ML20126H837

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Forwards SE Granting Relief from Certain Inservice Insp Requirements of Section XI of ASME Boiler & Pressure Vessel Code Determined to Be Impractical to Perform
ML20126H837
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 12/30/1992
From: Larkins J
Office of Nuclear Reactor Regulation
To: Yelverton J
ENTERGY OPERATIONS, INC.
Shared Package
ML20126H842 List:
References
TAC-M76001, NUDOCS 9301050339
Download: ML20126H837 (4)


Text

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- NUCLEAR REGULATORY COMMISSION WASHINGT ON, D. C. 20555

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k .n.. December 30, 1992 Docket-No. 50-368 '

Mr. Jerry W. Yelverton Vice President, Operations AND Entergy Operations, Inc.

Route 3 Box-137G--

Russellville, Arkansas 72801 -!

Dear Mr. Yelverton:

SUBJECT:

FIRST-10-YEAR INSERVICE INSPECTION RELIEF REQUESTS,-ARKANSAS: NUCLEAR ONE, UNIT 2 (ANO-2) (TAC NO. M76001)

In a letter to the NRC dated August-31, 1989 Entergy Operations,--Inc. (the licensee), requested relief from certain inservice inspection requirements ofJ Section XI of-the ASME Boiler and Pressure Vessel Code, that had been .

determined to be impractical to perform at ANO The NRC staff issued a:

request for additional information_(RAI) in a letter dated September 10,n1991.

In response.to the RAI and-a conference call on December 10,:1991 Ethe licensee provided a' table with estimated-percentages of the code-required'.

examinations for some weldsLand withdrew the requests for relief on other. I welds in a submittal dated April. 30, 1992. Issues not-resolved by the-April 30,-1992' submittal were discussed with the licensee during a conference- '

call held on June' 3, -1992.1 Additional information regarding the April 30, L1992, submittal was provided-in a submittal dated August 20, 1992. r The NRC staff,Lwith assistance from its contractor Idaho NationalJ Engineering -

Laboratory (INEL), has reviewed and evaluated the First 10-Year Intervali inservice Inspection requests- for relief: and the additional' information-provided regarding ANO-2. Based upon information submitted,- the :statf has determined that for the requests.for relief submitted.(except for 8-B/B3;1,>

B-J/B4.5 (in part), and C-E-1/C2.5), either. relief. is not ~ required, or' the -

code-required examinations-of the components cited by the111censee:are-_

impractical to perform and relief. is granted.

Where relief is- granted, the NRC staff has determined that-the granting of -

relief is authorized by law, will not endanger life or: property or the; common >

. defense and security,' and'is otherwise in.the public interest'.: -In making:this-

determination, we have'given due consideration to the burden that.could result!

if the applicable ASME Code requirements were imposed on your facility. -.Where

-these-findings:could not be made, the requests for. relief were denied.

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.Mr. Jerry W. Yelverton -December 30, 1992 The licensee is-required to perform the appropriate inspections-that are denied at the next scheduled outage of sufficient duration or resubmit these:

requests with additional information. A summary of-the requirements and the bases for our findings are contained in the enclosed Safety Evaluation.

This action closes TAC No. M76001.

Sincerely, ORIGINAL SIGNED BY: Thomas Alexion for John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation =

Enclosure:

Safety Evaluation cc w/ enclosure:

See next page DISTRIBUTION:

TDocketJFiler* NRC & Local PDRs PD4-1 r/f J. Roe T. Murley F. Miraglia J. Partlow B. Grimes M,Virgilio J. Larkins- P Noonan PD4-1 p/f T. Alexion ACRS (10) A. B.-Beach D. Smith J. Lieberman LE. Jordan G. Hill (4) OPA OC/LFDCB J. Mitchell OGC

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0FC LA:PD4-Jw Pit:BD4 N IT '0GC/h D:P 4 l NAME' PNoonan Y >TAlexion:h'f /k// dJLarkins DATE O/d/92 N/1\/92 /1 W/ 92 f [L/SO/92 0FFICIAL RECORD COPY Document Name: AR276001.rel l

Mr. Jerry W. Yelverton December 30, 1992 The licensee is required to perform the appropriate inspections that are denied at the next scheduled outage of sufficient duration or resubmit.these requests with additional information. A summary of the requirements and the bases for our findings are contained in the enclosed Safety Evaluation.

This action closes TAC No M76001.

Sincerely,

& WL J

)bohnT.Larkins,Directo roject Directorate IV-1 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation

Enclosure:

Safety Evaluation cc w/ enclosure:

See next page

,m. _ _ - _ , . . . _ - . . , _ _ _ . , . - .-

Mr. Jerry W. Yelverton .

Entergy Operations, Inc. Arkansas Nuclear One, Unit 2 CC:

Mr. Donald C. Hintz, President Mr. John R. McGaha and Chief Executive Officer Vice President, Operations Support Entergy Operations, Inc. Entergy Operations, Inc.

P. O. Box 31995 P. O. Box 31995 Jackson, Mississippi 39286 Jackson, Mississippi 39286 Mr. Robert B. McGehee Mr. R. A. Fenech Wise, Carter, Child & Caraway General Manager, Plant Operations P. O. Box 651 Entergy Operations, Inc. Jackson, Mississippi 39205 Route 3 Box 137G Russellville, Arkansas 72801 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations Mr. Nicholas S. Reynolds ABB Combustion Engineering Nuclear. Power Winston & Strawn 12300 Twinbrook Parkway, Suite 330 1400 L Street, N.W. Rockville, Maryland' 20852 Washington, D.C. 20005-3502 Admiral Kinnaird R. McKee, USN (Ret)

Mr. Robert B. Borsum 214 South Morris Street-Licensing Representative Oxford, Maryland 21654 B&W Nuclear Technologies 1700 Rockville Pike, Suite 525 Mr. James J. Fisicaro Rockville, Maryland 20852 Director, Licensing Entergy Operations, Inc.

Senior Resident Inspector Route 3, Box 137G U.S. Nuclear Regulatory Commission Russellville, Arkansas 72801 1 Nuclear Plant Road-Russellville, Arkansas 72801 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611~Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Honorable Joe W. Phillips County Judge of Pope Ccunty Pope County Courthouse Russellville, Arkansas 72801 Ms. Greta Dicus, Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little-Rock, Arkansas 72205-3867