ML052130070
| ML052130070 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/26/2003 |
| From: | - No Known Affiliation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2005-0210, FTI-00-1353 | |
| Download: ML052130070 (27) | |
Text
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Approved 719103 Etrective 7117/03
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Condition Report Engineering Disposition Form Assignment No:
Page I
of CR No.:
M2-03-10511 97 Disposition:
E] CRED Not Required L Repair Ol Rewor 3 Use As is Disposition Justification During the Secondary Side Foreign Object Search and Retrieval (FOSAR), the vendor Identified four pieces of flexitallic gasket, which had not been previously identified or evaluated to remaln In the steam generator.
Additionally, he also identified that this material was not retrievable. Although this material was visually inspected, It remains on the tubesheet at the following locations:
Piece I -HL Piece 2 -1iL Piece 3-CL Piece 4-HL R123 L122 R133 L 110 R32 L5 R134 L109 R124 L123 '
R132 Lill R33 L4 R135 L108 R34 L5 Note 1 Originally identified as R123 L121. The correct tube is R124. L123.
The CRED allows the irretrievable material to remain in the steam generator. This issue was addressed during RFI 3 In a previous CRED for CR-00-01 234. This situation (i.e.. evaluation of flexatillic gasket) Is bounded by that CRED and the associated FTI Evaluation. That CRED allowed two flexatilhic gaskets to remain In the steam generator. ECT testing, after two operating cycles, identified zero wear rate for those components. That CRED remains valid also.
AWO#:
M2-02-13339 Continuation sheets attached 3
50.59 Screen (Required for "Non-Document or Non-Design Change" repair Nj Yes E lNo and use-as-is disposition)
Change Type:
[ ICEUMOD
[ Specification Change l EE D MEPL Upgrade
[l Temporary Modification F1 Other QCalclation Change Noa-Docurment or Non-;9!
Chane Preparer Lawrence Loomis 0Qeg°aw 10/26/03 pn s.iga.
Date If QA l?!
I;3 mayequfre an
-r lidependent..,.
Reviewer f?( O,& nL) print sign Date Approver b4eC.zyt* ),
print sign Date Information in this record was deleted In acm W'flb to D I 03-AAA h
cC=
Rev. 005 FODAQ' Page 1 of I
Condition Report Engineering Disposition Formr Assignment No:
CRNo.: M2-03-10511 The potential failure mechanism related to loose parts or foreign material in the steam generator is localized damage. The damage or degradation could occur as either immediate impact damage or long-term (usually years) fretting/wear damage. FTI Engineering Information Record S1-5008373-01, "Input to a Safety Evaluation for Millstone Unit 2 Steam Generators" (Attachment 1), provides reasonable assurance that, based on the part size, mass, and FrI flow induced vibration analysis, the loose parts will not result in wall degradation in excess of the tube plugging limits (i.e., 40 % nominal wall thickness) over the operating life of the steam generators. (Based on the location (i.e., tube sheet), part size, and same material, the new foreign material is bounded by this original FTI evaluation).
Potential Impact Damage The possibility of tube damage resulting from impact does not exist. The gasket remnants, rening in the generator, have very small mass distributed over approximately 4" in length (i.e., low density material). Consequently, movement of these parts will not result in the generation of sufficient energy to cause tube damage Potertlal Fretting Damage As identified in FTI Engineering Information Record 51-5008373-01, "Input to a Safety Evaluation for Millstone Unit 2 Steam Generators", the flex gasket is thinner and same relative hardness as the tube.
Consequently, it would wear through before a tube developed significant damage. This is consistent with the historical data obtained at MP2.
During RF13, tubes at locations R50, L7, R52, L7, R44, L85, R46, L85 and R45, L86 were identified as having irretrievable foreign material. Visual inspection confirmed they were in contact with Flexitallic Gasket. These tubes were Eddy Current Tested during RF15. The results are provided in Attachment 2, which identifies no damage had incurred to these tubes over two operating cycles. provides the ECT results documenting the fact that, although the new material has been present for some undistinguished time, there has been no resulting tube damage. The location of the new gasket material is consistent with the material identified during R13. That is, as identified by visual inspection, all gaskets are located on the tubesheet. As shown on the Attachment 2 inspection sheets, material located on the tubesheet has not resulted in tube damage.
During RI5, MP2 identified minor tube damage resulting from tube to flexitalE c interaction All damage was associated with flexitallic gaskets located within 7 inches of the lower support plate (Hot or Cold).
The five flexitallic gaskets causing the damage were removed and determined to be greater than 7 inches in length. To date no tube damage has been identified relatng to -any fleyitallic gasket removed, or remaimni on the tube sheet. Hower,Eddy Current Examinaions, un accoirdance with NEI 97-06, wil provide asurance that preventive -actions can be taken prior -to degradation, wich could rest in tube leakage. Millstone performs all SG EC Exarinations in accordance with NEI 97-06.
ConcluslonwDisposition USE-ASIS Based on the discussion above, historical data, and the referenced FM Report, leaving the foreign material in the steam genetors is acceptable and will not result in unacceptable tube degradation. Although not expected, degradation could occur over time. However, Eddy Current aminations, in accordance with NEI 97-06, will provide assurance that preetiv actions can be taken prior to tube leakage.
Page 2 of 2
l FTI Engineering Information Record 51-5008373-01 INPUT TO A SAFETY EVALUATION FOR MILLSTONE UNIT 2 STEAM GENERATORS
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F-SM T-N4 P-l-1MAY 16
' 42 FRAMATOME 7 E C H N 0 LO a I ES May 1S,2000 FI-O0.1353 Nordheast Utlitis Services Company MUillMone Unit 2 P.O. Box 128 Rop FeRy Road WaterbT, Caonmecicut 06385 Rof i nc.
P.O. 02126322 Rev. 001, Roloaw.001 dated 01V03/00 Subject Mi~lstone 2 - Safty Evaluadon of Forcign Objec-b Dear Jack Bnclosed plcas find FTI Docuemr No. 51-5008373-0l, "Impt to a Safety Evaluation for Millstonc Ut 2 Steam Geneator.
This rport addresses operafion of illstone 2 with Iown and pot=il loose pasts at the seconday face of the steam genra tabhot. Taohe evoaaion concludes tbat leaving known or undentified objects dmilar to those removed fkom the SG' during 2R13 does not represent in cmmviewed safety question for rwo cycles of futme operaion.
Please call either R. Schaefer at (804) 832-4009 or mo If you have questions or require addfional infornstion.
Levandoldd Sr. Project Mager FJIo66:gl,.
Enclosure Co; w; M.ll, 166 MMII RMdgO Road, Lburg, VA 245-341 TOWphM: 8044324700 Foc eD4432062 INtmet hM0Arwftzram
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FT1 Repair Succ.
F-53 T-046 P-061 M1Y I6 '0 15 1 7.
FMNGINWNGGINFMATIONWEORD Document Identifier SI -
5008373-01 Title Input to a Safty Evahlation for MIstonc Unit 2 Steam cncrit
.PREPARED BY:
EEVIEWED BY:
Nme MS Leeiub Name A__
Siaue h
Date 5-16a SiguDau 5
l Dase 5-TechniC9l MIK S~znt: Iialsb Reviev= is hdpendean FII Propiietw his dacli mcigjin oma nih onm cd bhczi t day aodmdrw
. u de popat of Fnaic TeKIog It conalns confl latfomatmonda iodtb.
od Ndor coped iiwiobh
.Et nor mayit b Dmlahd to iezw r
die txps d wzen permiloa of Frtmamn Tecbno=les m may my uwc be made of It gm c or may be Injudam io Pmao Teccnoaoic.
docwnt ftd mny faWstodmvfiW wd aWpis dqia may vh been =dc must bc rctnued pmp rqocsL This Safety Evaluation addresses the safety siifimmce of ope4ing the Milbstne Unit iNuclear Power Station vithnl fov f
gobJots onthe tubesheotoonsar fieo in stom g 2mtor2 (S2) and othe potental loos j
oects in both steam geneorso Abhough nono of the foregn objects has awased known tube degAsdago, a saft valuation is being paefo ed to doament the location eid e7At on of each object and to asse its safty sgnificae This evaluaionlso addresses the safety signifcance of operaig durig te last two opeting eycls with oier objects dia wvre removed from the steam Senrators. Thle evaluataon atso addresses the safty izficance if these parts had not been removed from the steam generators.
Conclusons:
Based upon te tluaions peented hrin, leaving die known objects on the S022 ebhoae scoondazy fce, as they cy c= y ais and leavirg in eie sfram* peg oetr othe =Mdtified objects siwiar to tbo sc rmoved from both stm geneaois stfias i1 parts ofthe 50.59 saty evaluafion and is not anumviewed aft quesdon for two cydos of operatii Hmwver, for this vcuatin to temaln valid for more an two cqc of opeaion. ET of th tbe locations fisted in Table I is toeuiW at a inimm to vcrify thit conditions evaluated have notce Psag
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d,57 CR#6003118 Mistone Unit 2 Fereign Objects Page 3 of 4 LOCATION D.
OWECT ISPOSITION Wedged Hex Piece SO 2 Hot Leg Unable to retrieve R94 - L139 R93 -L140 R9S5-L140 Weld Wire SG 2 Hot Leg Unable to retrieve R26-L21 R27 -L20
.R28 - L21 R29 -L20 Weld Wire SG 2 Cold Leg Unable to retieve R93 -L130 R94 -L129 R95 -L130 R96 -L129 R97 -L130 R98 -L129 R99-L130 R100 -L129 RIO1 -L130
_R102-L129 Weld Wre SO 2 Ho Leg Unable to retrieve R47-L36 R45-L36 R46 -L37 Gasket Matil SG 2 Hot Leg Unable to reieve R50-L7 R52-L_
Flat MetaW Piece Hot Leg SO 1 Removed from SG I
-1 Y2 L x K x l/32 thick Gasket Material Hot Leg SG 2 Removed fom SG 2 12" long Gasket atal Hot Leg SG 2 Removed fom SG 2
-4" long Gasket ial ColdlgS2 Removed fromS S2 n53 long
A 4 Y" "I CR4#6003118 Milstbne Unit 2 Foreign Objects Page 4 of 4 oDJECr LOCATION DISPOSITON Gasket Material Cold Leg SG 2 Removed from SG 2
- 5 " lo ng I
Gasket Materlio Cold Leg SG 2 Removed F om SG 2
'-6 long Giskqt Material Cold Leg SO 2 Removed from SG 2 C4 long Gasket Material Cold Leg SG 2 Removed from SG 2
-2" long GasketMaterial Hot Leg SG 2 Removed from S( 2 6" long Gasket Material Hot Leg SG 2 movedfrom SO 2 6" long Gasket Material Hot Leg SG 2 Removd-fRom SG 2 6 "31 lon g_
GasketMaterial Cold-Leg SQG2 Removed from SG 2 3 Ws Long GasketMaterial SG 2 Cold Leg Unable to retrieve R44 -L85 L46-L86_
Gasket Material Hot Leg-SG 2 Removed from SG 2 6 -7" long Gasket Material Hot Leg-SG 2 Removed from SG 2 7-8" long GasketMateflal Hot Leg SG 2 Removed from SG 2 Weld ir Hot Leg SG 2 Rem-oved from SO 2 2 "9 L o n g aasket Maerial Hot Leg SGT 2 Removed from SG 2 1" long
b'? er8kOYI RF1S ECT RESULTS TUBES IDENTIFIED WITH FLEXATELLIC GASKETS DURING RF13 Note: No defect identified
ECT Inspection Results for 2RF014 H/L FOSAR reporting Mllstone Unit 2 Steam Generator No. 2
. Cycle 2 RP t5 Roaw Col Volts Deg Ch=n Indn Percent Location Utill Util2 Cal Probe Extent Tested Plan 44
$s O
SON2HOMA SOIMO 61OBM TEC5 H 50MMBO VW=
O 8OCG2=A 802c001 610~PeF TSCTS SO2.C.RPC Or242CO 45 86 0
802HOMA S3 H0 SIOBOB TECMH SOZ-&2 0/2120 o
S32COOIA SMM0 61MIC TSC S02-CAPW W24M0 46 85 a
S303iO3A SME2 610BOB TICM 5O2-B.O 012arm O
St2COOIA S02C001 MMORPC TSCC S02-C-PaW 0
oM SO 7
O SOM 2
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3021W6S 610RPC TSnTSH SG2-H-RPCP 8441AM 52 7
O SIW2O G02R3li AiMCM MVHm
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S302106A 302HD65 610WC 1SHTSH S02-KAPPO WM=
Total Tubes:
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V( I7-- O?- Attachment 3 RF15 ECT DATA TUBES ASSOCIATED WITH FOREIGN MATERIAL
)vq77U, ECT Ispection Results for EUL FOSAR reporting Millstone Unit 2 Cycsa 2no1S Steam Generator No. 2 IRow Col Volts Deg Cban Indn Percent Location Utill Util2 Cal Probe Extent Tested Plan Date v"K.
0 )
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i 26 21 0.45 97 14 rLP TSH 0.48 SS0 61ORPC TSHTSH S0241-RP WV=
039 230 S PLP t3a 0.76 LA 01010 61030B ThCTEH 30240OB 0/19=
05 94 14 PM TSD 0.48 SG21 61017C TSHTSH 502-H4FL?
0/4=
27 20 0.47 95 14 FLP TSH 0.75 302H16S 610RPC 7T3113 302S""
OF20 NDF TSH lUSS S02065 610PI C TSHTSH 5MHC W24=003 OA6 9
14 PM TSH 0.75 S2W 61ORPC TS51 S02.M-PLJ WU=
A0.6 22 PLY TM 15S LA 5021009 610BO 7ECTEH 50218O 0C1W=
L28 21.
0.41 92 14 PM TSl 09 S0210 61ORC T7U3 S3-SP OrUM OAS 2323 FL?
TSH 2Z LA 30Z100 San T
S:
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SHD5 61tJRPC TS3H 30S5 0tW OAS Ps la FU TSH 0.96 80205 61S-PC 29 20 0.47 236 PL?
S73H 2.76 LA SOM010 61EBOB TECTUE s50-BOB 9121X13 0.42 94 14 PID 7SH 1.27 501069 61RPC S31H7 3024J4 0W400 1
T5H 176 SOM206S 610hC 7,HSg S02--RPP 742003 0.45 97 14 PUL TSH 1.27 302HSC5 SISPC TS15K S02-RPJ!CP UWW
-1123 1212-11 N
a 0
S02H077 6IORPC 502OM045 610B03 ISHMS 302481JL 012510 TECTFJ S02-".80 002?20 124 123 0
SG02146 610BOB TECTXH 502BOB 022003 132 111 Jf y"'i 0
0 50O11069 6103PC S02HD40 61000B ISHMS 3024M.PL WU=a'00 TEC1!H 302-4180 01/r=
133 110 0
S02HO0 610B30 TECTI 3a2413 WW0a3 s021m 61OPC T311H 802-1SW 62V 134 109 f
f1 0
t1 13S 105 a
0 302H177 AMUIC 8021040 610303 731711 302-H-FLP WS=100 TECIrM 30241805 W612=
I 0
0 80210 GIWIC 502140 61030 751H75 302W fA OrA TECTSZI 302-E D03 G= =20 Total Tube=:
10 0 - 2 If - -I a y
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31W4yy ECT Inspection Results for C/L FOSAR reporting Millstone Unit 2 I Qde 03-1 Steam Generator No. 2 ow Col Volts Deg Chlm Indn Percent Location UtWIl UtWl Cal Probe Extent Tested Plan Date f
28 5
Q19 10o 5
23 OIC 444 S02CD038 610PP OICOIC 502-SU Cris=
0.t9 109 5 VOL OIC 449 SoC002 610iPC OICOIC S024.RPCJ 0Wrf03 PC OlC 42.9 S02CO03 619PC OICOIC SO-C-RPCI OdZlZCM
- 4 132 3 LKI TSC 21.59 L&
302H011 610BO MM S02.3MO WM=
034 121 3
PD TSC 21.59 S0Q57 61=OD TSCTR sozaDS 128 s
32 S
0 SO30H11 6106o9 hCTIE}m s0241So oar 33 4
o 5omil1 LIOBOB TEOTEH 302-H-DOB 119200
.. 34 5
H o
50H0I1 6100808 TEM 30Z.BO WMt
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19 302CO03 SIOEPC OICOIC S0oC.1C 02512003_
0.13 0.13 051 046 U
S 4 5 109 3 113 3 VOL PD Lpl 21 OlC OlC T5C rnc 34.v 17.28 17.28 LA s0o S
S02=02 302H057 802H109 6"1aSC 61QRFC 61CO3B 61co00 OICOIC O1CO1C TECTEH TECTEH 302=5P013 024-BOB ansnam OA=
Ora wriomx Total Tubes:
S ILnd-C S6 2 Jo aW A. w, w Pag I of I
TUBE HISTORY 1eam Generator No. 2 123 122 Millstone Unit 2 VOLYS AIGLE CHANNEL INDU Pct LocATno ELEVATI0 Me MITAGE OATE pM Mt NT CAL PROBE C01GKENT PLAN 00-1 00-1 03-i 03-1 91-1 92-1 05103/Z0 123 122 05/04/2000 123 122 10/25/2003 123 122 1/22200 1D3 122 0815/1991 123 122 1I/14/1M 123 122 a
0.44 0
0 3.23 a
0 a
133 3
IUR 0
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r l
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4 M0M 0
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16.76 0
0 14.76 0
O TECIEH SG2HO61 60006 0 TEC1EH S02HO61 60030 0 lSHTSH SOHO7 610RPC 0 7ECIEH 8021H45 61080 0 7ECTEN 068A-02 600808 0 TEHTEC 0004 6008S SM2-H-SLe S02*H-BOI St-H-PLP s02-H-Wo0 S62-H-306 sc2-c-aos a
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TUBE HIS TO mwr 3Feanm WTAG 00-1 00-1 (03-1 91-1 92-1 94-1 97-1 DATE 05/02/ZOOO 05/04/2=00 1012Z/2003 08/08/1991 1214/19m 10/19/1994 06/21/1997 1K4 124 124 124 124 124 124 K jy 124 123 M~t COL VOLTS ANGLE CHANWEL ItND PCT LOCATION 123 0
0 0
123 0
0 a
123 0
0 0
123 0
0 0
123 0
0 0
123 0
0 0
123 0
0 0
, Generator No. 2 one Unit 2 ELEVATION XTENT CAL PROBE COWERT PLAN a
0 0
0 0
0 0
a 0
a 0
0 0
0 TECTEH TECTEH lECTEH TECTEH TENTEC TECTEH TECTER 5G2HOOO SGZH060 SW.046 O7OA-01 00034 041 SG2HO35 600 6108W 600808 600808 600800 64060B t=2 H-SOB SG2.H.We SC2-H-808 SG2-H-MB s02-*C-50 SG2-H-BO8 S02-H-WOB iI
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TUBE HISTORY Sftam Generator No. 2 N110 Milstone Unit 2 voLrs AN1GLE CIUWNEL IRDN PC!
LOCATION ELEVATION EXTEI OWAGE DATE Raw COt IT CAL PROBE COMMAT PULA 00-1 00-1 a3-1 03-1 91-1 92-1 94-1 97-1 05/O/2000 05/04/20o 10/250a3 10/22/2003 08/1tO0191 l2/13/1992 10/19/1994 06/21/1997 133 110 133 170 133 110 133 110 133 110 133 110 133 110 133 110 0
0 0
0 0
0 a
0 0
0 0
0 0
0 00 0
0 TEHTEC SM2H52 0
0 TECTEH 502Ho52 0
0 TSNtSH SG2H0 O
O TECTEH S6ZtO40 0
0 TECIEN 094A-01 O
0 TEHIEC 00o O
0 TEC1EH 043 O
0 TECTEH Sl;H033 600308 600W0 610RPC 610MW 600BOB 600W0B 60080 600BOB SG2-H-SLO SG2-H-W80 S02-H-PLP s52-HN-w Sl2-H-BOE 012-C-0OS SG2-K-BCS SG2-N-BOB 0
0 0
0 0
0
p
.4 c
- IDS, 3
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-.4 SyUa, Odo6e 34 003
TUBE HISTORY JTA9 ODAlTE ROM COL III ZSeam Generator No. 2 Millstone Unit 2 VOLTS AlNGLE CHANNEL IRND PCT LOCATION ELEVATON EXTE MT CAL PROBE COWENT PLAN 00-1 QaD 91-I 92-1 94-I 97-1 0S/O2Rf000 132 111 05/04/l00U 132 111 10/42003 132 111 08/1511991 132 111 12/13J1992 132 111 10/19/1994 132 111 06/21/1997 132 111 0
0 a
a 0
0 a
0 0
0 0
0 0
0 0
0 0
0 0
0 O
O TEHTEC SGZHOS2 60QU0B 0
0 TEC7EH 5G2HQ52 60W806 0
0 TSHTSH S02N069 6MORPC 0
0 TECTEH SG2H040 610905 0
0 TECTEH 092A-01 600309 0
0 TENTEC 00024 600303 O
0 TECTEN 041 60080o 0
0 TECTEH S02H033 60061
$G2-H-SLG SG2-H-909 SGZ-H-PLP Su2-H-BOB SO2-H-Bwo SG2-C-BW SG2-H-BOB
=-WmBO 0
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TUBEHISTORY 3
ITACE DAT!E ROW OOL VOL1 00-1 05/02/2000 32 5
00-1 05/04/2000 32 5
C C ~
10/19/2003 32 5
91-1 08/0311991 32 5
92-1 12/1211992 32 5
3z 5
- am Genemator No. 2 Millstone Unit 2 rs AuGLet CHANNEL IRMD PCT LOCATIOR ELEVATION EXTEIHT CAL PROBE COI0RN PLAN 0
0 0
0 0
0 0
0 0
0 0
0.
0 0
0 0
0 0
a 0 TECTEH S&2H013 600O08 O TECTEH S02HO13 600809 0 TECTEN SCZHO1I 6100B5 O tECTEH 0O9A-01 6000B8 O TEHTEC 00004 600BB 5Q2-l8-Sta S02-t4-506 SGZ-H-BOO s502-8 -30 sGz-C.B06
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TUBM HISTORY gSeam Generator No. 2 Millstone Unit 2 VOLTS AHOLE CHANNEL INDN PCT LWATION ELEVATIO)
EXTENT CAL OUTAGE DA1E ROW cOt PROEE COErNT PULW 00-1 91-1 92-1 94-1 97-1 05/0/000 05I04/2000 10/19/2003 08/03/1991 Z/12/19M 10/18/1994 06/20/1997 33 4
33 4
33 4
33 4
33 4
33 4
33 4
0 0
0 0
o 0
o 0
o a
C 0
0 0
0 0
O 0 TECTEH a
0 TECTER O
O TECTEM O
O TECMEH O
0 lEHlEC O
0 lECTEH O
0 7ECTEH SUZHO14 S0ZHO14 SG2HO12 OD9A-01 o0004 009 SG2H012 600BO8 6we06 61080 6008D 6009SO 600a 600808 SCZ-H-SEG 562-H-W06 SG2-H-BoJ SU2-N-r08 s62-c-moO
$62-H-we SG2-H-50O 0
0 0
0 P"
cI 1
-rC g
X 2
Z C
b
TUBE HISTORY 34 -
5 Sfeam Generator No. 2 Millstone Unit 2 VOLTS AMGLE CIUAHEL INDH PCA LOCAxOly ELEVATIO EXTENT CAL WitM Con~
91-1 92-1 94-1 DATE ROW COx PROBE CaOMENT PLAN 05/02/2000 OS/04/2000 10/19/2003 08/03/1991 12/11t4992 10/18/1994
.34 34 3'
3' 34 34 S
5 5
.5 5
5 0
0 a
0 0
0 0
0 0
0 a
0 0
0 0
0 0
0 TECTEN 0
0 lECTEH 0
0 TECTEM 0
0 TECTEH 0
0 TENTEC 0
0 TECTEN S02H014 S021014 SG2HO12 009A-01 00004 009 600808 600108 61008M 600305 600801 600601 502-H-SLG 102-H-DOS SGZ-H-0S SG2-H-BOB S02-C-8O0 SG2-H-0Bo I'
awi Ua*ZO, ZOOS Pqelofl
pme Z vfj -,
TUBE HISTORY 13 109 Otam Generator No. 2 MillstoneUnit 2 OWAGE DATE ROW 0OL VOLTS ANCLE CHAMEL INDN PC?
LMYAION ELEVATION EXTENT CAL PROBE CWWN T PLAN 00-1 00-1 00-1.
91-1 91-1 92-1 92-1 94-1 94-1 97-1 97-1 05/02/20o 134 109 05/022000 134 109 05/02/2000 134 109 10/25/Z003 134 109 10/2Z/2003 134 109 08110/1991 134 109 08/10/1991 134 109 12/13/192 1
109 12/13/1I9M 13 10 10/19/1994 134 109 10/19/1994 134 109 06/21/1997 134 109 06/21/1997 134 109 0
0.18 0.46 0
0 3.97 3.8 3.39 3.52 0.53 0.17 0.8 0.6 0
65 102 0
0 0
0 0
0 185 162 168 174 3
6 IHR I1R 4
Ku9 4
Nme 4
RON 4
NU I
INR I
[R I
IWR I
IUR 0
0 06N 0 Q1C 0
06R 0
01C 0
OIC 0
06N 0
06H 0
01C 0
01C 0
06H 0
4.07 13.59 0
3.97 13.54 13.57 3.73 3.78 13.45 13.45 3.78 O 7ECTEH 0 TECTEH O TEcrEH 0
TSUTSH 0
TECTEN 0 TEC7EH 0 TECTEN 0 lENtEC 0
TENTEC 0 lECTEH O IECTEH O TECTEH 0 TECTEM SOZHO53 600808 502H053 600906 sS2HQ53 6000S8 SG2HOTT 61ORPC SG2H040.
6108OD 094A-O¶ 600601 094A-01 603W06 00022 60006 00022 600808 041 600308 041 60030B S02H033 60Q080 WC2HO33 600806 S52-H-SLG SG2-H-lOS SG2-H-BO SQ2-H-PLP 5S2-H-SOM
$02-H-0OS S2-H-BOO SG2-C-0OS Se2-C-mBe S52-H-BW
$02-Hma SG2-H-BOB S62-H-lOB 1 C
&BxdcV O d.M26d 2001 1i r
TUBE HISTORY 135 108 eam Generator No. 2 Millstone Unit 2 CUTAAI 00-1 00-1
, 7iD 92-1 94-1 9W-1 DATE 05/0/2000 05/02n20 102/24t0 10/22/203 08/10/1991 12/13/1M 10/19/1994 06ai1/19T ROI coL 135 135 135 135 135 135 135 135 108 108 108 10J 108 108 108 108 VOLTS ANGLE CKAMMEL ION PCI LOCATION o
0 0
0 0
0 0
0 0 0 E E 0
0 0
0 0
0 0
0 0
fLEVAIOMN 0
a 0
0 0
0 0
0 O TMERCE 0 TECTER 0 TSHYSN 0 TEnCE 0
TECTEN 0 TENTEC O TECTEH 0 TECTEN SGZWM sG2)o53 5 21069 S02H040 096A- 01 00022 041 SG2HQ33 EXTE n CAL PROBE CONKENT PLAN 600800 600608 61ORPC 61308B 600808 6008 6008M0 6QOB08 SQ2-H*SLG SI:2-H-BOa SG2-H-PLP S02-H-808 SG2-H*D-0 S62-C503 S02-H-BOB SG2-H-sOm
(
P~gc~of1
- awo, ucwa a
Approval 6120103 Effective Q
6116/.03 50.59 Screen Form Unit:
2 Document No Cred CR-03-10511 Revision No.
A.
BRIEF DESCRIPTION OF ACTIVITY (Completed by Preparer)
(What is being changed)
The subject CRED identifies the acceptability foreign material (i.e., 4 pieces of flexatillic gaskets) to remain in the steam generator during the next two operating cycles. The CRED documents that, based on the mass and the size of the parts, there will be no adverse impact on the RCS pressure boundary. Additionally, the fact that 100 percent of the tubes in SIG number 2 will be ECT testing, during RF17 to comply with the requirements of NEI 97-06, provides assurance that preventive actions can be taken long before any potential tube leakage.
During the Secondary Side Foreign Object Search and Retrieval (FOSAR), the vendor identified four pieces of irretrievable flexitallic gasket, which had not been previously identified. Although this material was visually inspected, it remains on the tubesheet at the following locations:
Piece I -HL Piece 2 -HL R123 L122 R133 L l10 R123 L121 R132 Llll Piece 3 -CL Piece 4-FlL R32 L5 R134 L109 R33 IA R135 L108 R34 L5 The change allows the iiretrievable material to remain in the steam generator. This issue was addressed during RF13 in a previous CRED for CR-0O001234. This situation (i.e., evaluation of flexatillic gasket) is bounded by that CRED and the associated FMl Evaluation. That CRED allowed two flexatillic gaskets to remain in the steam generator.. ECT testing, after two operating cycles, identified zero wear rate for those components.
B. SCREENING QUESTIONS (Completed by the Preparer)
- 1.
Does the proposed activity require a change to the Operating License or the Technical Specifications?
[Ifyes, prepare OLITS change If no, document below and continue.]
- a.
Justificationfor determination:
Technical Specifications and the Operating Ucense do not address secondary side steam generator loose parts. Technical Specification 3.4.5 requires each Steam Generators to be operable based on Inservice Inspection (i.e., ECT).
This testing was satisfactory completed.
The CRED identifies that the loose parts, on the secondary side of SIG 2, will not have an adverse impact on the results of the ECT or the RCS Pressure boundary. Therefore, no change in the OL or TS are required.
Fonn RAC 12-001 Rev. 000-02 1 of 4
Approval 5/20/03 Effective 616103 50.59 Screen Form Unit:
2 Document No Cred CR-03-10511 Revision No.
I
- 2.
Does the proposed activity involve a change to an SSC that adversely affects an UFSAR described desigafunction?
[Ifyes, prepare 50.59 evaluation. If no, document below and continue.]
- a.
Justification for determination:
This CRED is administrative. The FSAR does not address foreign material within the steam generator. Therefore, acceptance of this CRED will not result in a modification of the facility or change in the operation of a SSC, which would change the design function, as described in the SAR The CRED documents both that the foreign material will have no adverse impact on the SIG (based on the FTI Evaluation, and historical data which established zero growth rate over two operating cycles (I.e.,similar existing material and location) and It being permanently lodged at this location) and the acceptability of the material to remain in the SIG. Consequently, the CRED will not adversely change the Steam Generator design function (i.e., RCS Pressure Boundary), as described in the SAR.
- 3.
Does the proposed activity involve a change to a procedure that adversely affects how UFSAR described SSC design functions are performed or controlled?
[Ifyes, prepare 50.59 evaluation. If no, document below and continue.]
- a.
Justification for determination:
This CRED is administrative in that it documents that the foreign material, based on a Location. Size, FTI report, and historical data, will have no adverse impact on the SIG. That it is acceptable for the material to remain in the SIG.
The CRED does not adversely affect any design functions.
- 4.
Does the proposed activity involve revising or replacing an UFSAR described evaluation methodology that is used in establishing design bases or used in the safety analyses?
[Ifyes, prepare 50.59 evaluation. If no, document below and continue.)
- a.
Justification for determination:
This CRED is administrative In that it documents that the identified foreign material will have no adverse Impact on the SIG and that it is acceptable to remain in the SIG. The CRED does not change any evaluation methodology used in establishing design basis Form RAC 12-001 Rev. 000-02 2of4
rajt,,q 4q
Approval 5/20/03 Effective 6/16/03 50.59 Screen Form I Unit:
2 Document No Cred CR-03-10511 Revision No.
- 5.
Does the proposed activity involve a test or experiment not described in the UFSAR where an SSC is utiied or contolled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the UFSAR?
jlfyes, prepare SO.59 evaluation. If no, document below and continue.]
- a.
Justificationfor determination:
This CRED does not involve a test or experiment. It documents that the foreign material will have no adverse impact on the S/G and that it is acceptable to allow it to remain in the S/G. Consequently, it does not involve any test or experiment not addressed in the SAR.
I Form RAC 12-001 Rev. 000-02 3 of 4
/ 004& fY Y1 f5 Approval 5/20/03 Effective 6116/03 50.59 Screen Form 4,.
Unit:
2 Document No Cred CR-S-10511 Revision No.
I C.
CONCLUSIONS
- 1.
A O/L or T/S change is required?
J No (Screen question I answered No)
- 2.
A 10CFR50.59 Evaluation is required?
0 No (Screen questions 2, 3, 4 and 5 answered No)
If both 1 and 2 are answered NO, then implement the activity per the applicable procedure for the type of activity.
D.
REFERENCES List the documents (e.g., licensing basis, technical commitments) reviewed, Including section numbers where relevant information was found.
Technical Specifications. Section Reviewed:
3/4.4-Reactor Coolant System Coolant Loops and Circulation 3/4.5 ECCS, 6.9.2.a Special Reports FSAR Review 4.3 System Design Table 4.3-2 S/G parameters 14.2 Decrease in Heat Removal by Secondary Side 14.3 Decrease in Reactor Inventory 14.6-3 SGTR f
E.
REVIEW AND APPROVAL Preparer: Lawrence E Loomis A
(
Print Name Signare Date: A Reviewer I C
y46ZE:60
%Z Print Name Signature Date: 2346/3
.1 Form RAC 12-001 Rev. 000-02 4 of 4 TOTAL P.45