CP-201100772, Response to Request for Additional Information, Relief Requests Nos. B-10 and B-11

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Response to Request for Additional Information, Relief Requests Nos. B-10 and B-11
ML11173A064
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 06/15/2011
From: Flores R
Luminant Generation Co, Luminant Power
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CP-201100772, TAC ME5217, TAC ME5218, TXX-11071
Download: ML11173A064 (14)
v • d • e


Text

Rafael Flores Luminant Power Senior Vice President P 0 Box 1002

& Chief Nuclear Officer 6322 North FM 56 Rafael.Flores@ Luminant.com Glen Rose, TX 76043 Luminant T 254 897 5550 C 817 559 0403 F 254 897 6652 CP-201100772 Ref. # 10CFR50.55a Log # TXX-11071 June 15, 2011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NO. 50-445 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION, RELIEF REQUESTS NOS. B-10 AND B-11 (TAC NOS. ME5217 AND ME5218)

REFERENCES:

1. Letter logged TXX-10157 dated December 15, 2010 from Rafael Flores to the NRC submitting Relief Request No. B-10 for the Unit 1 Second 10 Year ISI Interval from 10 CFR 50.55a Inspection Requirements due to Physical Interferences (Second Interval Start Date: August 13, 2000).
2. Letter logged TXX-10158 dated December 15, 2010 from Rafael Flores to the NRC submitting Relief Request No. B-11 for the Unit 1 Second 10 Year ISI Interval from10 CFR 50.55a Inspection Requirements due to Physical Interferences (Second Interval Start Date: August 13, 2000).
3. Email dated May 16, 2011 from Balwant Singal of the NRC to Jack Hicks of Luminant Power requesting additional information regarding Relief Request Nos. B-10/B-11.

Dear Sir or Madam:

Per references 1 and 2, Luminant Generation Company LLC (Luminant Power) previously submitted requests for relief from the applicable requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, as identified in the referenced relief requests.

Luminant Power has determined that certain inspection requirements of ASME Section XI are impractical due to physical interferences. Per reference 3, the NRC provided a request for additional information regarding the subject relief requests.

Luminant Power has provided the information requested per reference 3 in the attachments to this letter.

This communication contains no new commitment regarding Comanche Peak Unit 1.

A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

  • Comanche Peak - Diablo Canyon - Palo Verde
  • San Onofre
  • South Texas Project - Wolf Creek A&W7

,UJ6

U. S. Nuclear Regulatory Commission TXX-11071 Page 2 of 2 Should you have any questions, please contact Mr. Jack Hicks at (254) 897-6725.

Sincerely, Luminant Generation Company LLC Rafael Flores By: 21" 22 -,-.

/Frre W. Madden Director, Oversight & Regulatory Affairs Attachments 1. Response to Request for Additional Information

2. Relief Request B-11 Sketch and Data Sheets c - E. E. Collins, Region IV Ms. Alice Rogers B. K. Singal, NRR Environmental & Consumer Safety Section Resident Inspectors, Comanche Peak Texas Department of State Health Services Brian Welch, ANII, Comanche Peak 1100 West 49th Street Austin, Texas 78756-3189 to TXX-11071 Page 1 of 3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST NUMBERS B-10 and B-11 FOR THE UNIT 1 SECOND 10 YEAR ISI INTERVAL FROM 10 CFR 50.55a INSPECTION REQUIREMENTS DUE TO PHYSICAL INTERFERENCES (SECOND INTERVAL START DATE: AUGUST 13, 2000) (TAC NOS. ME5217 and ME5218)

The following questions were provided to Luminant Power in the email dated May 16, 2011 from Balwant Singal of the NRC to Jack Hicks of Luminant Power (reference 3) requesting additional information regarding Relief Request Nos. B-10 and B-11:

NRC Question 1:

Please provide material specifications for the weld TBX-1-4201-9 and TBX-1-4201-10 and associated pipe and elbow in RR B-10. Provide the material specifications for weld TBX-1-4300-13 and safe end, in RR B-11.

Luminant Power's Response to Question 1:

TBX-1-4201-9 and TBX-1-4201-10 Pipe welds Line: 10"-SI-1-180-2501R-1 Pipe: 10" diameter, sch. 140; material: SA376, Type 304 stainless steel TBX-1-4300-13 Reactor Vessel safe-end to pipe weld Line: 27.5"-RC-1-042 Pipe: 27.5" diameter, 2.21" thickness; material: SA-351-CF8A Safe-end: material: SA-182, Type F316 stainless steel NRC Question 2:

It appears that the subject welds in RR B-10 are associated with the safety injection system piping.

However, the examination sheets identify the piping system as accumulator discharge. Please identify the exact piping systems for subject welds in RRs B-10 and B-11.

Luminant Power's Response to Question 2:

The piping system is safety injection. The examination data sheets took the component/system description (accumulator discharge) from the description found on the ISI sketch, TBX-1-4201.

NRC Question 3:

For RR B-10, would it be possible to remove the structural restraints to increase the examination coverage? Please clarify.

Luminant Power's Response to Question 3:

The structural restraint, an obstruction when conducting the volumetric examination, is a pipe support for the safety injection line and is attached to the lower structural beam for Steam Generator #2. This restraint cannot be easily removed. Removal would have required a temporary support (s) for the safety injection line. Additional dose would also be obtained during the removal /reinstallation of the restraint and temporary support.

Attachment I to TXX-11071 Page 2 of 3 This piping configuration was the same in all four loop rooms, with this line selected because more weld volume could be obtained by examining these two welds. This fact was determined by field walk downs.

NRC Question 4:

For RR B-10, did Luminant Generation Company LLC consider using longitudinal waves to examine past the centerline in the area currently limited from examination, thus increasing the examination coverage?

Please clarify Luminant Power's Response to Question 4:

Longitudinal wave examinations for the subject welds would not improve/generate additional volumetric coverage. The subject welds were examined from two sides in both the axial and circumferential directions on all accessible sides/directions.

NRC Question 5:

Section 3 of RR B-10 states that "...The subject pipe size is 10" and Table IWB-2500-1 calls for a surface examination of the weld..." Please discuss whether a surface examination has been performed in the inside or outside surface of the subject welds. If no, please justify why a surface examination was not performed.

Luminant Power's Response to Question 5:

Per the second paragraph under Section 3 of Relief Request B-10, CPNPP has adopted RI-ISI for ASME Code Class 1 and 2 piping welds, with the alternative approved by the NRC in a Relief Request for the second interval of Unit 1. Following Code Case N-578 and EPRI methodology in TR-112657 revision B-A, these welds are classified as Category R-A, Item No. R1.16, with IGSCC identified as the degradation mechanism. Using the EPRI document, the degradation mechanism is from the inside diameter (ID) of the pipe/weld and only a volumetric examination is required. Thus, a surface examination is not performed.

NRC Question 6:

Please provide the inspection history (inspection dates, methods used, and Non Destructive Examination results) of the subject welds in RRs B-10 and 11.

Luminant Power's Response to Question 6:

RR B-10 for TBX-1-4201-9 and TBX-1-4201-10 Pipe welds were examined in 1RF13 (Fall 2008). These welds were selected for RI-ISI for the second interval of Unit 1. There were no recordable indications identified. Presevice Inspections PSI) of the subject welds occurred during 1984, with ultrasonic testing, penetrant testing, and visual examinations performed. There were no limitations and no recordable indications identified.

RR B-11 for TBX-1-4300-13 Reactor vessel safe-end to pipe weld was examined in IRF14 (Spring 2010) and 1RF07.

Attachment i to TXX-11071 Page 3 of 3 NRC Question 7:

For RRs B-10 and B-11, please discuss whether new Ultrasonic Testing (UT) technology (e.g., phased-array UT) has been considered which may provide higher percentage of examination coverage than the existing UT technology. If yes, please discuss whether the new UT technology will be used in the next in-service inspection. If no, please discuss why new UT technology was not explored.

Luminant Power's Response to Question 7:

Phased array UT was not considered. The limitation caused by the obstruction is such that no coverage could be obtained in this area with any other ultrasonic technique, from any other direction.

NRC Question 8:

For RR B-11, please provide illustrations of the weld configuration that identifies the examined weld area/volume and the weld area/volume that was not examined. Specifically describe how the configuration or obstruction restricts full examination of the weld. The configuration should include the reactor vessel nozzle, safe end, weld, pipe, and counter-bore.

Luminant Power's Response to Question 8:

A sketch depicting the required weld area/volume to be examined and the data sheets are included as to this response. There is no readily available sketch annotating the weld are/volume that was not examined for UT. As stated in RR B-11, this limitation of 88.99% was caused by the ID configuration of the counter-bore and root configuration, where the sled with the transducers attached was not in the required contact surface with the weld. Thus, volumetric coverage in this area could not be credited. The combined coverage of UT and Eddy Current Testing (ET) did yield 100% coverage.

NRC Question 9:

RR B-11 proposed a supplemental examination using eddy current techniques on the inside surface of the pipe/weld. Please discuss why this supplemental eddy current examination is not proposed for the welds in RR B-10.

Luminant Power's Response to Question 9:

As stated previously in the answer to question 5 and in RR B-10, welds TBX-1-4201-9 and TBX-1-4201-10 are RI-ISI welds; Category R-A, Item No. 1.16. Since the degradation mechanism occurs from the ID, only a volumetric examination is required per the EPRI methodology and Code Case N-578. The manual UT examination of these welds occurred from the OD and examined the lower 1/3 volume of the weld base metal.

DETECTION SLED SCANS CD0 cu INCREMENT DISTANCE = 0,25' (1.04*) f or AXIAL SCANS 3I A ~ 1 f

= 0.08' f or CIRC SCANS mg E; T2 C.

U L

n. L L x x I DISTANCE FROM __

VESSEL QL SIZING SLED SCANS INCREMENT DISTANCE = 0.125' (0,52") f or AXIAL SCANS

= 0,08' for CIRC SCANS DM WELDS ELBOW WELDS NOZZLE COMANCHE PEAK 1-TBX TBX-1-4400-14 TBX-1-4300-14 TBX-1-4400-13 TBX-1-4300-13

@ 67"

@ 113" WesDyne Internationca TBX-1-4200-14 TBX-1-4200-13 @ 247*

TBX-1-4100-14 TBX-1-4100-13 2 293* sMut INLET SAFE END EXAMS 2010 EXAMINATION PROGRAM PLAN ALL DMENSIONSIN UNLESS NOTED OTHERWISE INC JSHEET 6 OF 6

Attachment 2 to TXX-1 1071 Page 2 of 9 WesDyne International Reactor Vessel Weld Results Summary COMANCHE PEAK UNIT 1 WELD NO. DESCRIPTION COVERAGE TBX-1-4300-14 Inlet Nozzle to Safe-End @ 1130 100%

TBX-1-4300-13 Inlet Safe-End to Elbow @ 1130 *88.99%

LIMITATIONS NO LII YESW1X

  • flD Configuration of Safe-End to Elbow Weld UT RESULTS NO. OF UT INDICATIONS 0 STATUS N/A ET RESULTS El NO. OF ET INDICATIONS 0 STATUS N/A EXAM DOCUMENTATION INDICATION DOCUMENTATION

[-] ANALYSIS LOG D ASSESSMENT SHEET

  • j ACQUISITION LOG D-PARAGON HARD COPY F] SCAN PRINTOUT D--OTHER (specify)

[X COVERAGE BREAKDOWN WESDYNE ANALYST I-- e maWpsyml ->

Page 1 of 1 ANALYSIS LOG # SE-1 13-1 I Disk No: I Utility: ILUMINANT Plant: C OMANCHE PEAK U It 1 Outage: I IRF14 0 Procedure No: PDI-ISI-254-SE-NB Procedure Rev. No.: 1 Weld No: TBX-1-4300-13, 14 Weld Type: DM/SE/PIPE Exam. Surface: ID Applicable Sensitivity Calibration Data Sheet No: PDI-SE-AX-DET-01 Acquisition Log No: SE- PARAGON Anal. Release: 6.3.5 PDI-SE-CIRC-DET-01 I113-1 UT Examiner Signature: Level: II Date: 4-17-2010 Data File Name UT Beam Angle I NI RI RI Examiner IDI Channel Beam Resolution I Comments I Limitations Date No. Direction [pIor out, CW or C W]

TBX-113-PRP-IN 1 70 IN X JDF /4-17-10 TBX-113-PRP-IN 2 70 OUT X JDF /4-17-10 TBX-113-PRP-IN 5 70 IN X JDF / 4-17-10 TBX-1 13-PRP-IN 6 70 OUT X JDF/4-17-10 TBX-113-PAR-IN 1 70 CCW X JDF/4-17-10 TBX-113-PAR-IN 2 70 CW X JDF / 4-17-10 TBX-113-PAR-IN 3 70 CCW X JDF / 4-17-10 TBX-1 13-PAR-IN 4 70 CW X JDF / 4-17-10 TBX-1 13-PAR-IN 5 70 CCW X JDF / 4-17-10 TBX-113-PAR-IN 6 70 CW X JDF/ 4-17-10 TBX-113-PAR-IN 7 70 CCW X JDF / 4-17-10 TBX-113-PAR-IN 8 70 CW X Form 12.5 PDI-ISI-254-SE-NB, Rev. 1

-0 >

CD 02 ID.

ET Analysis Log: SE-113-1

-4

.Utility: LUMINANT Plant: COMANCHE PEAK Unit: I Outage: 1R14 Procedure No: WDI-STD-146 Procedure Rev. No.: 9 Weld No. TBX-1-4300-13,14 Weld Type: DMISE/PIPE Applicable Sensitivity Callbra Data S No: ET-1 Acquisition Log No: SE-113-1 ET Examiner Signature: Level: II Date: 4-17-2010 Data ET ET Probe Scan NI RI RI Examiner ID I Date File Name Probe Direction Resolution I Comments I Limitations No. (Avial/Ci]

TBX-113-PRP-IN I AXIAL X JDF /4-17-10 TBX-113-PRP-IN 2 AXIAL X JDF 14-17-10 TBX-113-PRP-IN 3 AXIAL X JDF 14-17-10 TBX-113-PRP-IN 4 AXIAL X JDF 14-17-10 TBX-113-PAR-IN I CIRC X JDF 14-17-10 TBX-113-PAR-IN 2 CIRC X JDF 14-17-10 TBX-113-PAR-IN 3 CIRC X JDF 14-17-10 TBX-113-PAR-IN 4 CIRC X JDF 14-17-10 Form 12-5

malwqspyfl DATA ACQUISITION LOG # SE-113-1 Utility: I LUMINANT Plant: I Comanche Peak Unit: 1 Outage: I1RF14 0

Procedure No: I PDI-ISI-254-SE-NB Procedure Rev. No.: I I Applicable Sensitivity Calibration Data Sheet No: PDI-SE-AX-DET-01, PDI-SE-CIRC-DET-01 UT Examiner Signature: -, j t Level: 11 Date: 4/17/2010 Data File Name Weld No. Index Scan Total # 'AVE' Gain _. Date Time Comments Start Start of Signal Adj.

Sweeps Amplitude (dB)

  • m (d .CO (mmfddlyy) o--

TBX-113-PRP-IN 1 TBX-1-4300-13,14 -2.0' 120.72" 178 11 0 KB 4/17/10 0344 TBX-113-PRP-IN 1 TBX-1-4300-13,14 -2.0' 120.72" 178 11 0 KB 4/17/10 0344 TBX-113-PRP-IN 1 TBX-1-4300-13,14 -2.0' 120.72" 178 14 0 KB 4/17/10 0344 TBX-113-PRP-IN I TBX-i-4300-13,14 -2.0" 120.72" 178 9 0 KB 4/17/10 0344 TBX-113-PAR-IN 1 TBX-1-4300-13,14 128.14" -2.0. 62 14 0 KB 4/17/10 0410 TBX-113-PAR-IN 1 TBX-1-4300-13,14 128.14" -2.0' 62 9 0 KB 4/17/10 0410 TBX-113-PAR-IN 1 TBX-1-4300-13,14 128.14" -2.0" 62 9 0 KB 4/17/10 0410 TBX-113-PAR-IN 1 TBX-1-4300-13,14 128.14" -2.0° 62 13 0 KB 4/17/10 0410 TBX-113-PAR-IN 1 TBX-1-4300-13,14 128.14" -2.0° 62 12 0 KB 4/17/10 0410 TBX-113-PAR-IN 1 TBX-1-4300-13,14 128.14" -2.0° 62 11 0 KB 4/17/10 0410 TBX-113-PAR-IN 1 TBX-1-4300-13,14 128.14" -2.0" 62 12 0 KB 4/17/10 0410 TBX-113-PAR-IN 1 TBX-1-4300-13,14 128.14" -2.0° 62 13 0 KB 4117/10 0410 Form 12.4 PDI-ISI-254-SE-NB, Rev. 1 to TXX-1 1071 Page 6 of 9 TBX-113-PRP-INScanSummary4-17-2010_3-44-58.log WesDyne International Reactor Vessel Inservice Examination Scan Parameter Execution SITE ........................ Comanche Peak #1 CONTROL SYSTEM .............. SQUID Site Weld ID = Inlet SE Weld and Scan Type = inlet SE PERPENDICULAR SCAN Scan Data File Name = TBX-113-PRP-IN SCAN AREA DEFINITIONS SCAN INDEX (inch) (degree)

START CW 120.720 -2.000 END CW . 135.390 182.080 START CCW  : 135.390 182.080 END CCW . 120.720 -2.000 SCAN AREA COVERED SCAN INDEX (inch) (degree)

TOP LEFT . 120.720 -2.000 TOP RIGHT  : 135.390 -2.000 BOTTOM LEFT  : 120.720 182.080 BOTTOM RIGHT  : 135.390 182.080 Increment Size (deg) = 1.040 Number of indexes specified = 178 Number of Indexes Completed = 178 Ti me Date Scan Started 03:24:49 04/17/2010 Scan Completed 03:44:58 04/17/2010 OPERATOR DATE 04/17/2010 03:44:58 OPERATOR Al /A4 DATE 04/17/2010 03:44:58 COMMENTS Page 1 to TXX-1 1071 Page 7 of 9 TBX-113-PAR-INScanSummary4-17-2010_4-10-15.log WesDyne International Reactor vessel Inservice Examination scan Parameter Execution SITE ........................ Comanche Peak #1 CONTROL SYSTEM .............. SQUID Site Weld ID = Inlet SE weld and Scan Type = Inlet SE PARALLEL SCAN Scan Data File Name = TBX-113-PAR-IN SCAN AREA DEFINITIONS SCAN INDEX (degree) (inch)

START CW  : -2.000 128.140 END CW . 182.000 133.020 START CCW 182.000 133.020 END CCW . -2.000 128.140 SCAN AREA COVERED SCAN INDEX (degree) (inch)

TOP LEFT  : -2.000 128.140 TOP RIGHT 182.000 128.140 BOTTOM LEFT -2.000 133.020 BOTTOM RIGHT  : 182.000 133.020 Increment size (in) = 0.080 Number of Indexes Specified = 62 Number of Indexes Completed = 62 Ti me Date scan started 03:53:25 04/17/2010 Scan Completed 04:10:15 04/17/2010 OPERATOR ' DATE 04/17/2010 04:10:15 OPERATOR __ _ _ _ _ _ _ _ DATE 04/17/2010 04:10:15 COMMENTS Page 1

COMANCHE PEAK UNIT 1 DIRECTION / ORIENTATION C(0~

RPV COVERAGE ESTIMATE BREAKDOWNS PARALLEL SCANS CCW / CW PERP. SCANS IN / OUT 00=

WELD WELD NO. TBX-1-4300-13 DESCRIPTION Inlet Nozzle Safe-End to Elbow @ 1130 BEAM ANGLES BEAM 700 L Dual *ET DIRECTION EXAM VOLUME EXAM SURFACE CCW 77.97* 100 cw 77.97* 100 IN 100 N/A OUT 100 N/A UT COVERAGE = 88.99% Procedure limited in the detection of axial flaws per the PDQS document.

Combined Coverage (UT & ET) = 100o of limitation Areas *1D inspected Configuration by Eddy Current technique.

of Safe-End to Elbow weld ANALYST ~2c~

a, COMANCHE PEAK UNIT 1 DIRECTION I ORIENTATION CDO RPV COVERAGE ESTIMATE BREAKDOWNS PARALLEL SCANS CCW / CW Co -

PERP. SCANS IN / OUT

-4 WELD WELD NO. TBX-1-4300-14 0

-.4 DESCRIPTION Inlet Nozzle to Safe-End @ 1130 BEAM ANGLES BEAM 700 L Dual *ET DIRECTION EXAM VOLUME EXAM SURFACE Ccw 100 100 Cw 100 100 IN 100 N/A OUT 100 N/A UT COVERAGE = 100%

Combined Coverage (UT & ET) 100%

ANALYST__________

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