ML20129D581
| ML20129D581 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/25/1996 |
| From: | Alexion T NRC (Affiliation Not Assigned) |
| To: | Yelverton J ENTERGY OPERATIONS, INC. |
| References | |
| NUDOCS 9609300130 | |
| Download: ML20129D581 (4) | |
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September 25, 1996 Mr. Jerry W. Yelverton Vice President, Operations ANO Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72801
SUBJECT:
ED0Y CURRENT INDICATIONS IN COMBUSTION ENGINEERING DESIGNED WELDED STEAM GENERATOR TUBE SLEEVES
Dear Mr..Yelverton:
The NRC. staff has developed questions regarding the above subject and needs responses to determine Entergy Operations, Inc.'s (E01's) plans with respect to inspection and repair of these sleeved tubes at.the next outage.
The staff requests that E01 respond to the enclosed request for additional information within 60 days from the date of this letter.
l Sincerely, ORIGINAL SIGNED BY:
Thomas W. Alexion, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-368
Enclosure:
Request for Additional Information cc w/ encl:
See next page DISTRIBUTION:
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September 25, 1996 Mr. Jerry 'W. Yelverton Vice President, Operations AN0 Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72801
SUBJECT:
EDDY CURRENT INDICATIONS IN COMBUSTION ENGINEERING DESIGNED WELDED STEAM GENERATOR TUBE SLEEVES
Dear Mr. Yelverton:
The NRC staff has developed questions regarding the above subject and needs responses to determine Entergy Operations, Inc.'s (E01's) plans with respect to inspection and repair of these sleeved tubes at the next outage.
The staff requests that E01 respond to the enclosed request for additional information within 60 days from the date of this letter.
Sincerely, f
x Qh5 l'YU Thomas W. Alexion, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-368
Enclosure:
Request for Additional Information cc w/ encl: See next page 4**
Mr. Jerry W. Yelverton Entergy Operations, Inc.
Arkansas Nuclear One, Unit I 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, Division of Radiation P. O. Box 651 Control and Emergency Management Jackson, MS 3920S 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
REQUEST FOR ADDITIONAL INFORMATION ON ED0Y CURRENT INDICATIONS IN COMBUSTION ENGINEERING DESIGNED WELDED STEAM GENERATOR TUBE SLEEVES Backaround During the Prairie Island Unit 1 (PI-1) January 1996 steam generator (SG) tube inspection, 61 eddy current (EC) indications were found in the upper sleeve weld region of Combastion Engineering (CE) welded tubesheet sleeves. These indications were characterized as single or multiple circumferential indications or volumetric indications. All sleeved tubes with the circumferential indications were removed from service (four tubes were pulled; seven tubes were plugged). The sleeved tubes with volumetric indications were evaluated for location.
Sleeved tubes with volumetric indications located by EC below the centerline of the sleeve weld were removed from service; the remaining sleeved tubes were left in service (1 tube was pulled; 16 tubes were plugged; 34 tubes were left in service).
The five pulled sleeve / tube assemblies were examined by CE with oversight by the Electric Power Research Institute (EPRI). The results were documented in a March 1996 CE report, " Verification of the Structural Integrity of the ABB CEN0 Steam Generator Welded Sleeve," CEN-628-P, Revision 01-P.
To summarize the report, the EC indications were the result of either or both of two weld conditions termed " incomplete fusion" or " sleeve outside diameter (00) suckback" caused by improper cleaning of the parent tube prior to welding.
Although present since installation, the nondestructive examination (NDE) methods used at the time were not sensitive enough to detect these weld conditions. There was no evidence of inservice induced degradation.
The faulty installation process also affected sleeve / tube assemblies at the following plants: ANO-2, Ginna, Kewaunee and Zion-1 and -2.
The staff needs responses to the following questions to determine the licensee's plans with respect to inspection and repair of these sleeved tubes at the next outage.
(Questions do not need to be directed to Ginna since the SGs were recently replaced.)
Staff Questions 1.
During the licensee's next SG tube inspection, what is the licensee's intention regarding inspection of the upper weld in the existing CE-designed welded sleeves?
Include inspection scope and nondestructive methodology (ies) to be used, i
2.
What is the licensee's intention regarding disposition of sleeved tubes with weld zone indications? Include past practice and present intentions.
If the licensee intends to leave weld zone indications (WZIs) in service, provide the basis for the acceptability of this practice including the uncertainty in locating the exact position of volumetric flaws.
l 3.
The staff understands a CE topical report addressing the shortcomings found with previous installation practices (e.g., cleaning and NDE methods) is forthcoming.
Is it the licensee's intention to adopt this l
topical report when it is issued?
If so, how will the licensee incorporate this topical report into its Technical Specifications for future sleeving?
ENCLOSURE
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