ML060530454

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Fax from Licensee Regarding 2005 Steam Generator Tube Inspections at Salem, Unit 2
ML060530454
Person / Time
Site: Salem PSEG icon.png
Issue date: 02/20/2006
From:
Public Service Enterprise Group
To:
Office of Nuclear Reactor Regulation
References
TAC MC6729
Download: ML060530454 (5)


Text

Apr-ZU-Ub UM:bUpm From-FSEU NUCLEAR LLC Mb3391I440 1-b44 P.0U/05 F-900 Salem Unit 2 R14 Responses to NRC SG Tube Inspection Discussion Points

1. During Cycle 14, primary to secondary leakage was less than I gpd. However, a few Steam Generator Gross Activity measurements were not below detection limits. In addition, gamma activity was detected on condensate polisher anion resin samples that were checked for radioactivity prior to shipment to a laboratory for resin condition evaluation. These are possible indications of a miniscule quantity of RCS escaping to the Secondary Cycle.
2. No secondary side pressure tests have been performed during 2R14.
3. No new deviations have been taken to the EPRI Industry Guidelines during RF014.

The following is a list of the deviations taken during previous inspections that are being taken again during 2R14:

  • Level III SSPD Exemption
  • Analyst Performance Monitoring
  • Calibration Standard Flaws
  • Transfer Standard Voltage
  • Process Control Requirements The technical justification for all of these exceptions has been document as required in Appendix D of NEI 97-06. Equivalencies have also been performed and documented to ensure that the techniques utilized in 2R14 are not adversely affected.
4.

See the Table below, "Summary of 2R14 SG Base Scope Tube Inspection Plans",

for a summary of the inspections performed during outage 2R14. Expansions are in accordance with the EPRI PWR Examination Guidelines Rev 6.

5. See the Table below, "Salem 2RM4 Summary of Tube Degradation", which provides degradation detected To date. Information related to the severity of the indications is also provided. Performance criteria were met at EOC 14 for all degradation detected to date. No new or unexpected degradation detected at this time.
6. All tubes with crack-like indications and those exhibiting greater than or equal to 40%TW cold leg thinning or AVB wear will be repaired by plugging.
7. No tube pulls or in-situ testing is planned at this time.
8. SG eddy current estimated to be completed by 4/22/2005 - 4/23/2005, followed by tube plugging.

SG manway installation is targeted for approximately 4/24/2005.

Apr-20-05 03:50pm From-PSEG NUCLEAR LLC e5633s1448 T-544 P. 03/06 F-988

9. Loose Parts:
a. During the ECT inspections, the bobbin coil data is screened for PLPs (possible loose parts) and tube degradation. Additionally, the rotating coil

(+Point) data is reviewed for PLPs or wear associated with PLPs.

In addition to the eddy current inspections, secondary side visual inspections were also performed in all four steam generators.

These inspections were performed after sludge lancing and included top of tubesheet inspections of the annulus and the divider lane and included a minimum of five inner bundle passes. The visual inspections also include all locations of eddy current PLPs at the top of the tubesheet.

b. A large portion of the loose parts detected were metal curls or turnings.

This is especially true at Ihe top of the hot leg tubesheet in SG24. These curls range up to about 2 inches long, however are predominantly in the range of approximately 1/2 inch. Metal rods up to about 1/41"4 diameter and about 2" long were detected A few pieces of wire were also detected.

Some parts were located in the inner bundle at the top of the tubesheet.

Most of the parts, however, were located in the annulus region at the top of the tubesheet.

c. Several foreign objects have been removed from the Salem Unit 2 SGs, work efforts are still in progress.
d. No eddy current indications of wear from foreign objects detected at the time of this letter.
e. The feedwater system maintenance activities from previous outage(s) are suspect for the source of the foreign objects.

Apr-20-05 03:51Pm From-PSEG NUCLEAR LLC 8563391449 T-544 P.04/06 F-98U Summary of 2R14 SG Base Scopc Tube Inspection Plans Area Probe Inspection Full Lngth I00% of a)] in-service tubes in each steam I

Ful Length Bobbin generator with exception of tubes inspected in U-(lube end to tube end) bends with RC Probe (see DA)

-ends T

100% of all in-servicc U-bcnd tubes in Rows 2

2 U-ed m7l) through 10. and 20% of Rows 13 through 17 in

__(_

to__7_)

___each steam generator 100% of all in-scrvirc tubes in the HL in each

.3 WEXTEX TTS

+Point" steam generator Extent is +3" above TTS and -" below TTS 4

Tubcsheet Anomalies

+Point:TM Inspcct all 2R13 historical tubesheem anomalies (HL & CL) 100% of the => I volt dented TSP locations at PWSCC 011-, 021, 0311 and 20% sample of 04H in cah 5

for

+Pointru SG.

Dcnted TSP Intersections I V) 100% of the I>

volt dcntcd AVB locations in thc U-bend ODSCC 6

for

+PointTu 25% of the > 5 volt dented TSP locations at 04H Dented TSP Intersections to 07H. in cach SO.

(_ 5 V)

SuspctedTSPLigaent Bobbin 7

SUSJCrac1kinTSgPLLClt S

and 100% +Point of all previously identificd SLC CrackinginSLC) 25% inspection of the ->2 volt HL dings in each Free Spun Bobbin Indications

+Poin7 SG from TSH1 +0.5" to 07H + 2.0" (DinIs) 100% inspection of the =~'2 volt dings in each SG within the U-bend region (07H to 07C)

Visual inspection of 100% of the installed rube Visual plugs in e.ch steam generator.

9 Tube Plugs pnc

+Point inspection of 4 tube plugs (SO 21 R2 C45

+Poitn T

and SG 24 R2 C3), HL and CL as discussed in thc

)DA Visual SSI and NDE Level III rcvicw of ECT data 1AW Vad DA (sections 7.1.2 and 7.6):

10 Special Interest Base Scope Bobbin SG 21 R2 C45 and/or SG 24 R2 C3

+Point SG 24 RIS C92

Apr-20705 03:51pm From-PSEG NUCLEAR LLC 1-b44 F-M. b/

SALEM UNIT 2 R14 Preliminary Repairable Indication and Tube Status Report

-L 11nTube I

Steam Generator Tota Location l

Degradation J 2-1 I 2-2 ll 2-3 2-4 Tt Axial PWSCC 1

1 2

1 z_

Axial ID/Axial OD_

Circ PWSCC TSP Circ ODSCC 1

I Axial GDSCC i 5c Mixed Mode Axial OD/Circ, Mixed Mode Axial ID/Circ 1

1 Axial PWSCC in W* Length 10 5

21 36 Axial ODSCC TTS I

2 2

5 Tubesheet Circ PWSCC @ TrS Circ ODSCC c ITS 2

2 I

Volumetric OD 17TS 2

2 Axial PWSCC (IncIs)

Axial ODSCC (lncis U-bends Circ PWSCC (Inds)

Innermost/Outermost Rows with Degradation High Row U-bends AVB Wear >=40'%

2 1

3 Cold Leg Thinning Thinning >=40%D 1

5 6

Free Span Confirmed Indications Misc.

Preventative Total Pluggable Indications 18l 1

32 s0 Total Tubes to Plug 17 9

1 30 57 This table shows the number of indications with each type of degradation (not the number of tubes).

Status: As of 4/20/2005, 12 pm.

Apr-20705 03:51rm From-PSEG NUCLEAR LLC B563391448 T-544 P.05/05 F-988 Salem 14RFO 2005 Axial Indications SG Row Tube Ind Volts TSP Inch Probe Depth %TW Ax Len Dog. Mode 24 20 22 SAI 0.73 TSH

-0.2 720PP 24 0.05 WEXTEX PWSCC 24 39 22 MAI 0.64/0.40 TSH

-0.16/-0.28 720PP 46/56 0.16/0.12 WEXTEX PWSCC 24 6

42 SAI 0.51 TSH

-0.09 720PP 40 0.06 WEXTEX PWSCC 24 7

27 SAI 0.43 TSH

-0.28 720PP 28 0.1 WEXTEX PWSCC 24 32 58 SAl 0.43 TSH

-1.4 720PP 41 0.09 WEXTEX PWSCC 24 8

2 SAI 0.81 01H

-0.02 72OPP 40 0.23 TSP PWSCC 24 10 39 SAl 0.3 O1H

-0.14 720PP 40 0.08 TSP ODSCC 22 3

70 SAI 0.3

_1H

-0.26 720PP 19 0.05 TSP PWSCC Circumferential Indications SG Row Tube Ind Volts TSP Inch Probe Depth %TW Are Len Deg. Mode I

I(max) 21 13 29 MCI 0.1/0.15 TSH 0/-0.01 720PP 1311 23J41 dog ODSCC 21 14 29 SCI 10.12 TSH

-0.07 72OPP 11 74 deg ODSCC 21 37 57 SCI 0.12 03H 0.08 720PP 19

_31 deg ODSCC Circ/Axial Indication at Same Location SG Row Tube Ind Volts l TSP Inch Probe D(mah) lTW Afc Len l

_Deg. Mode_l 21 6

2 SCI 0.63 l

01H 0.25 720PP 62 J 38 deg PWSCC SAI 0.35 01H 0

720PP 51 1

0.14 PWSCC Repairable Bobbin Calls By Depth SG Row Tube

%TW Volts TSP Inch Probe Deg. Mech 22 43 60 54 0.45 02C 0

72OULC CLT 24 43 34 47 0.71 03C 0.05 72OULC CLT 24 43 34 45 1.12 02C 0.05 72OULC CLT 21 23 68 43 3.32 AV2

-0.45 72OULC AVB Wear 24 30 83 42 1.51 01C

-0.09 72OULC CLT 24 43 59 42 1.53 01C

-0.04 72OULC CLT 24 33 78 41 2.23 02C 0.16 72OULC CLT 21 36 52 40 3.12 AV2

-0.53 72OULC AVB Wear 23 40 54 40 2.76 AVi 0.52 72OULC AVB Wear I~

a

-'I a

Preliminarv Status: As of 4/20/2005. 12 omr.