ML20206M758

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Forwards SE Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2
ML20206M758
Person / Time
Site: Arkansas Nuclear  
Issue date: 05/11/1999
From: Gramm R
NRC (Affiliation Not Assigned)
To: Hutchinson C
ENTERGY OPERATIONS, INC.
Shared Package
ML20206M764 List:
References
TAC-MA5146, TAC-MA5147, NUDOCS 9905170047
Download: ML20206M758 (4)


Text

May 11, 1999 o

Mr. C. Rindy Hutchinson.

Vics Presid:nt, Op: rations ANO Entsrgy Operations, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

EVALUATION OF ALTERNATIVE EXAMINATION 99-0-001 FOR ARKANSAS NUCLEAR ONE, UNIT NOS.1 AND 2 (TAC NOS. MA5146 AND MA5147)

Dear Mr. Hutchinson:

By letter dated April 1,1999, Entergy Operations, Inc., submitted Alternative Examination 99-0-001, requesting relief from the expedited examination of containment required by Title 10 of the Code of Federal Reaulations (10 CFR) Section 50.55a(g)(6)(ii)(B) and the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code)Section XI. To comply with the expedited examination of containment requirements of 10 CFR 50.55a(g)(6)(ii)(B), visual examinations of Class MC (and metallic liners of Class CC concrete components) must be performed in accordance with the requirements of Subsection IWE and visual examinations of Class CC (concrete components) must be' performed in accordance with the requirements of Subsection IWL.

t You requested authorization of an alternative examination pursuant to 10 CFR 50.55a(a)(3)(i) or (ii). An alternative to Code requirements was proposed that uses a combination of character-and workmanship-based samples to determine the resolution required to ensure that indications that might challenge containment integrity are detectable. Paragraph IWL-3111, Acceptance of Concrete, requires that the Responsible Engineer determine what surface conditions are acceptable and ensure there is no evidence of damage or degradation sufficient

- to warrant further evaluation or repair. Therefore, your Responsible Engineer will identify the minimum flaw size (indications of interest) required to be detected. For remote visual examinations, procedures and equipment used will be demonstrated to be capable of detecting and resolving these indications. A record of the demonstration performed will be maintained.

The staff has reviewed and evaluated the information in your request and finds that your proposed alternative provides an acceptable level of quality and safety. Therefore, this proposed alternative is authorized, pursuant to 10 CFR 50.55a(a)(3)(i), for the Arkansas

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Nuclear One, Unit Nos.1 and 2 containment inspections required to be completed, in accordance with 10 CFR 50.55a(g)(6)(ii)(B), by September 9,2001.

Sincerely, ORIG. SIGNED BY I

Robert A. Gramm, Chief, Section 1 I

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, g 9905170047 990511 Project Directorate IV & Decommissioning PDR ADOCK 05000313 Division of Licensing Project Management P

PDR Office of Nuclear Reactor Regulation Docket Nos. 50-313 and 50-368 DISTRIBUTION N.Hilton S.Richards (covert ltr only)

Enclosure:

Safety Evaluation (Docket Filer PUBLIC ACRS cc w/ encl: See next page PDIV-1 RF OGC C. Nolan K. Brockman, RIV G. Hill (4)

D. Lange, EDO D. Terao CNorsworthy (e-mail SE)

DOCUMENT NAME: G:\\ANO1-2\\ RELA 5146.WPD To receive a copy of this document, indicate in the box:

'C' = Copy without enclosures

  • E' = copy with enclosures

'N' = No copy OFFICE PDIV-1/PM L E

PDIV-1/LAh hE ECGB*

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PDIV-1/SC _. 6 NAME-NHILTON A Ll3ERRY XGl DTERAO RWEISMAN RGRAMM Sb DATE 05/ % /99 6 /l\\/99 I

4 / 29 /99 5/ 6/99 c~/ (//99

  • See Previous Concurrence OFFICIAL RECORD COPY

Mr. C. R:ndy Hutchinson Vice Pr2sident, Operations ANO Enttrgy Optritions, Inc.

1448 S. R. 333 Russellville, AR 72801 4

SUBJECT:

EVALUATION OF ALTERNATIVE EXAMINATION 99-0-001 FOR A NSAS NUCLEAR ONE, UNIT NOS.1 AND 2 (TAC NOS. MA5146 AND 147)

I

Dear Mr. Hutchinson:

By letter dated April 1,1999, Entergy Operations, Inc., submitted Alt ative Examination 99-0-001, requesting relief from the expedited exam tion of containment required by Title 10 of the Code of Federal Reaulations (10 CF Section 50.55a(g)(6)(ii)(B) and the requirements of the American Society of Mechani ngineers (ASME) Boiler and Pressure Vessel Code (Code)Section XI. To comply wit e expedited examination of containment requirements of 10 CFR 50.55a(g)(6)(ii)(B, visual examinations of Class MC (and J

metallic liners of Class CC concrete components) m t be performed in accordance with the requirements of Subsection IWE and visual exam ations of Class CC (concrete components) must be performed in accordance with the requ ments of Subsection lWL.

You requested authorization of an alternati examination pursuant to 10 CFR 50.55a(a)(3)(i).

An attemative to Code requirements was roposed that uses a combination of character-and workmanship based samples to deter e the resolution required to ensure that indications that might challenge containment integri 'are detectable. Paragraph IWL-3111, Acceptance of Concrete, requires that the Respo ble Engineer determines what surface conditions are acceptable and ensures there isp evidence of damage or degradation sufficient to warrant further evaluation or repair. Therefore, your Responsible Engineer will identify the minimum flaw size (indications or inter 9s't) required to be detected. For remote visual examinations, procedures and equipment sed will be demonstrated to be capable of detecting and resolving.

these indications. A rec of the demonstration performed will be maintained.

The staff has reviewed nd evaluated the information in your request and finds that your proposed alternative drovides an acceptable level of quality and safety. Therefore, this.

proposed alternativ/is authorized, pursuant to 10 CFR 50.55a(a)(3)(i), for the Arkansas Nuclear One, Uni hos.1 and 2 containment inspections required to be completed, in accordance wit 10 CFR 50.55a(g)(6)(ii)(B), by September 9,2001.

Sincerely, Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation et Nos. 50-313 and 50-368 DISTRIBUTION N.Hilton E closure: Safety Evaluation-Docket File PUBLIC ACRS w/oncl: See next page PDIV-1 RF OGC C. Nolan K. Brockman, RIV G. Hill (4)

D. Lange, EDO CNorsworthy (e-mail SE)

  • D. h,

DOCU ENT NAME: G:\\ANOFINAL\\ RELA 5146.WPD To receive a copy of this document, indicate in the box:

  • C' = copy without enclosures
  • E' = Copy with enclosures
  • N' = No copy OFFICE PDIV-1/PM E

PDIV-1/ LAM E

ECGB/BCA4, E

OGC8AD PDIV-1/SC NAME NHILTON #

L. BERRY W EIMBRO W ctM%

RGRAMM DATE 04/ r$ /99 W $o/99

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j NUCLEAR REGULATORY COMMISSION l

WASHINGTON, D.C. 30086-0001

\\NAT May 11, 1999

,,,g Mr. C. Randy Hutchinson Vice President, Operations ANO Entergy Operations, Inc.

1448 S. R. 333 j

Russellville, AR 72801

SUBJECT:

EVALUATION OF ALTERNATIVE EXAMINATION 99-0-001 FOR ARKANSAS NUCLEAR ONE, UNIT NOS.1 AND 2 (TAC NOS. MA5146 AND MA5147) f

Dear Mr. Hutchinson:

By letter dated April 1,1999, Entergy Operations, Inc., submitted Altemative Examination 99-0-001, requesting relief from the expedited examination of containment required by Title 10 of the Code of Federal Reaulations (10 CFR) Section 50.55a(g)(6)(li)(B) and the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code)Section XI. To comply with the expedited examination of containment requirements of 10 CFR 50.55a(g)(6)(ii)(B), visual examinations of Class MC (and metallic liners of Class CC concrete components) must be performed in accordance with the requirements of Subsection IL and visual examinations of Class CC (concrete components) must be performed in accordan e with the requirements of Subsection lWL.

You requested authorization of an alternative examination pursuant to 10 CFR 50.55a(a)(3)(i) 1 or (ii).' An alternative to Code requirements was proposed that uses a combination of character and workmanship-based samples to determine the resolution required to ensure that indications that might challenge containment integrity are detectable. Paragraph IWL-3111, Acceptance of Concrete, requires that the Responsible Engineer determine what surface i

conditions are acceptable and ensure there is no evidence of damage or degradation sufficient j

to warrant further evaluation or repair. Therefore, your Responsible Engineer will identify the minimum flaw size (indications of interest) required to be detected. For remote visual examinations, procedures and equipment used will be demonstrated to be capable of detecting j

and resolving these indications. A record of the demonstration performed will be maintained.

The staff has reviewed and evaluated the information in your request and finds that your l

proposed attemative provides an acceptable level of quality and safety. Therefore, this proposed alternative is authorized, pursuant to 10 CFR 50.55a(a)(3)(i), for the Arkansas Nuclear One, Unit Nos.1 and 2 containment inspections required to be completed, in accordance with 10 CFR 50.55a(g)(6)(li)(B), by September 9,2001.

I

'ncerely, Robert A. Gramm, Chief, Section 1 i

Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-313 and 50-368

Enclosure:

Safety Evaluation cc w/enci: See next page I

= _. _.

p Arkansas Nuclear One, Units 1 & 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 39286-1995 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 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 RusselMile, AR 72801

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