ML14093A243
| ML14093A243 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/30/2014 |
| From: | Mahesh Chawla Plant Licensing Branch III |
| To: | Entergy Nuclear Operations |
| Chawla M | |
| References | |
| TAC MF3196 | |
| Download: ML14093A243 (16) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043-9530 April 30, 2014
SUBJECT:
SUMMARY
OF CONFERENCE CALL WITH PALISADES NUCLEAR PLANT REGARDING THE FALL 2014 STEAM GENERATOR INSPECTIONS (TAG NO. MF3196)
Dear Sir:
On February 3, 2014, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with representatives of Entergy Nuclear Operations, Inc. (the licensee) regarding the steam generator (SG) inspection activities at Palisades Nuclear Plant. On December 6, 2013, the licensee was provided with the list of questions (Agencywide Documents Access and Management System Accession No. ML13343A185), to discuss the ongoing results of the SG tube inspections prior to completion of the inspections and repairs conducted during the Palisades Nuclear Plant refueling outage. The information provided by the licensee in support of the teleconference is part of the enclosed conference call summary.
Based on the information provided by the licensee, the NRC staff did not identify any issues that warranted immediate follow up action. However, the staff asked to be notified in the event that any unusual conditions were detected during the remainder of the outage. If you have any questions regarding this matter, I may be reached at 301-415-8371.
Docket No. 50-255
Enclosure:
Conference Call Summary cc: Distribution via ListServ Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
CONFERENCE CALL
SUMMARY
PALISADES NUCLEAR PLANT REGARDING SPRING 2014 STEAM GENERATOR INSPECTIONS DOCKET NO. 50-255 TAC NO. MF3196 On February 3, 2014, the staff of the Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB) of the Division of Engineering participated in a conference call with representatives of Entergy Nuclear Operations, Inc. (the licensee) regarding the ongoing steam generator (SG) inspection activities at Palisades Nuclear Plant. In support of the conference call, the licensee provided the document attached to this conference call summary.
Palisades Nuclear Plant has two Combustion Engineering Model 2530 replacement SGs. There are 8,219 mill annealed Alloy 600 tubes in each SG. The tubes have a nominal outside diameter of 0. 75 inches and a nominal wall thickness of 0.042 inches. The tubes are supported at various locations by stainless steel eggcrate lattice type tube supports, diagonal straps, and vertical straps. The tubes were expanded through the full depth of the tubesheet using an explosive process.
Additional clarifying information not included in the document provided by the licensee is summarized below.
The last bullet under the response to question four should be deleted.
In the summary indications table under the response to question five, two axial outside diameter stress corrosion cracking indications were found in SG Bat tube support locations. The indications had not yet been sized, but the amplitudes of these signals, as determined from the +Point' probe, were small (<0.3 volts).
In the summary indications table under the response to question five, the volumetric indications in SGs A and B are due to loose parts.
The calculated burst pressure of the flaw in the tube located in row 33 column 52 of SG A (page 3 of the licensee's document) was based on the data from profiling the depth of the flaw over its length.
The three tubes in SG B listed as having indications with d9fths greater than 40 percent through wall (TW) were analyzed with a +PointT probe. Two of these three historical indications were confirmed to be less than 40 percent TW, and one indication was confirmed to be 41 percent TW. The tube with wear measuring 41 percent TW will be plugged.
Enclosure At the time of the call, eight tubes in SG A required plugging and 10 tubes in SG B required plugging.
The licensee stated that there were still more than 200 tubes requiring special interest inspections with the +Point' probe, at the time of the call.
The foreign object search and retrieval in SG B is complete. The licensee attempted to retrieve one loose part in SG B and was unsuccessful. The tube next to the loose part will be stabilized and plugged.
The SG channel heads were inspected and no degradation (including degradation of the cladding) was noted. Palisades has a bolted divider plate.
There were no proximity or tube~to~tube wear signals noted during the SG inspections.
Noise levels of the eddy current inspection data were comparable to the last several outages and the quality of the eddy current inspections was good The reactor coolant system hot-leg operating temperature (T HoT) for Palisades is 583T In the attached document, provided by the licensee, the following acronyms are used:
- 3DP - 3 times differential pressure PLP - Potential Loose Part
+Pt - Plus Point POD-Probability of Detection AVB -Anti-vibration Bar psi - pounds per square inch
- BED-Best Estimate Depth PWR-Pressurized Water Reactor BEL - Best Estimate Length PWSCC - Primary Water Stress
- Circ-Circumferentail Corrosion Cracking CMOA-Condition Monitoring/
RPC - Rotating Pancake Coil Operational Assessment RxxCxx-Row xx Column xx EPRI - Electric Power Research TEC -Tube end cold-leg side Institute
- TEH-Tube end hot-leg side ETSS-Examination Technique TSH - Tubesheet hot-leg side Specification Sheet
- TSP-Tube Support Plate
- kHz-kilohertz
- TTS-Top of Tubesheet NDE - Non-destructive Evaluation TW-Through-wall ODSCC - Outside Diameter Stress
- V-Volts Corrosion Cracking Vpp -Volts peak-to-peak PDA-Percent Degraded Area The staff did not identify any issues that required follow-up action at this time; however, the staff asked to be notified in the event that any unusual conditions were detected during the remainder of the outage.
STEAM GENERATOR TUBE INSPECTION DISCUSSION DURING PALISADES 2014 (1 R23) OUTAGE Currently Palisades is - 95% through the base scope eddy current inspection and 30% through special interest as of 2/2/2014 at-1200 hours
- 1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.
Refer to attached Primary to Secondary Leak Rate for Operalional Cycle 23 Primary to Secondary Leak Rale graph. Leakage has been minimal all cycle.
- 2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results.
No secondary side pressure tests are planned for the 2014 refueling outage (1 R23).
- 3. Discuss any exceptions taken to the industry guidelines.
Last cycle (22) Palisades submitted a deviation to the NRC: Technical Justification Supporting Deviation from the EPRI Appendix I ETSS for ODSCC Sizing Palisades will deviate from the needed requirement to use an approved Examination Technique Specification Sheet (ETSS) contained in The "EPRI PWR Steam Generator Examination Guidelines-Revision 7", Section 6.2 for ODSCC sizing. Palisades will instead use a modified ETSS for ODSCC. The modified ETSS will be identical to the ETSS approved per Appendix I of the examination guidelines with the exception that only the sub-set of data from CE plants will be used instead of the combined fleet data set used in the approved ETSS.
A comprehensive review of axial ODSCC in Palisades steam generators shows that Appendix 128432 over sizes maximum depth values for axial ODSCC at Palisades. There is a reasonable basis to submit a deviation request for maximum depth sizing of axial ODSCC indications at Palisades. The request is relatively modest since it uses the Combustion Engineering (CE) subset of the well vetted data of Appendix 128432. The regression slope and standard error of regression are retained. Only the intercept parameter is changed. This provides an across the board reduction of NDE maximum depth sizing of 11.23 % TW.
This will lead to about a 1000 psi increase in calculated condition monitoring burst pressures and much better matching of projected and measured NDE maximum depths.
Attachment
The deviation was implemented in the 2012 (1 R22) refueling outage steam generator inspection for the remaining life of the existing Palisade steam generators.
- 4. For each steam generator, provide a description of the inspections performed including the areas examined and the probes used (e.g.,
dents/dings, sleeves, expansion-transition, U-bends with a rotating probe),
the scope of the inspection (e.g., 100% of dents/dings greater than 5 volts and a 20% sample between 2 and 5 volts), and the expansion criteria.
100% bobbin coil examination of all in-service tubes (except Row 1, 2, and 3 U-bends).
1 00% Rows 1, 2, and 3 U-bend +Point examinations in both SGs 100% hot leg TTS +Point examination in both SGs from TTS + 3" to a minimum of 12.5" below the bottom of the expansion transition (typically 13.5" below the TTS but needs to be verified during data analysis if not already previously verified) 100% +Point coil examination of Freespan dings >SV between TSH and TSC in both SGs 100% +Point coil examination of dented >2V eggcrates, diagonal bars, and vertical straps in both SGs, both hot leg and cold leg sides (SCC concern) 25% +Point coil examination of historic% TW calls at diagonal bars and vertical straps
+Point testing of the outer 3 peripheral tubes at the cold leg from TTS+3" to TTS-2" for detection of possible loose parts or wear signals. The periphery region is defined to be the outer three (3) tubes exposed to the annulus, all tubes in rows 1 through 4, and the inner three (3) tubes around the stay cylinder region.
20% sampling of 5 2Vpp dents in each steam generator using the +Point probe
- 5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc),
provide a summary of the number of indications identified to-date of each degradation mode (e.g., number of circumferential primary water stress corrosion cracking indications at the expansion transition). For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit).
2
As of 2/2/2014@ 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> Number SG Location Tvoe Indications*
Axial A
TSH ODSCC 2
Axial A
TSH PWSCC 0
Circ A
TSH PWSCC 0
Circ A
TSH ODSCC 6
A TSH Volumetric 2
A TECto TEH Wear> 40 0
Axial B
TSH ODSCC 2
Axial B
TSH PWSCC 0
Circ B
TSH PWSCC 0
Circ B
TSH ODSCC 2
B TSH Volumetric 1
B TEH to TEC Wear> 40 5
Axial A
Tube Supports ODSCC 0
Axial A
Freespan ODSCC 0
Axial B
Tube Supports ODSCC 0
Axial B
Freespan ODSCC 0
Total*
20
- Some tubes have multiple 1nd1cat1ons Worst Flaws to Date SGA Tube R33C52 ~Sludge Pile Axial ODSCC ~
Voltage 0.79 v by plus point.
Length = 0.42" Max Depth 54.4 %
Calculated Burst Pressure= 5407 psi (3DP = 4110)
Tubesheet and Sludge Pile Number Integrity Tubes AccEmtable 1
YES 0
N/A 0
N/A 5
YES 2
YES 0
N/A 2
YES 0
N/A 0
N/A 2
YES 1
YES 3
YES 0
N/A 0
N/A 0
N/A 0
N/A 16 The most significant flaw in this area is the same indication as above. Tube R33C52 in SGA 3
The largest circumferential ODSCC voltage in SGB (Tube R 28 C51)
TSH + 0.07 0.4 volts 11.69 PDA.
Calculated burst pressure= 8166 psi (3DP = 4110)
Supports Plus point data is in progress at this time. No cracks have been confirmed at this time at the supports - only wear. There are currently 3 tubes with wear > 40% in SGB. R113 C48 R123 C116 R135 C92 All three are being retested for confirmation because they are historical with little change.
Frees pan There is no free span repairable indications reported to date.
U-Bends There are no U-bend repairable indications reported to date.
- 6. Describe repair/plugging plans.
Currently there are 8 potential tubes requiring tube plugging in SG E-50A and 8 potential tubes in SG E-508.
All stress corrosion cracking (SCC) indications will be plugged. Any circumferential SCC indications near the top-of-tubesheet (TTS) will be stabilized and plugged. C' depth is applicable to the HL All wear indications (at support structures) greater than or equal to 40% TW will be plugged.
- 7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).
Based on the available data to date, no tubes will require in-situ pressure testing.
4
- 8. Discuss the following regarding loose parts:
What inspections are performed to detect loose parts?
The hot leg lop of tube sheet (TTS) region is inspected with +Pt up to 3 inches above TTS. A similar inspection is performed for the cold leg TTS region (3 tubes deep along periphery and tube lane. Foreign object search and retrieval (FOSAR) is performed for the periphery, tube lane annulus, and stay cavity areas.
A description of any loose parts detected and their location within the SG As of 2/2/2014 at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />, the following are the number of potential loose parts identified with the plus point inspection:
E-50A E-50B 184 PLP Calls in 172 Tube Locations 93 PLP Calls in 88 Tube Locations The majority of the indications is historical and has not changed. Visual inspection with FOSAR will be performed in both generators.
If the loose parts were removed from the SG SG E-SOA It is anticipated that FOSAR will start in SG E-50A on 2/3/2014 on night shift.
SG E-SOB It is anticipated that FOSAR will start in SG E-50B on 2/2/2014 on night shift.
The visual inspection will be performed around the periphery of both the hot leg and cold leg and along both sides of the tube lane approximately 3 tubes deep. This is following sludge lancing.
Indications of tube damage associated with the loose parts Currently there is 1 location in SGA and 1 in SGB that have wear associated with the part. An attempt will be made to remove the parts and retest with a volumetric standard. If unable to remove, the affected tube and surrounding tubes will be removed from service.
5
- 9. Discuss the scope and results of any secondary side inspection and maintenance activities (e.g., in-bundle visual inspections, feedring inspections, sludge lancing, assessment deposit loading, etc).
Visual inspections are scheduled for both SG E-50A and SG E-50B tubesheet periphery regions and foreign object search and retrieval (FOSAR) of the top of cold and hot leg tubesheets. This will be performed following sludge lancing.
- 10. Discuss any unexpected or unusual results.
Currently there are no unexpected or unusual results. There are no tubes that have failed the screening criteria requiring in-situ pressure testing
- 11. Provide the schedule for steam generator-related activities during the remainder of the current outage.
Currently bobbin and top of tubesheet +Pt RPC are approximately 99%
complete. Special interest will complete by - 2/4/2014 in both steam generators (this includes dings/dents. u-bend. cold leg top oftubesheet, eggcrate etc.). Tube plugging will start as early as 2/4/2014.
6
2014 Steam Generator Degradation Assessment Summary Table Table 9-1: Eddy Current Technique Table Degradation Probe EPKI llcmon~tnued Applicability Extended Detection"!
Sizing POD Sizing Parameter' Mechanism T\\'PC ETSS Annlicabilitv BOIJRI!'II I'\\Jbc to -1 ubc 13091.1 Fre~>pa~ tube-to-tube wear lkpth- 0_94*NDE +1.24 Wear Bobbin Rn*. 0 at 190 kHL None Y<:'
CMOA Sy,~- I.57 N~40 R--1 0 128413 Free>pan tc~cluding u-bend),
POIJ; Log-! ogi>tic i\\~ial OD<;CC Bobbin Rev. 3 cggcratc. sludge pile, & broached None Yes N"
Slope= 4.296 rsPs with or "ithout dents <2Vnn lntcrccnt = -5.6 79 i\\\\.ial ODSC'C Bobbin 24013.1 Free>pan including dings :0:5v
"'one Yes Rev. 2 I oreign Objc<:t 27091.2 Foreign object "car Lxtended for Depth 0.79*NDL t-12.85 Bobbin Ye; CMOA Sy,x = 13.49
\\I.' car Rev. l (pun not present): l-690 tubing l-600 tubing N=27l R=0.8 96004.1 A VA~. TSPs, Depth 0 9R*NDE + l.~<J
<;upport w~ar Robbin Rev 13 vertical and diagonal <;traps I\\ one Ye<>
CMOA
!'-.y,>. ~ 4.19 N-76.R~0.98 96005.2 Frcespan in the Depth 0.27*ND!.: 4 28.42 Pitting Bobbin Rev. 9 pre sene~ of copp~r Sludge Pile Yes CMOA Sy.x-1336 l\\~62.R~0.41 AxialODSCC Depth 0.9<J94*NlJL.,. 0.49n Sy,x = 11.~56 128424 N-58<J.R=O.RR R~v. 3 id~tcct);
TSP (with or without dents '-~2vppl RED* CMOA POD: Log-1 ogi<>tic Bl.:Ll = 0.9941*\\IOF + 2.7324 Axial ODSCC
- Point'"
and <>llldgc pile None Yes Slope= 11.4155 s~.x = l0.6R5 1284] l BEL: CMOA Intercept= -17.7154 "l = 5R9, R = 0.~95 Rc\\ 2 (Sil.illg)
BEL= 0.645l*NDE + 0.0785 S}.x=O.l06 "l = 5!\\<J. R = 0.723 Lkpth 1.0069*NDF. + 0.3736 Sy.x = 12.329 12842."
N=676.R~0.862 Re~.3 (detect)
Frcc.<>pan (excluding u-bend].
BLD: CMOA POD: Log-Logistic BF[)- 0.972*NDE-3.69~
Ax1al Q[)S('("
+PointTM
~ggcratc, & broached rsr:. with or None Ye:.
Slope= 6.7176
<;},X~ 12.153 12H432 without dents :o2Vpp BFL. CMOA Intercept= -9.146 N=676.R~0.859 Rev.2 (sizing)
BEL= 0.516*1\\UL
- 0.208 Sy,x = 0.2 N ~ 676, R ~ 0.592 8
[)cgradation Probe F:PRI flcmonstrated Applieabilit)
Extended Detection'!
Sizing POO Sizing Parameters Mechani~rn Ty c ETSS A
licabilih
?
I 0411.1 lligher Row Depth I IO*NDF -10.4 Axial OD!',CC
--Point'"
R~v- 0 Low Row tJ-bcnd-;
L-bends Y~s CMOA
<;y,x-19.02 N~J7,R-0.69 PDA - O.J*NUE -26.49 Sy,x = 1~.14 21409. I Suppon structures, l'r~e,pan, sludge PDA: lnl'ormalion N=9 K=0.36 Axial OD~C (
-PoiniT" U-bends Yo; Rev. 7 pile, & tuh~'heet ern tee Length; Information Length= I 14*NDE +0_0.1 Sy,x~0_21 N~9 R-0.94 D~pth - 0. 13*NDL
- 74.55 Sy.x = 14.44 22401 I l*reespan dings &
Depth: Information N=22,R=O_I3 Axial ODS( (
-PoimT" Rev_ 4 DenteJ TSP~
dented AVBs Yes Length: CMOA Length- 0_74*NDF- 0.27 s,.x~0.27
- -.J-22,R-0.62 A~ial PWSCC Depth 0_6!\\*NDF + 14.45 Sy.>. = 12.44
\\J-33. R= 0.64 20511 I Tuheshcct & non-PDA: lniOmlation PDA = 0.21 *NDF-2!1._77 A~ial PWSC('
-PointT" Rev_ R Exp~n:.ion 'Jransition>
Jented >upports Yes S).>- ~ 7.95 Length; C MOA N-32, R= 0.33 l.ength=IIO*NDL-0.()]
Sy,x=O.I3 1'-i-J2, R~ 0.87 Depth - 0.90*NDL ' 7.56 5),X = 15.2H 96703.1 Tubcshcct & non-Depth: CMOA N=40,R~O_Hl Axiul PWSCC
+l'omtTM
]{c; 17 llems
<.knted support>
Yc>
l.ength: CMOA Length -J.OO*NDL + 0.13 S),X = 0.2!1.
'-J=46,R~0_91 96511.2 Higher Ro\\'
Depth 0.56*NDF ~ 19.06 AAtal PV.-'!',('C
'Point'"
Rev. 16 Lo" Rtm L-hends U-bends Ye~
CMOA S~,x-14.97 N -24. R~ 0.66 99997.2 Higher Row Depth = 0.95*NUL-5.61 Axiali'VI'SCC
~rointT" Rc~- 10 l.ow Rtm U-benJs lJ-bends Yes CMOA Si,x = I 0_50 N = 24, R- 0_!1.5 Circ ODSCC 9
Degradation Probe EPRI Demonstrated Applicability
!':>;tended Detection?
Sizing POU Mechanism T\\' e F:TSS Applicability
?
Sizing Parameters Depth 0.13*NDL *60.10
<_;;,X = 24.5()
N=40,R=0.14 Depth: Information PDi\\ = I.02*NDF. + 21.H4 Cir~ ODSCC
- Point'"
21410.1 Lxpansion Transiuons None Ye>
Sy.x = 23.SH Rev. 6 PDA: CMOA Length: CMOA
>-.J~JH R-0.47 Length-1.24*NDF -0.42 Sy.x = 0.69 N-J~R-0.69 22842.1 Length = 0.52*NDE + 0.03 Circ OD~CC
-Point'"
Re~- 4 Dented Supports l*reespan dings Yes CMOi\\
S:.~- 0.26 N-18.R~0.75 1-:I'RI Depth 1.0*'-./DF.
TR*
PDA* CMOi\\
Sec S;.~~11.R Circ ODSCC
-Pointn*
107197-F.xpan,ion Transition; None
'>izing Depth: CviOA FPRI TR*I07197*PI PDA-1.05*NDl-0.011 PI
<; *,x = 13.43 Circ PWSCC 111524 POD: Log Logistic
('ire PWSCC
- !'oint'"
Rn.O Lxpan;ion I ransitions
!\\one Yes Nr Slop~- *20.522 lmerce t-13.733 Depth *- 0.73*t,;nr + 8.16 Sy.x-19.27
\\J = 37. R= 0.53 20510.1 PDi\\ = On*NDE - 2.!\\3 Circ 1'\\\\/<,CC
- Point'"
Rev. 7 Expansion Transitions IJ-hend<;
Ye>
CMOA Sj.X ~ 6.98 r-- = 37. R= 0.88 Length= l.01*NDF. + 0 16 S}.X ~ 0.26 N 37. R-O.R9 96511.2 lligher Ro" lkpth = 0.56*NDL
- 19.06 Ctrc PW<,CC
>Point'"
Re\\'. 16 Low Row U-bends U-bends Yes For mlimn<~tion onl}
Sy.x= 14.97 N = 24. R= 0.66 10
Degradation Probe F.PRI Demonstrated Applicability Exte11ded Detection'?
Sizing POD Si1i11g Parameters Mcchani~m T~pe F.TS~
Applieabilih-D~pth 0.!\\4*!\\DL _,_ 10.32 Sj,X ~ 9.56 N ~ 16, R= 0.92 96701 I Dents and PDA-1_0 I *NDF + 8.55 Cirt PWSCC
+Point'"
R~v. 12 L>,pansion I ran;itions tubesheel y"
CMOi\\
Sy.x ~ 7_53 N-16,R-0.90 Length= 0.91 *NUL
- 0.22 Sy,x=O.I5
~ -16.R- 0.97 99997.2 Higher Row Depth 0.95*1*>DF.
5.61 Circ PWSCC
+Point'"
R~v. 10 Low Row U-bends U-bends y"
For intOnnation only
~y.x = 10.50 N = 24. R= O_H5 Wear Tube to Jub~
\\3901.1 Freespan tube-to-tuhe wear lkpth l.04*NDL -0.91
\\V~ar
+-Point'"
R~\\*. 0 at 300 kll1 None Ye<;
CMOA
- O.y,'- = I.50 N=40R=l.O l 090H.4 Foreign ob_iect wear Depth 1.06*NDF.+O_I3
\\Vcar
+Point' Re,_ I A Vlh. Lg.gcrate; (part present)
Yo; C\\tOA Sy,x-378
]'.;=49,R-0.99
- l*oreign
+Point'" or 27901 Foreign object wear Volumetric See speciftc 1:*1 ~S [Error! Reference 115 through Free,pan Wear Ye>
CMOA source not found.F.rror!d~efcrcncc Object Wear Pancake
~7907 (part not present)
(part not pre;ent)
SOUTCf not fOUild, Pitting 21998.1 Depth I.02*NDL
- 5.!\\1 Pitting
+Pomt'"
Re' 4 VollUnetnc in li'cespan Sludge Pile Yes CMOA Sy.x = 6.2g
'J-63, R- 0.94 Specialh* Probes I'D A 0.38*"-JLll::. 35.<12 lloth: CMOi\\
~y,),= 14.92 20407_1 1"=26 R=0.42 Ax1al ODSCC Ghent**
Rev_ 7 Support structure~ & freespan None Yes i\\vg_ Dcpthll.t:ngth applies to teehmque I.~ngth - 0.33*NDF +0.36 Sy.x = 0.13 N=26R=0.48 CMOi\\
Length= 2.0g*NDL -0.29 20508_1 Axial PW~CC Ghent**
Rev. 6 Lxpan;ion Transition~
None Yes I.cngth applie' to Sy,x=O.l5 tcehni ue N-32 R~O.!\\
Axiali'WSCC Ghent**
20509_1 Dented <;upport structures None Yes Not qualilicd Rev_ 'i 11
Dl"gradation Probe EPRI L>cmonstnkd Applil"ahility Enended Detection?
Sizing POD Si1ing Parameters Mechani~m T,pe ETSS Applicabilih*
Depth O.S5*NDL+35.18 S}.X-24.02 N~n R-(l.52 C~OA Ungth = 1.81 *NDF -0.07 Circ ODSCC (jhcnt**
20406.1 Top oftubeshcet & expansion None y"
- -.oy.x = 0.54 Rev. 7 transitions Depth/ Length/ PDA N=22 R=0.78 apply to technique PDA-1.34*NDL I 13.72 S}.>-- 23.9H
- -.J=22 R~0.5H Depth O.<J*)'.;DL 11.91
<;),X~ 13_43 N-21 R~0.79 20507.1 Ungth = O.H*NDL I 0.34 Circ f'WSCC Gh~nl**
Re,_ h Expansion l ran:.ilion<>
None Yes CMOA Sy,x = 0.27 N-21 R=0.79 f'DA- 0.99*NDF -4.64
- -.oy,x = 6.37 l\\=21 R=0.87 Notes for Table 9-1
- There are multiple ETSSs available for depth s1zing of foreign object wear, each depending on the shape of the wear scar and the coil being used. If foreign object wear {w1th no part present) is reported, an appropriate +Point' or pancake coli technique will be selected for performing CMOA The associated NDE uncertainties and CMOA limits will be documented in the CMOA report.
- The Ghent probe will only be used if needed for clarification of the eddy current response or for additional sizing information associated with unusual or unexpected indications 12
Vice President, Operations Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043-9530 April 30, 2014 SUBJECT
SUMMARY
OF CONFERENCE CALL WITH PALISADES NUCLEAR PLANT REGARDING THE FALL 2014 STEAM GENERATOR INSPECTIONS (TAC NO. MF3196)
Dear Sir:
On February 3, 2014, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with representatives of Entergy Nuclear Operations, Inc. (the licensee) regarding the steam generator (SG) inspection activities at Palisades Nuclear Plant On December 6, 2013, the licensee was provided with the list of questions (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13343A185), to discuss the ongoing results of the SG tube inspections prior to completion of the inspections and repairs conducted during the Palisades Nuclear Plant refueling outage. The information provided by the licensee in support of the teleconference is part of the enclosed conference call summary.
Based on the information provided by the licensee, the NRC staff did not identify any issues that warranted immediate follow up action. However, the staff asked to be notified in the event that any unusual conditions were detected during the remainder of the outage. If you have any questions regarding this matter, I may be reached at 301-415-8371.
Docket No. 50-255
Enclosure:
Conference Call Summary cc: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-1 RIF RidsNrrDoriDpr Resource RidsNrrLAMHenderson Resource AJohnson, NRR Sincerely, IRA!
Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsAcrsAcnw_Ma1ICTR Resource RidsNrrDorllp13-1 Resource RidsRgn3MaiiCenter Resource RidsNrrDssSrxb Resource RidsNrrPMPal1sades Resource KKarwoski. NRR