VERIFIED AS BEING ACCEPTABLE BASED ON M f-PROPERTIES AND SCC RESISTANCE METALL0 GRAPHIC EXAMINATION e
STRINGERS OBSERVED WITHIN THE CLAD FO e Al 023 LOTS OF MATERI AL M AN.ts...:;-
-R. /_ :U --
i i
page 12 of 22 MATERIAL A"D CORROSIO" VERIFICATION PR0 i d OBJECTIVES (A). DEMONSTRATE BY APPROPRIATE NDE AND METALL0 GRAPHI THAT THE BIMETALLIC SLEEVING MATERIAL MEETS ALL OF THE ASME BOILER AND PRESSURE VESSEL CODEf SECTION II AND SECTION III (1980 EDITION THROUGH WINTER 1980 ADDENDA)
REQUIREMENTS.
G) VERIFY THAT THE SLEEVING MANUFACTURE AND FIELD INST PROCESSES DO NOT INTRODUCE ANY CONDITIONS WHICH WILL RESULT IN PREMATURE TUBE OR SLEEVE DEGRADATION.
(C) VERIFY THAT THE BIMETALLIC SLEEVING PROVIDES IMPROVE INITIATION RESISTANCE ALONG WITH ACCEPTABLE RESISTANCE T OTHER MODES OF CORROSION',' (ALL RESULTS TO BE COMPARED
~
WITH MILL ANNEALED INCONEL 600 PERFORMANCE).
L
1 page 13 of 22 CC CLUEL0liS A) BINETALLIC INCONEL 625/INCONEL 690 SLEEVING CAN BE f
MANUFACTURED TO MEET ALL REQUIREMENTS OF THE ASME BOILER ANDPRESSUREVESSELCOD$.
B) THE-INTEGRITY OF THE METALLURGICAL BOND BETWEEN THE INCONEL 625/INCONEL.690 CAN BE EVALUATED DURING SLEEVE MANUFACTURE USING C0sVENTIONAL NDE TECHNIQUES. NO LACK
~
OF BOND HAS BEEN OBSERVED.
C) METALL0 GRAPHIC EXAMINATION OF THE STARTING TREX ( TUBE REDUCED EXTRUSION ) ALONG WITH SELECTIVE IN= PROCESS METALL0 GRAPHIC EXAMINATIONS INDICATE ACCEPTABLE CLAD THICKNESS UNIFORMITY DIMENSIONAL REQUIRBiENTS OF THE SLEEVE DRAWING HAVE BEEN MET.
STRINGERS HAVE BEEN OBSERVED IN THE INCONEL 625 D) AL 023 CLAD. THESE STRINGERS HAVE NO EFFECT ON THE CORROSION RESISTANCE, MECHANICAL PROPERTIES, NDE AND STRUCTURAL REQUIREMENTS OF THE BIMETALLIC SLEEVE.
E)
ELECTROCHEMICAL, BEAKER AND AUTOCLAVE EXPOSURE OF BIMETALLIC SLEEVING RESULTS IN SIMILAR RESISTANCE TO PIT INITIATION AS OBSERVED FOR WROUGHT INCONEL 625.
n page 14-of 22 WORK SCOPE FOR CL%53:0!i E'/ALUKi10!i c
Compare the pitting potential of wrought Inconel-625 with the bimetallic 3
Inconel 625/Inconel 690.
Verify the corrosion and stress corrosion cracking resistance of Millstone sieeving materials under off-chemistry secondary-side and e
Compare the performance of various lots of primary water environments.
bimetallic materials.
Evaluate the performance of bimetallic Inconel 625/Inconel 690 under heat Under, these conditions, the behavior of the annulus e
transfer conditions.
between the tube and sleeve will be evaluated.
I 1
9" e
l l
l t
A page 15 of 22 CORROSION RESULTS BEAKER' TESTS o
NO EVIDENCE OF PITTING OBSERVED ON 1625/690 OR 1625 o
'OTHER MATERIALS, IIE., 1600', AND I690, EXHIBITED PITTING o
NO EFFECT OF STRAIN GN PIT INITI ATION, I.E.,
EXPANDED VS. UNEXPANDED VS 0-BEND
. ELECTROCHEMICAL-TESTS (CHLORIDES)
~
o THE CLAD OUTER LAYER OF THE 1625/690 BIMETALLIC PROVIDES INCREASEDRESISTANCETbPITINiTIATION o
PITTING ELECTR0bHEMICkL POTENTIkL FOR BIMETALLIC EbulVALENTTOklROUGHT1625 O
v w
page 16 of 22 CORROSTON BESULTS ELEVATED TEMPERATURE TESTS OF THE BIMETALLIC MATERIAL IN RELEVANT MP2 CONCENTRATED OFF-CHEMISTRY SECONDARY SIDE ENVIRONMENTS HAS CONFIRMED THAT THE INCONEL 625/INCONEL 690 PROVIDES IMPROVED RESISTANCE TO PIT INITIATION kHILE PROVIDING SCC RESISTANCE',
HEAT TRANSFER TESTS ADDRE'SSING THE PERFORMANCE OF THE TUBE / SLEEVE CONFIGURATION UNDER SIMULATED OFF-CHEMISTRY SECONDARY SIDE ENVIRONMENTS ARE BEING PERFORMED, INTERIM EDDY CURRENT INSPECTIONS ARE BEING PERFORMED TO MONITOR ANY TUBE / SLEEVE DEGRADATION'..
l e
l 9
l
Pa9e 17 f 22 TECHA?.,'!O._ TESI TER!FICATION IEST PROCEDURE FORMAT SIMILAR TO PREVIOUS H SLEEVING REP e
PROGRAMS 0
LEAK RESISTANCE (RT, 600 F)
O FATIGUE 0
THERMAL CYCLE O
PUSli-0UT AND PULL-0UT 0
LOCA AND MAIN STEAMLIN,E BREAK e
MECHANICAL JOINTS 0
UPPER JOINT (HEJ)
O LOWER JOINT 0
Fixed MOCKue CE TUBESHEET SPECIMEN 5; (TUBESHEET WELD)
O e
PROCESS PARAMETERS
- 9 :IEST RESULTS
- 0 RESULTS FOLLOW PATTERN OBSERVED IN PREVIOUS PROGRAMS WITH GIVEN TUBE DI AMETER AND WALL THICKNESS 625 CLAD /690 0
PROCESS PARAMETERS SAME AS 690 OR 600
,0 STRUCTURAL STRENGTH VERIFIED 0
ACCEPTABLE JOINTS HAVE BEEN FABRICATED FOR ALL CONDITIONS
(
.s t
page 18 of 22 l
ANALYTICAL VERIFICATION e
ASME BOILER AND PRESSURE VESSEL CODE, SECTION III, 1980 EDITION e
ANALYTICAL PROCEDURE FOR STRESS EVALUATION SAME FOR PREVIOUS h SLEEVING PROGRAMS USING WECAN PROGRAM e
MILLSTONE DESIGN, FAULTED., IEST CONDITIONS L0CA + STEAMLINE BREAK e
SLEEVE CLADDING NOT USED FOR PRIMARY STRESS CONDITIONS PER ASME CODE NB 3122.1 BUT USED FOR SECONDARY STRESS PER NB 3122.2 e
THERMAL STRESS ANALYSIS e
FATIGUE EVALUATION ALLOWABLE SLEEVE DEGRADATION PER REGULATORY GUIDE 1.121 CRITERIA e
e TuBESHEET/ SUPPORT PLATE INTERACTION -- CE STEAM GENERATOR EVALUATION OF OPERATION WITH FLOW EFFECTS DUE TO SLEEVING e
~
page 19 of 22 IN5P.ECTABILITY OF THE INSTALLED BIMETALLIC SLEEVE I.
BIMETALLIC SLEEVE HAS NO UNIQUE IMPACT ON THE NDE INSPECTABILITY 0F THE SLEEVE / TUBE ASSEMBLY II.
TECHNIQUES TO BE UTJLIZED FOR BIMETALLIC SLEEVES ARE EQUIVALENT TO OR IMPROVED UPON FROM PREVIOUS SLEEVING PROGRAMS III.
IMPROVED CROSS WOUND COIL PROBE PROVIDES MORE EFFECTIVE FREQUENCY MIXING AND ANALYSIS 4
page 20 of 22 SYSTBi PRESSURE TESTS o
LEAKAGE TEST ON SLEEVED TUBES' WILL BE PER ASME SECTION XI REQUIREMENTS (i.E.
SYSTEM LEAKAGE TEST)','
o ~ ALL TUBE SLEEVES WERE SUBJECTED TO A SHOP HYDROSTATIC PRESSURE TEST AT l','2,5-X Poes rGN (3','110 Ps'ici) k I
l
7-page 21 of 22 ALARA o
CHANNEL HEAD EXPECTED RADIATION LEVEL - 17R/HR 0
CHEMICAL DECONTAMINATION O
CONSERVATIVE DF = 2','S 0
ANTICIPATED DF RANGE FROM 3-10 O
MOCKUP IRAINING 0
CARTRIDGE SLEEVE LOADER 0
APPROXIMATE 50 PERCENT REDUCTION IN CHANNEL HEAD TIME FOR SLEEVE INSERTION / EXPANSION AS COMPARED TO PREVkOUS E SLEEVING INSTALLATION O
ESTIMATED IOTAL MAN-REM Exe0SuRE l
(.
l l
l
i page 22 of 22
+
MILLSTONE 2 SAFETY ASPECTS - BI-METALLIC SLEEVING PROGRAM j
o 'ALL GDC WILL BE MET i
o SLEEVING / PLUGGING 0F TUBES IN ACCORDANCE WITH TECH SPECS.
TUBE INSPECTION AND EVALUATION IN ACCORDANCE WITH R.G.
1.83, REV. 1. FUTURE INSPECTIONS WILL CONTINUE IN ACCORDANCE WITH CURRENT TECH SPECS.
~
EVALUATION OF SLEEVE MARGIN IN ACCORDANCE WITH R.G. l'.121 o
o SLEEVE DESIGN AND TEST PROGRAMS (MECHANICAL, PRESSURE,
~
THERMAL, CORROSION) EQUAL 0R EXCEED THE APPLICABLE S/G COMPONENT DESIGN SPECIFICATIONS (NORMAL, TEST, EMERGENCY, FAULTED CONDITIONS).
o SLEEVING PROCESSES FOR THE BI-METALLIC SLEEVING PROGRAM ARE THOSE USED IN PREVIOUS WESTINGHOUSE APPLICATIONS AND l
ACCEPTED BY THE NRC.
~
!