ML20237B463
| ML20237B463 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/13/1998 |
| From: | William Reckley NRC (Affiliation Not Assigned) |
| To: | Hutchinson C ENTERGY OPERATIONS, INC. |
| References | |
| GL-92-01, GL-92-1, TAC-MA0524, TAC-MA524, NUDOCS 9808180298 | |
| Download: ML20237B463 (4) | |
Text
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Mr. C. Randy Hutchinson August 13, 1998 Vice President Operations ANO Entergy Operations, Inc.
'1448 S. R. 333 Russellville,' AR 72801
SUBJECT:
- REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR
. PRESSURE INTEGRITY AT ARKANSAS NUCLEAR ONE, UNIT 2 (ANO-2)
Dehr Mr. Hutchinson:
Generic Letter (GL) 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp. 1), " Reactor Vessel Structural integrity," was issued in May 1995. This GL requested licensees to perform a -
review of their reactor pressure vessel (RPV) structural integrity assessments in order to identify, collect, and report any new data pertinent to the analysis of the structural integrity of their RPVs and to assess the impact of those data on their RPV integrity analyses relative to applicable requirements.
- By letter dated June 18,1997, Entergy Operations, Inc., submitted information that included the compilation of data for reactor vessel materials by the Combustion Engineering Owners Group and fluence evaluations for ANO-2.' The staff requires further information to complete its assessment of the information submitted for ANO-2 and requests that you provide a response to the enclosed request for additional Information within 75 days of receipt of this letter.
Please contact me if you have any questions regarding this request for information.
Sincerely, ORIGINAL SIGNED BY:
William Reckley, Project Ma'1ager Project Directorate IV-1 Division of Reactor Projects ll!/IV Office of Nuclear Reactor Regulation Docket No. 50-368
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Enclosure:
Request for Additional Information cc w/ encl: See next page
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'+,*****,o August 13, 1998 Mr. C. Randy Hutchinson Vice President, Operations ANO Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72801
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE INTEGRITY AT ARKANSAS NUCLEAR ONE, UNIT 2 (ANO-2)
Dear Mr. Hutchinson:
Generic Letter (GL) 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp. 1), " Reactor Vessel Structural Integrity," was issued in May 1995. This GL requested licensees to perform a review of their reactor pressure vessel (RPV) structural Integrity assessments in order to identify, collect, and report any new data pertinent to the analysis of the structural integrity of their RPVs and to assess the impact of those data on their RPV integrity analyses relative to applicable requirements.
By letter dated June 18,1997, Entergy Operations, Inc., submitted information that included the compilation of data for reactor vessel materials by the Combustion Engineering Owners Group and fluence evaluations for ANO-2. The staff requires further information to complete its assessment of the information submitted for ANO-2 and requests that you provide a response to the enclosed request for additional information within 75 days of receipt of this letter.
Please contact me if you have any questions regarding this request for information.
Sincerely, William Reckley, Project Ma ger Project Directorate IV-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket No. 50-368
Enclosure:
Request for AdditionalInformation cc w/enci: See next page l
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Mr. C. Randy Hutchinson Entergy Operations, Inc.
Arkansas Nuclear One, Unit 2 cc:
Executive Vice President Vice President, Operations Support
& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc.
P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-199 Wise, Carter, Child & Caraway Director, D! vision of Radiation P. O. Box 651 Control and Emergency Management Jackson, MS 39205 Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Manager, Rockville Nuclear Licensing Framatone Technologies 1700 Rockville Pike, Suite 525 Rockville, MD 20852 Senior Resident inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 I
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Request for Additionalinformation l
(ANO-2 Reactor Pressure Vessel)
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(1)
With ragard to upper / intermediate shell circumferential weld 8-203, weid wire heat number 1013it the revised chemistries from the Combustion Engineering Owners Group (CEOG) reportfated July 1997, were provided. However, the submittal stated that this weld was not incTuded in the evaluation because its fluence is lower than any of the other components. In order to obtain the correct docketed values for weld 8-203, please l
provide (a) fluence at the expiration of license (EOL), (b) ART, at EOL, (c) margin term, and (d) RT, at EOL.
n (2)
The submittal states that Reference 18 (Report 96-R-2030-02, Revision 0, " Revised Reactor Vessel Fluence Determination") provides the details of the fluence evaluation described on pages 15 and 16. Please provide this reference or your most recent fluence 4
determination if this repc rt has been superseded.
(3)
Excore ratios were use6.9 the evaluation of the fluence. These ratios are meant to evaluate the amount of letkage from the core from cycle to cycle. The staff is not aware of the use of excore ratios n, rpWs vessel fluence calculations by other licensees. If not included in the response to question 2, please provide references for this methodology and a more detailed explanation of how the excore readings were used.
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(4)
The submittal references the following statement from a safety evaluation for Calvert Cliffs dated January 2,1996:
The methodology employed the CASK cross section set. CASK is based in an early ENDF/B version which is known to have an iron scattering cross section error, which is corrected in ENDF/B-VI. However, we know from experience that this error appears only during neutron transmission through significant amounts of iron, as for example the thermal shield or the vessel. Neither of the Calvert Cliffs units is equipped with a thermal shield; thus, the staff does not expect the results to have been affected by the use of the CASK cross section.
The ANO-2 vessel does not have a thermal shield, but the licensee did not use CASK for the fluence evaluation. CASK uses ENDF/B-ll or ENDF/B-Ill and the ANO-2 evaluation uses the ENDF/B-IV library. The submittal states that, based on the reference, the surface fluence would not change if the fluence analysis were performed using the ENDF/B-VI library. Since the ENDF/B-ll, ENDF/B-lil, ENDF/B-IV, and ENDF/B-VI cross sections are not the same and may not change in a progressive manner, explain the relevance of the Calvert Cliffs safety evaluation citation to ANO-2.
(5)
Adjustments were made to the calculated fluence to account for issues such as differences in cross sectional libraries (ENDF/B-IV vs. ENDF/B-VI) and power shift.
Provide additional justification for the adjustment of 10% to the 1.69 EFPY calculated fluence for the extrapolation to 21 EFPY (i.e., explain why 10% is sufficient to address all the stated issues).
ENCLOSURE
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