ML20206F061
| ML20206F061 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/29/1999 |
| From: | Gramm R NRC (Affiliation Not Assigned) |
| To: | Hutchinson C ENTERGY OPERATIONS, INC. |
| Shared Package | |
| ML20206F067 | List: |
| References | |
| RTR-REGGD-01.147, RTR-REGGD-1.147 TAC-M99243, NUDOCS 9905050324 | |
| Download: ML20206F061 (4) | |
Text
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UNITED STATES l
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30006 0001 April 29, 1999 Mr. C. Randy Hutchinson Vice President, Operations ANO Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72801 l
SUBJECT:
THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN AND ASSOCIATED REQUESTS FOR RELIEF, ARKANSAS NUCLEAR ONE, UNIT 1 (TAC NO. M99243)
Dear Mr. Hutchinson:
i By letter dated June 25,1997, Entergy Operations, Inc. submitted the Inservice inspection (ISI)
Plan for the third 10-year interval and associated requests for alternatives for Arkansas Nuclear One, Unit 1 (ANO-1). Additionally, in response to a request for additional information (RAl), a letter dated April 28,1998, documented that drawings were forwarded to the staff and the remaining portions of the response were submitted by [[letter::1CAN129801, Forwards Response to NRC 971202 RAI Re ANO-1 Third 10-yr ISI Program.Rev 1 to Third 10-Yr Interval ISI Program for ANO-1, Encl|letter dated December 9,1998]].
1 The staff, with technical assistance from its contractor, the Idaho National Engineering and j
Environmental Laboratory, has reviewed and evaluated the information in your request. In your ISI Program, the staff determined that there were eight apparent discrepancies in the third 10-year ISI program plan. However, it should be noted that you may have additional information available to document the acceptability of each condition. If you can adequately document the acceptability of each condition, no further information is required by the staff.
The staff found that two out of three requests for attematives to the American Society of Mechanical Engineers (ASME) Code,Section XI, were acceptable. Code Case N-521 states that the examination of reat. tor pressure vessel nozzles, inside radius sections, and nozzle-to-l safe end welds may be dsferred provided (a) no inservice repairs or replacements by welding l
have ever been performed on any of the subject areas, (b) none of the subject areas contains identified flaws or relevant conditions that currently require successive inspections in accordance with IWB-2420(b), and (c) the unit is not in the first interval. You confirmed that these conditions have been met. Additionally, all subject areas are to be scheduled for examination such that the new sequence of examinations will not exceed 10 years between examinations. You examined all the subject areas during the third period of the second 10-year interval. Therefore, the staff concluded that your proposed alternative contained in Request for Relief No.97-004 provides an acceptable level of quality and safety and therefore is authorized
,j pursuant to 10 CFR 50.55a(a)(3)(i). The use of Code Case N-521 is authorized for the third 10-I year interval at ANO-1, or until the Code Case is approved for general use by reference in Regulatory Guide 1.147. After that time, you may continue to use Code Case N-521 with the limitations, if any, listed in Regulatory Guide 1.147.
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You requested that Request for Relief No.97-005 be reviewed separately from the third 10-year interval program to gain the benefits during a past refueling outage. The staff reviewed and granted the relief request, for Code Class 1 piping only, in a letter, with enclosed safety 9905050324 990429 PDR ADOCK 05000313 i
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-April 29, 1999 C. R. Hutchinson,
evaluation, dated April 17,1998. The staff completed the review for both Class 1 and 2 piping and conc!vded that the 4-hour hold time should allow potential leakage to penetrate the insulation, thus providing a means of detecting significant leakage with the insulation in place.
l Further, by subsequently removing the insulation each refueling outage for Class 1 bolted connections, and each period (not exceeding 40 months) for Class 2 bolted connections, you will be able to detect minor leakage indicated by the presence of boric acid residue. Therefore, the staff concluded that your proposed alternative contained in Request for Relief No.97-005
- provides an acceptable level of quality and safety and therefore is authorized pursuant to 10 CFR 50.55a(a)(3)(i). The use of Code Case N-533 is authorized for the third 10-year l
l interval at ANO-1, or until the Code Case is approved for general use by reference in l
Regulatory Guide 1.147. After that time, you may continue to use Code Case N-533 with the l
limitations, if any, listed in Regulatory Guide 1.147.-
In a telephone conference call on March 24,1999, regarding Relief Request 97-003, your staff clarified that it was asking to eliminate the ultrasonic exam for piping with wall thickness less than 3/8-inch, which is not subject to inspection and Enforcement (IE)Bulletin 79-17, and perform only a surface examination. In Relief Request 97-003, technical justification was not provided as to why eliminating the volumetric exams for piping less than 3/8-inch nominal wall thickness which is not subject to IE Bulletin 79-17, and its proposed alternative to perform a l
surface examination, provides equivalency or acceptable quality and safety. Therefore, your proposed alternative is denied.
l An RAI was required to complete this review. We issued the RAI on December 2,1997. A portion of the response was provided on April 28,1998; however, your response was not completed until December 9,1998. Although you indicated the delay was due to competing i
i resource oemands, and the delays were discussed with the ANO project manager, the staff may not support response intervals of this magnitude in the future, in order to improve our
. licensing review timeliness, we plan to deny those requests for which a licensee is unable to respond to RAls in a timely manner.
Sincerely, ORIG. SIGNED BY f'..
Robert A. Gramm, Chief, Section 1 p
roject Directorate IV & Decommissioning 4 '7 ivision of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313 Distribution:
Enclosure:
Safety Evaluation w/att. Restselfjef PUBLIC PDIV-1 r/f l
cc w/ encl: See next page J. Zwolinski/S. Black R. Gramm OGC T. McLellan D. Lange, EDO ACRS G. Hill (2)
K. Brockman, RIV S. Richards C. Norsworthy (RCN)
L. Berry N. Hilton DOCUMENT NAME: G:\\ANO1FINA\\REL99243.WPD To receive a copy of this document, indicate in the box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy OFFICE PDlV-1/P&l E
PDIV-1/14 E
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NAME NHilton 4 LBerry O/ hr GBagchi
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DATE h / @/99 ~
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- SE incorporated with no substantial changes OFFICIAL RECORD COPY l
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Q C. R. Hutchinson evaluation, dated April 17,1998. The staff completed the review for both Class 1 and 2 piping and concluded that the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> hold time should allow potentialleakage to penetrate the insulation, thus providing a means of detecting significant leakage with the insulation in place.
Further, by subsequently removing the insulation each refueling outage for Class 1 bolted I
connections, and each period (not exceeding 40 months) for Class 2 bolted connections, you
. will be able to detect minor leakage indicated by the presence of boric acid residue. Therefore, the staff concluded that your proposed alternative contained in Request for Relief No.97-005 provides an acceptable level of quality and safety and therefore is authorized pursuant to 10 CFR 50.55a(a)(3)(i). The use of Code Case N-533 is authorized for the third 10-year interval at ANO-1, or until the Code Case is approved for general use by reference in Regulatory Guide 1.147. After that time, you may continue to use Code Case N-533 with the limitations, if any, listed in Regulatory Guide 1.147.
In a telephone conference call on March 24,1999, regarding Relief Request 97-003, your staff clarified that it was asking to eliminate the ultrasonic exam for piping with wall thickness less than 3/8-inch, which is not subject to inspection and Enforcement (IE)Bulletin 79-17, and perform only a surface examination. In Relief Request 97-003, technicaljustification was not provided as to why eliminating the volumetric exams for piping less than 3/8 inch nominal wall thickness which is not subject to IE Bulletin 79-17, and its proposed alternative to perform a surface examination, provides equivalency or acceptable quality and safety. Therefore, your proposed altemative is denied.
An RAI was required to complete this review. We issued the RAI on December 2,1997. A portion of the response was provided on April 28,1998; however, your response was not completed until December 9,1998. Although you indicated the delay was due to competing resource demands, and the delays were discussed with the ANO project manager, the staff may not support response intervals of this magnitude in the future. In order to improve our licensing review timeliness, we plan to deny those requests for which a licensee is unable to respond to RAls in a timely manner.
Sincerely, k
h Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313 i
Enclosure:
Safety Evaluation w/att.
cc w/ encl: See next page i
Arkansas Nuclear One, Unit 1 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, DMolon of Radiation P. O. Box 651 Controland 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 1
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