ML15294A292

Summary of Conference Call with Palisades Nuclear Plant Regarding the Fall 2015 Steam Generator Inspections

ML15294A292
Person / Time
Site:	Palisades
Issue date:	10/27/2015
From:	Jennivine Rankin Plant Licensing Branch III
To:	Entergy Nuclear Operations
Rankin J, NRR/DORL/LPLIII-1
References
CAC MF6993
Download: ML15294A292 (19)

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 October 27, 2015

SUMMARY

OF CONFERENCE CALL WITH PALISADES NUCLEAR PLANT REGARDING THE FALL 2015 STEAM GENERATOR INSPECTIONS (CAC NO. MF6993)

Dear Sir or Madam:

On October 2, 2015, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with representatives of Entergy Nuclear Operations, Inc. regarding the ongoing steam generator (SG) inspection activities at the Palisades Nuclear Plant.

A list of the conference call participants is contained in Enclosure 1. A list of discussion questions were discussed on the call and are attached to the enclosed conference call summary in Enclosure 2. 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 including whether any in-situ pressure tests were performed.

If you have any questions regarding this matter, I may be reached at 301-415-1530.

Docket No. 50-255

Enclosure:

1. List of Participants

2. Conference Call Summary cc: Distribution via ListServ Sincerely, ennivine Rankin, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

LIST OF PARTICIPANTS OCTOBER 2, 2015, CONFERENCE CALL WITH ENTERGY NUCLEAR OPERATIONS, INC.

PALISADES NUCLEAR PLANT FALL 2015 STEAM GENERATOR INSPECTIONS NUCLEAR REGULATORY COMMISSION Andrew Johnson Ken Karwoski Alan Huynh Jennie Rankin Mel Holmberg April Nguyen ENTERGY NUCLEAR OPERATIONS, INC.

Dustin Daggett Tim Crocker Jake Milliken Jeff Erickson Jim Miksa Barb Dotson Dan Meatheany Celeste Bell Kent Colgan

CONFERENCE CALL

SUMMARY

REGARDING PALISADES NUCLEAR PLANT FALL 2015 STEAM GENERATOR INSPECTIONS DOCKET NO. 50-255 CAC NO. MF4714 On October 2, 2015, the U.S. Nuclear Regulatory Commission (NRC) staff 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 (Palisades). The licensee-provided attachment is included at the end of this conference call summary. The data in the attachment is preliminary.

Palisades has two Combustion Engineering Model 2530 replacement SGs. Each SG has 8,219 mill-annealed Alloy 600 tubes with an outside diameter of 0.750 inches and a wall thickness of 0.042 inches. Stainless steel, eggcrate, lattice-type tube supports, diagonal straps, and vertical straps support the tubes at various locations. The tubes were expanded through the full depth of the tubesheet using an explosive process.

Undefined abbreviations used in the licensee-provided document (Attachment 1) include:

1 R22 - Unit 1 Refueling Outage 22 ODSCC - Outside Diameter Stress

• CL-Cold Leg Corrosion Cracking CM - Condition Monitoring psi - pounds per square inch CMOA - Condition Monitoring PWSCC - Primary Water Stress Operational Assessment Corrosion Cracking DB - Diagonal Bar RF24 Refueling Outage 24 ECT - Eddy Current Testing SAi - Single Axial Indication EFPY - Effective Full Power Year SCI - Single Circumferential EPRI - Electric Power Research Indication Institute SGMP - Steam Generator GPO - Gallons Per Day Management Program HF - High Frequency SVI - Single Volumetric Indication

• HL-Hot Leg TEC - Tube End Cold IQDA - Independent Qualified Data TEH - Tube End Hot Analyst TR -Topical Report ISi - lnservice Inspection TRA - Trackable Anomaly MR - Mid-Range TSC - Top of Tubesheet Cold NIA - Not Applicable TSH - Top of Tubesheet Hot NOE - Non Destructive Examination

• TW - Through Wall NRC - Nuclear Regulatory

• V-Volts Commission Vpp - Volts Peak-to-Peak

• VS - Vertical Strap Information exchanged during the call and not included in the licensee-provided information is summarized below:

The indications identified during the inspection are not considered to be large enough to contribute to primary-to-secondary leakage. The source of the primary-to-secondary leakage has not been identified.

Visual inspections of all installed plugs did not identify any potential leakage from the plugged tubes. There are about 500 to 600 plugs in each SG.

The licensee performed visual inspections in accordance with Westinghouse Nuclear Safety Advisory Letter 12-1 during the previous outage. During refueling outage 24, as-found visual inspections were performed in all four channel heads. No degradation was identified.

At the time of the call, the licensee had yet to begin their special interest examinations.

The largest crack indication was identified near the top of the tubesheet in SG A and was 0.83 V. The indication is less than 0.25 inches long and had a maximum depth of approximately 64 percent TW. The licensee expects that the indication does not compromise tube integrity.

During the call, the licensee identified an error in their reply to item 6. The number of potential tubes requiring tube plugging in SGs A and B were corrected to 9 and 4 instead of 10 and 5, respectively. The correction has been made in the licensee-provided attachment of this enclosure.

The ISi referenced in question 9 is related to a SG nozzle.

The licensee plans to communicate its operating experience with auto analysis to the industry.

If any loose parts are left in the SGs, the licensee assesses their significance to ensure it is acceptable to leave the parts in the SG until the next inspection.

The NRC staff did not identify any issues that required follow-up action at this time.

STEAM GENERATOR TUBE INSPECTION DISCUSSION DURING PALISADES 2015 (RF24) OUTAGE (Preliminary Information)

0 STEAM GENERATOR TUBE INSPECTION DISCUSSION DURING PALISADES 2015 (RF24) OUTAGE (Preliminary Information)

Currently Palisades is - 80% through the base scope eddy current inspection and starting the special interest as of 10/1/2015 at - 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />

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 Operational Cycle 24 Primary to Secondary Leak Rate 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 2015 refueling outage (RF24).

3. Discuss any exceptions taken to the industry guidelines.

In 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 NOE 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 NOE maximum depths.

0

0 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.

Full length ECT bobbin coil examination of all in-service tubes (except row 1, 2, and 3 U-bends) in both SGs.

ECT +Point' coil examinations (both SGs):

100% of rows 1, 2, and 3 U-bends.

100% of hot leg from TTS + 3" to a minimum of 13.5" below the bottom of the expansion transition.

100% of free span dings >5V between TSH and TSC.

100% of >2V dents at egg crate, diagonal bar, and vertical strap intersections between TSH and TSC.

25% of historical % TW calls at diagonal bars and vertical straps 100% of historical TRA indications 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.

The expansion criteria for each degradation is attached to the back in tables 9-1 through 9-4.

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 0

0 As of 10/1/2015@ 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> Number Number Integrity SG Location Type Indications Tubes Acceptable Axial A

TSH ODSCC 6

6 YES*

Axial A

TSH PWSCC 0

0 NIA Circ A

TSH PWSCC 0

0 N/A Circ A

TSH ODSCC 1

1 YES*

A TSH Volumetric 2

2 YES*

A TEC to TEH Wear> 40 0

0 N/A Axial B

TSH ODSCC 4

4 YES*

Axial B

TSH PWSCC 0

0 N/A Circ B

TSH PWSCC 0

0 NIA Circ B

TSH ODSCC 0

0 N/A B

TSH Volumetric 0

0 N/A B

TEH to TEC Wear> 40 0

0 N/A Tube Axial A

Supports ODSCC 0

0 N/A Axial A

Frees pan ODSCC 0

0 N/A Tube Axial B

Supports ODSCC 0

0 N/A Axial B

Freespan ODSCC 0

0 N/A

• Expectation based on voltage and sizing performed to date SGA 6 OD SAls, all at TTS sludge pile on hot side (TSH+0.3" to 1.16") (see plot) 1 OD SCI, at TSH 3

0

0 0

0.83 v o

Max circumferential extent 0.38" (62 degrees) o Max depth 83 % TW o Not structurally challenging o

No depth profile sizing yet 2 foreign object wear flaws (SVls) o No sizing yet.

o We will attempt to remove the object, and then size them.

SG B 4 OD SAls, all at TTS sludge pile on hot side (TSH+0.43" to 1.27")

o Voltages are less limiting than the 3 largest in SG A.

o No sizing yet.

No foreign object wear Both SGs - Support Structure Wear No plugging expected Average growth rate is essentially zero 95/50 growth rate is -3 % TW/EFPY Frees pan There is no free span repairable indications reported to date.

LI-Bends There are no U-bend repairable indications reported to date.

6. Describe repair/plugging plans.

Currently there are 9 potential tubes requiring tube plugging in SG E-50A and 4 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.

4 0

0

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.

8. Discuss the following regarding loose parts:

What inspections are performed to detect loose parts?

The hot leg top 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 10/1 /2015 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-508 192 PLP Calls in 131 Tube Locations 102 PLP Calls in 76 Tube Locations The majority of the indications is historical and has not changed. Visual inspection with FOSAR has been completed in SGB. Anticipate FOSAR in SGA on 10/2/2015 If the loose parts were removed from the SG SG E-50A It is anticipated that FOSAR will start in SG E-50A on 10/2/2015.

SG E-508 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.

Several locations were identified and visually inspected. There were a few new parts identified from last outage. Most were identified as demister wire/sludge.

One location in SGB CL was determined to be a sludge rock. An attempt to remove it was unsuccessful.

5 0

0 Indications of tube damage associated with the loose parts Currently there is 1 location in SGA that has 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.

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).

Sludge lancing was not performed.

There is an ISi inspection (W0-384812) in E-50A which is being supported by the SG Project. This inspection is not part of the SGMP inspections.

10. Discuss any unexpected or unusual results.

An attempt was made to run one of the analysis systems in auto for the tube sheet region. Based on the manual analysis and IQDA inspections, it appears that the Auto system missed an axial crack at the sludge pile. The crack is - 0.8 volts. It is still being sized. The auto systems was adjusted to find this type of flaw but manual analysis of the remaining tubes and those affected by the auto analysis is being performed instead.

Currently there are no other 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.

Once the remainder of the base - bobbin and top of tube sheet, are complete, the special interest test will be performed.

Anticipate complete ECT on 10/4/2015 Anticipate complete repair on 10/6/2015 Anticipate closeout on 10/7/2015 Nozzle dam removal and manway installation on 10/7/2015 6

0

0 Steam Generator Degradation Assessment for Palisades 1 R24 Inspection, Fall 2015 The following is the Primary to Secondary Leak Trend for the Last Fuel Cycle Note: Units in Gallons per Minutes 0.0010 0.0009 0.0008 0.0007

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0 Steam Generator Degradation Assessment for Palisades 1 R24 Inspection, Fall 2015 The following is a trend of the Main Condenser Off-Gas Rad-Monitor in GPD 5.0 4.5 4.0 3.5 3.0 2.5 2.0 1.5 l Apr Jul 2014 ROS-test All available data points between 0311912014 00:00 and 09/1612015 23:59 PLP:1:PCS Gas:Verification of SIG leak Rate - RIA-0631:

Oct Jan 2015 Time Apr Jul 0

0 Table 9-1: Inspection Scope Summary - Wear 0

Steam Generator Degradation Assessment for Palisades 1 R24 Inspection, Fall 2015 e

Location E/P Probe/ ETSS Scope Expansion I Comments Mech.

D/S Wear Egg crates E/D/S Bobbin I 96004.1 100% bobbin except row 1-3 u-bends.

ff.Point all new wear, all wear ~40%TW, all bobbin I-codes DBNS E/D/S

+Point 10908.4 100% +Point row 1-3 u-bends.

P(SCC)/

+Point I

+Point all eggcrate wear, and 25% of DBNS wear not If SCC is coincident with significant DBNS wear, then D

(see sec sections) previously inspected, in order to detect any sec coincident

+Point all DBNS wear in the affected SG. In-situ testing with wear.

Will be required per CDME-07-119 Dented VS/DB (S E/D Bobbin I 100% bobbin except row 1-3 u-bends. Identifies coincident

+Point all bobbin I-codes and all bobbin indications 5Vpp) 96004.1

~ear and denting (see [3.e))

of coincident wear and denting E/D/S

+Point 10908.4 100% +Point row 1-3 u-bends, plus all bobbin indications of

~oincident wear and denting. (see CDME-07-119)

Dented VS/DB (>

+Point 10908.4 Apply this technique to all VS/DB dents >5Vpp reported by If wear cannot be sized (depth or voltage), then in-situ 5Vpp)

E/D/S bobbin probe to ensure detection and sizing esting will be required of wear (see CDME-07-119)

Tube to Tube E/D/S Bobbin I 100% bobbin except row 1-3 u-bends.

+Point all new wear, +Point all bobbin I-Codes Contact Wear 13091.1

+Point 13901.1

+Point row 1-3 u-bends.

E/D/S

+Point highest eggcrate through the square bend for the tubes surrounding R99 C140 in SGB EID Bobbin I 100% bobbin and FOSAR both SGs.

+Point all bounding tubes with loose part wear or loose Loose Part Wear 27091.2 part indication or visually detected loose part

+Point 27901-127901 thru 27907 when loose part not present (CMOA)

E/D/S 27907 10908.4 10908.4 when loose part present (CM)

Table 9-2: Inspection Scope Summary - Axial ODSCC/PWSCC 0

0 Steam Generator Degradation Assessment for Palisades 1 R24 Inspection, Fall 2015 Damage Location

~p Probe/ ETSS Scope Expansion I Comments Mech.

PIS Axial E/D Bobbin I 100% bobbin except row 1-3 u-bends.

+Point all bobbin I-Codes ODS CC Non-dented and 28413 s 2Vpp Dented I+ Point/

Eggcrates DBNS

~D 28425 l+Point inspection of all bobbin I-Codes for ODSCC detection Freespan EIS

!+Point I f+Point depth and length sizing of detected ODSCC 128432 f+Point Row 1-

!+Point/

r,3 U-bends P/D/S 10411.1 100% +Point row 1-3 u-bends.

+Point sizing of any low row indications.

EID Bobbin I 100% bobbin except row 1-3 u-bends.

+Point all bobbin I-Codes Freespan Ding

~4013.1

~5Vpp E/D/S I+ Point I

+Point inspection of bobbin I-Codes at dinged freespan locations for 122401.1 PDSCC detection, and length sizing of detected ODSCC.

Freespan Ding

>5Vpp E/DIS I+ Point I l+Point inspection to detect and length size axial ODSCC at 122401.1 dinged and dented locations.

Dented >2Vpp Egg crates DBNS

~ludge Pile and E/D

!+Point/

+Point 100% H/L TTS +3" to 13.5" below the bottom of the expansion

+Point 100% of region in affected SG; ensure 20%

28424 ransition; +Point inspection of cold leg bobbin I-Codes nspected in the other SG Exp Transition EIS

!+-Point/

+Point inspection for depth and length sizing of detected Axial 128431 ODSCC indications at the sludge pile and expansion transitions.

E/D/S I+ Point I (MR)

Axial Row 1-3 U-

~6511.2 100% +Point Row 1-3 u-bends f sec is detected in row 3, then inspect all u-bends in row 4 PWSCC bends

!+-Point I (HF) of the affected SG, and 20% of row 4 in the unaffected SG.

E/D/S 99997.2 Dented Egg crates P/D/S

!+-Point I I+ Point all >2Vpp dents at structures and dings >5Vpp in If an indication is detected, then a scope expansion will be DBNS 96703.1 reespan; +Point inspection of bobbin I-Codes determined based on the dent voltage and significance of the Dinged indication.

Frees pan Tubesheet and

!+-Point I

+Point 100% H/L TTS +3" to 13.5" below the bottom of the

+Point 100% of region in affected SG; ensure 20%

Exp Transition

~/DIS expansion transition; +Point 120511.1 nspection of cold leg bobbin I-Codes nspected in the other SG

0 Table 9-3: Inspection Scope Summary - Circumferential ODSCC/PWSCC 0

Steam Generator Degradation Assessment for Palisades 1 R24 Inspection, Fall 2015 Pamage

~ocation E/P Probe/ ETSS Scope Expansion I Comments IMech.

D/S Row 1-3 U-P/D/S

+Point I 22842.1 &

100% +Point row 1-3 u-bends If SCC is detected in row 3, then inspect all u-bends in row 4 K;ircODSCC bends

?1410.1 pf the affected SG, and 20% of row 4 in the unaffected SG Dented Egg crates P/D/S

+Point I 22842.1 &

+Point all >2Vpp dents at structures and dings >5Vpp If an indication is detected, then a scope expansion will be DBNS 21410.1 in freespan; +Point inspection of bobbin I-Codes; determined based on the dent voltage and significance of Dinged the circumferential indication Freesoan TIS and

+Point/

+Point 100% H/L TTS +3" to 13.5" below the bottom of the Expansion E/D/S 21410.1 expansion transition; +Point inspection of cold Transition leg bobbin I-Codes fl-Point 100% of region in affected SG; ensure 20%

Expansion

+Point I EPRI TR-nspected in the other SG rrransition EIS 107197-P1 Sizing of circumferential indications per EPRI TR-107197-P1 K;irc P/D

+Point (MR) I 100% +Point row 1-3 u-bends Row 1-3 U-96511.2 f sec is detected in row 3, then inspect all u-bends in row 4 PWSCC bends P/D

+Point (HF) I pf the affected SG, and 20% of row 4 in the unaffected SG 99997.2 Dented D/D r1-Point I

+Point all >2Vpp dents at structures and dings >5Vpp in Egg crates 11524

• reespan; +Point inspection of bobbin I-Codes If an indication is detected, then a scope expansion will be DBNS. Dinged

+Point I determined based on the dent voltage and significance of Freespan D/S 96701.1 Sizing of circumferential PWSCC the circumferential indication D/D

+Point I 100% +Point row 1-3 u-bends Row 1-3 U-11524 If SCC is detected in row 3, then inspect all u-bends in row 4 bends

+Point I pf the affected SG, and 20% of row 4 in the unaffected SG P/S 20510.1 Sizing of u-bend circumferential PWSCC EID

+Point I ITTS and Exp 11524

+Point 100% H/L TIS +3" to 13.5" below the bottom of the

+Point 100% of region in affected SG; ensure 20%

!Transition

+Point I expansion transition; +Point inspection of cold leg nspected in the other SG E/D/S bobbin I-Codes 96701.1

0 Steam Generator Degradation Assessment for Palisades 1 R24 Inspection, Fall 2015 0

Table 9-4: Inspection Scope Summary-Pitting Damage Location E/P Probe/ ETSS Scope Expansion I Comments Mech.

DIS P/D Bobbin I 100% bobbin exam of the region

~Point all bobbin I-Codes Pitting Sludge Pile saoos.2 P/S f+Point I

+Point sizing of detected pitting

~1998.1

ML15294A292

• via memo OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA DSS/SCVB/BC NRR/LPL3-1/BC NRR/LPL3-1/PM NAME JRankin MHenderson GKulesa*

DPelton JRankin DATE 10/26/15 10/26/15 10/15/15 10/27/15 10/27/15