2CAN041004, Response to Request for Additional Information on Request for Alternative ANO2-ISI-004
| ML101190462 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/29/2010 |
| From: | David Bice Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2CAN041004, ANO2-ISI-004 | |
| Download: ML101190462 (4) | |
Text
2CAN041004 April 29, 2010 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Request for Additional Information On Request for Alternative ANO2-ISI-004 Docket No. 50-368 License No. NPF-6
REFERENCE:
Entergy letter to the NRC, dated October 29, 2009, Request for Alternative ANO2-ISI-004 Proposed Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations (2CAN100902)
Dear Sir or Madam:
In the referenced submittal, Entergy Operations, Inc. (Entergy) requested approval for an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Code,Section XI, Paragraph IWB-2412 for Arkansas Nuclear One, Unit 2. In particular the requirement that volumetric examinations of essentially 100% of the reactor vessel pressure retaining Examination Category B-A and B-D welds be performed once each ten-year interval.
Subsequent to the referenced submittal, the NRC determined that additional information was required to complete their review and provided a Request for Additional Information (RAI) in an email dated April 13, 2010. The attachment to this letter contains the RAI and associated responses.
This letter contains no new commitments.
If you have any questions or require additional information, please contact me at 479-858-5338.
Sincerely, DBB/rwc
Attachment:
Request for Additional Information on Request for Alternative ANO2-ISI-004 Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-5338 David B. Bice Acting Manager, Licensing Arkansas Nuclear One
2CAN041004 Page 2 of 2 cc:
Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8 B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852
Attachment to 2CAN041004 REQUEST FOR ADDITIONAL INFORMATION ON REQUEST FOR ALTERNATIVE ANO2-ISI-004
Attachment to 2CAN041004 Page 1 of 1 REQUEST FOR ADDITIONAL INFORMATION ON REQUEST FOR ALTERNATIVE ANO2-ISI-004
- 1. In Table 3, Details of TWCF Calculation - ANO Unit 2 at 48 Effective Full Power Years (EFPY), input values are given for Cu, Ni, and fluence for each beltline material. These values are not all consistent with Nuclear Regulatory Commission (NRC) records. The Cu and Ni values are consistent with Arkansas Nuclear One, Unit 2 (ANO-2) License Renewal Application (LRA), Agencywide Documents Access and Management System, (ADAMS), Accession No. ML032890506, but were not consistent with Safety Analysis Report (SAR), Amendment No. 19. Fluence values are not consistent with the LRA or the SAR. Please identify a docketed and reviewed reference containing these values, or provide a technical basis for the change from previous values. If any input values are changed, please provide the appropriate revised calculations.
It should be noted that the copper (Cu) and nickel (Ni) content reported in the request for alternative for the beltline materials are consistent with those reported in Table 5.2-20a of Amendment No. 19 of the ANO-2 SAR.
The fluence values reported in the relief request and used in the calculation of TWCFs were obtained from Table 6-4 of the latest surveillance capsule report for ANO-2, BAW-2399, Revision 1, Analysis of Capsule W-104, Entergy Operations, Inc. Arkansas Nuclear One Unit 2 Power Plant. BAW-2399, Revision 0 was submitted to the NRC as Enclosure 2 to the ANO-2 Proposed Technical Specification Change Request Regarding Revised ANO-2 Pressure / Temperature and Low Temperature Overpressure Protection Limits for 32 Effective Full Power Years (2CAN100101), dated October 30, 2001. This submittal was made approximately the same time frame as the ANO-2 LRA. The proposed Technical Specification change was approved in letter dated April 15, 2002, Arkansas Nuclear One, Unit No. 2 -
Issuance of Amendment RE: Reactor Vessel Pressure-Temperature Limits and Exemption from the Requirements of 10 CFR Part 50, Section 50.60(a) (TAC NOS. MB3301 and MB3302).
Subsequent to the NRC approval, BAW-2399 was revised to correct weld wire heat identifications. This change did not impact the chemical composition of the beltline material nor the fluence value to that material.
- 2. Table 2, Additional Information Pertaining to Reactor Vessel Inspection - ANO-2, states that ANO-2 is bounded by 13 heatups/cooldowns per year. Please cite the plant design basis for heatup/cooldowns per year.
As stated in the Table 4.3-1, RCS Design Transients of the ANO-2 LRA, the number of RCS heat-up / cool-down design transient cycles for ANO-2 without the steam generators are 500 for a 40 year design life which equates to 12.5 transient cycles per year.