ML20207B952
| ML20207B952 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/26/1999 |
| From: | Nolan M NRC (Affiliation Not Assigned) |
| To: | Hutchinson C ENTERGY OPERATIONS, INC. |
| References | |
| GL-98-04, GL-98-4, NUDOCS 9906020160 | |
| Download: ML20207B952 (5) | |
Text
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UNITED STATES l
J[p NUCLEAR REGULATORY COMMISSION WAsMildBToN, D.C. 30005 4001 May 26,'1999 i
l-Mr. C. Randy Hutchinson Vice President, Operations ANO Entergy Operations,Inc.
1448 S. R. 333 Russellville, AR 72801 l'
SUBJECT:
CONTAINMENT PROTECTIVE COATING SYSTEM SURVEY TO SUPPORT TEST PROGRAM DEMONSTRATING COATING PERFORMANCE DURING ACCIDENT CONDITIONS l
Dear Mr. Hutchinson:
l Generic Letter (GL) 98-04, " Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment," discussed, in part, i
the degradation of emergency core cooling systems after a loss-of-coolant accident (LOCA) l due to the failure of containment protective coating systems and subsequent blockage of J
containment sump screens. Licensee responses to GL 98-04 are currently under review by the NRC staff. In conjunction with this review, the NRC's Office of Nuclear Regulatory Research has been asked to conduct a study of the performance of coating systems when exposed to a I
post-LOCA environment. This study will attempt to characterize coating degradation and transport mechanisms in order to better assess the potential impact to emergency core cooling I
system and containment spray system operations following a LOCA.
The staff has decided to conduct a limited survey in order to identify a sampling of protective l
coating systems in use throughout the industry. A better understanding of the coating systems in use, along with the range of environmental conditions under which these coatings could be i
exposed, will allow the staff to design a test program that is more representative of industry 1
conditions. The enclosed table provides a list of input parameters that the staff will use in finalizing the test plan. An example has been provided to demonstrate the level of detail L
desired in your response. Please provide the information requested in the enclosed table for those coating systems applied during original construction as well as those currently in use to support maintenance and modification activities, it has been determined that the performance of any coating system is highly dependent upon the method of application. The staff would be interested in any supporting information on application methods for coatings that were applied to manufacturer or site-specific practices that differ from industry standards. In addition, any supporting vendor literature regarding the chemical and physical properties of coating systems in use would be welcome.
The staff is extending rari invitation to licensees to provide samples of original containment coatings for inclusion into the testing program. The staff would subject these coatings to a post-LOCA environment and evaluate their susceptibility to degradation. The results of these tests would be published in a report documenting the overall testing program. The contents I
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C. R. Hutchinson May 26, 1999 The contents of this survey were discussed with Mr. Steve Bennett and others of your staff on May 6,1999. We agreed that your response would be provided by July 9,1999. If you decide to participate in providing actual coating samples to be included in the testing program, please contact Mr. Aleck Gerkiz at (301) 415-6563 to discuss sample requirements and shipping logistics. Samples will be accepted through December 31,1999.
If you have any questions regarding this matter, please contact me at (301) 415-1320.
Sincerely, ORIGINAL SIGNED BY M. Christopher Nolan, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-313 and 50-368
Enclosure:
As stated cc w/ encl: See next page plSTRIBUTION:
Docket File PUBLIC PD4-1 r/f OGC ACRS K.Brockman, RIV S. Richards N.Hilton J. Boardman J. Davis Document Name: G:\\PDIV-1\\ANO1-2\\LTR4016.WPD
- See Previous Concurrence Ta receive a copy of this document, Indicate in the box: "C" = Copy without enclosures *E" = Copy with enclosures "N"
= No copy OFFICE PM:PDIV-1 E
LA:PDIV-1 b n @, SC: EMCB*
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6 NAME CNolan #
LBerry
\\ (D ~ ESullivan A.Serkiz RGramm (Lls DATE 05/tf /99 05/ fab /99' 05/18/99 05/24/99 05/lle /99 OFFICIAL RECORD COPY
4 Arkansas Nucisar One cc:
Executive Vice President Vice President, Operations Suppod
& 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, Division 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 Lenior Resident inspector U.S. Nuclear Regulatory Commission P. O. Box 310
[
London, AR 72847 Regional Administrator, Region IV 611 Ryan Plaza Drivegry Commission U.S. Nuclear Regulat
, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 i
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