CP-201000889, Relief Request No. C-6 for 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)
| ML103560593 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/15/2010 |
| From: | Madden F Luminant Power, Luminant Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CP-201000889, TXX-10091 | |
| Download: ML103560593 (10) | |
Text
Rafael Flores Luminant Power Senior Vice President P 0 Box 1002 011
& Chief Nuclear Officer 6322 North FM 56 rafael.flores@Luminant.com Glen Rose, TX 76043 Luminant 2548975550 C 817 559 0403 F 254 897 6652 CP-201000889 Ref. # 10 CFR'50.55a(g)(5)(iii)
Log # TXX-10091 December 15, 2010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NO. 50-445 RELIEF REQUEST NO. C-6 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)
Dear Sir or Madam:
Pursuant to 10 CFR 50.55a(g)(5)(iii), Luminant Generation Company, LLC (Luminant Power) is submitting Relief Request C-6 (see attachment) for Comanche Peak Unit 1 for the second ten year inservice inspection interval. Luminant Power has determined that certain inspection requirements of ASME Section XI are impractical due to physical interferences.
The geometry of the excess letdown heat exchanger makes the Code required examination coverage requirements impractical. Ultrasonic Testing (UT) of the subject weld was performed during the second interval to the maximum extent practical based on design configuration restrictions. Pressure test VT-2 visual examinations were also performed with no evidence of leakage identified for the subject component. No undue risk to the public health and safety is presented by this request.
This communication contains no new licensing basis commitments regarding Comanche Peak Unit 1.
Should you have any questions, please contact Mr. Jack Hicks at (254)897-6725.
Sincerely, Luminant Generation Company LLC Rafael Flores By:
B Fred W. Madden Director, Oversight & Regulatory Affairs A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway Comanche Peak
- Diablo Canyon-PaloVerde.
San Onofre. South Texas Project Wolf Creek
U. S. Nuclear Regulatory Commission TXX-10091 Page 2 12/15/2010 Attachments -
- 1. Relief Request C-6 for Unit 1 Relief Request for Weld Examination Coverage for the Excess Letdown Heat Exchanger
- 2. Drawing and Inspection Sheets for Excess Letdown Heat Exchanger c -
E. E. Collins, Region IV B. K. Singal, NRR Resident Inspectors, Comanche Peak Brian Welch, ANII, Comanche Peak Anthony Jones, TDLR to TXX-10091 Page 1 of 3 10CFR 50.55a Request Number C-6 Relief Requested In Accordance with 10CFR50.55a(g)(5)(iii)
- Inservice Inspection Impracticality -
- 1. ASME Code Component Affected:
Class 2 Excess Letdown Heat Exchanger (TBX-CSAHEL-01) Head Circumferential Weld Code Cat / Item No.
Description Weld No.
C-A / C1.20 Excess Letdown HX Head to Flange Weld TBX-2-1 110-1
2. Applicable Code Edition and Addenda
The applicable ASME Boiler and Pressure Vessel Code (hereafter referred to as the "Code") edition and addenda is ASME Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1998 Edition through 2000 Addenda.
3. Applicable Code Requirement
ASME Section XI, Figure IWC-2500-1 (a) 1998 Edition through 2000 Addenda, requires a minimum volumetric examination of the weld volume extending 1/2" into the base metal on the vessel and flange sides for the head circumferential weld (Code Item C1.20).
Comanche Peak Nuclear Power Plant (CPNPP) second ten-year interval Inservice Inspection Program Plan also implements Code Case N-460, which is endorsed by the NRC in revision 15 of Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability ASME Section XI, Division 1." Code Case N-460 states, in part, whe'n the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted, provided the reduction coverage for that weld is less than 10 percent.
NRC Information Notice (IN) 98-42, "Implementation of 10CFR50.55a(g) Inservice Inspection Requirements," termed a reduction in coverage of less than 10 percent to be "essentiallyýi 00 percent." IN 98-42 states, in part, "The NRC has adopted and further refined the definition of "essentially 100 percent" to mean "greater than 90 percent"... has been applied to all examinations of welds or other areas required by ASME Section XI."
to TXX-10091 Page 2 of 3 10CFR50.55a Request Number C-6
4. Impracticality of Compliance
The examination of the subject component weld is limited by the configuration of the flange design and the location of two-four inch and two-three inch nozzles on the tube side of the heat exchanger. As shown on the Attachment 2, the proximity of the nozzles limits the perpendicular scans on the tube side. Parallel scans were limited on the flange side of the weld. This yields a composite coverage of 50% of the required examination volume.
The examinations were conducted in accordance with procedure TX-ISI-214,"Ultrasonic Examination Procedure for Welds in Piping Systems and Vessels." Straight beam (00) and angle beams (450 shear and 600 longitudinal) scans were used to achieve the weld volume obtained.
- 5. Burden caused by Compliance:
The design configuration restrictions of the of the subject component makes the Code required examination coverage requirements for the weld volume impractical. Plant modifications or replacements of components designed to allow for complete would be needed to meet the Code requirements. This would cause considerable burden to CPNPP.
6. Proposed Alternative and Basis for Use
Proposed Alternative:
The following alternatives are proposed in lieu of the required examination coverage of essentially 100 percent:
- 1. Ultrasonic testing (UT) of the subject component weld was performed to the maximum extent practical during the second ten-year interval.
- 2. Pressure test VT-2 visual examinations were performed, as required by Code Category C-H, during the second ten-year interval. No evidence of leakage was identified for this component.
Basis for use:.
The basis for use of this alternative is that it provides the best examination coverage practical within the limitations of the current configuration. Based on the percentage of the examination volume completed and the lack of any indications identified, there is a high level of confidence in the continued structural integrity of the weld. CPNPP believes that there is no undue risk to the public health and safety presented by this request.
to TXX-10091 Page 3 of 3 10CFR50.55a Request Number C-6
7. Duration of Proposed Alternative
The second ten-year ISI interval for Unit 1 began on August 13, 2000 and ended on August 12, 2010.
8. Precedents
Relief Request C-9 was submitted in letter TXX-98170 from CPNPP to USNRC in July 22, 1998 for the first ten-year interval for Unit 1.
PDI Calibration Data Sheet Plant / Unit COMANCHE PEAK UNIT I Company WESDYNE Comp / System CHEM. & VOL. CONTROL Procedure No.
TX-ISI-214 Rev / Chng. No.
4/NA Cal. Block No.
TBX-8 Cal. Block Temp 880 Comp. Temp 770 Therm S/N:
TU-2367 Size 8"
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13 UT-23 Page I
of Cal. Checks Time Initial Calib.
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KBA Serial No.:
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PDI Calibration Data Sheet Plant / Unit COMANCHE PEAK UNIT 1 Company WESDYNE Comp / System CHEM. & VOL. CONTROL Procedure No.
TX-ISI-214 Rev/ Chng. No.
4/NA Cal. Block No.
TBX-8 Cal. Block Temp 85' Comp. Temp 770 Therm S/N:
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to TXX-10091 Page 4 of 5 PLANT SYST/COMP EXAMINER EXAMINER i
WESTINGHOUSE NUCLEAR SERVICES DIVISION REPORT NO.
UT-98-129 INSPECTION SERVICES PAGE OF 3
PROFILE OF THE EMAMINATION V Eý,ý y
5-Comanche Peak UNIT I
SKETCH TBX-2-1110 Rev, 1 CHEMICAL & VOLUME CONTROL PROCEDURE TX4SI-214 Rev. 2 FC N/A Morini, George LEVEL II DATE 4110198 NIA LEVEL NIA DATE COMPONENT ID TBX-2-1110-1 COMMENTSISKETCH/DETAILS
(,6'LI S-TDE S F) A j
C, D: C)9P Iroj
.. 0 0 TU ELECTRIC REVIEW I DATE DeBonis, John I.
to TXX-10091 Page 5 of 5 m.m PLANT Cona SYST/COMP CHE*
EXAMINER Mort EXAMINER
- N/A anche Peak REPORT NO.
'UT-98-129 WESTINGHOUSE NUCLEAR SERVICES DIVISION
- PAGE OF LIMITATION TO EXAMINATION
~
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UNIT 1
SKETCH TBX-2-111O Rev. 1 ME CONTROL PROCEDURE TX-tSI-214 Rev. 2 FC NfA LEVEL I1 DATE 4t198 LEVEL NIA DATE AICAL & VOLU ni, George,
COMPONENT ID TBX-2-1110.1 RELATED TO Q MT Q PT UT 0
VT PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE, LOCATION AND TYPE OF LIMITATION.
COMMENTS/SKETCHIDETAILS Four nozzles located as shown below. Two 3-nozzles and two 4' nozzles on side 2. 50% not examined.
4
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T S%' 0.15 TU ELECTRIC REVIEW I DATE TU ELECTRIC LEVEL III REVEW / DATE ANII REVIEW I DATE DeBonis, John R
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