ML041350296

Relief, NRC Order Modifying Licenses (Effective Immediately) (EA-03-009) for the Reactor Pressure Vessel Head Penetration Nozzles, MC1915

ML041350296
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/29/2004
From:	Berkow H NRC/NRR/DLPM/LPD4
To:	Burford F Entergy Operations
Alexion T W, NRR/DLPM, 415-1326
References
EA-03-009, TAC MC1915
Download: ML041350296 (5)

Text

April 29, 2004 Mr. F. G. Burford, Acting Director Nuclear Safety & Licensing Entergy Operations, Inc.

1340 Echelon Parkway Jackson, MS 39213-8298

SUBJECT:

ARKANSAS NUCLEAR ONE, UNIT 1 (ANO-1) - RELAXATION REQUEST FROM U.S. NUCLEAR REGULATORY COMMISSION (NRC)

"ORDER MODIFYING LICENSES (EFFECTIVE IMMEDIATELY)" (EA-03-009),

ISSUED FEBRUARY 11, 2003, FOR THE REACTOR PRESSURE VESSEL HEAD PENETRATION NOZZLES (TAC NO. MC1915)

Dear Mr. Burford:

By letter dated February 3, 2004, as supplemented by letter dated April 21, 2004, Entergy Operations, Inc. (Entergy or the licensee) requested relaxation to implement an alternative to the requirements of Section IV.C.(1)(b)(i), of the Order for sixty control rod drive mechanism (CRDM) nozzles and one radiation calibration instrumentation nozzle at ANO-1. Specifically, pursuant to the process specified in Section IV, Paragraph F of the Order, you requested relaxation from the requirement specified in Section IV.C.(1)(b)(i), to instead perform inspections using ultrasonic testing and analysis.

The NRC staff has completed its review and concludes that the proposed alternative examination of the reactor pressure vessel (RPV) head provides reasonable assurance of structural integrity of the head. Further inspection of the head surface in accordance with Section IV.C.(1)(b)(i) of the Order would result in hardship without a compensating increase in the level of quality and safety. Thus, you have demonstrated good cause for the requested relaxation. Therefore, pursuant to Section IV, Paragraph F of the Order, I authorize, for one operating cycle commencing with the startup from the Spring 2004 refueling outage, the proposed alternative inspection for sixty CRDM head penetration nozzles and one radiation calibration instrumentation nozzle at ANO-1, subject to the following condition:

If the NRC staff finds that the crack-growth formula in MRP-55 is unacceptable, Entergy shall revise its analysis that justifies relaxation of the Order within 30 days after the NRC informs Entergy of an NRC-approved crack-growth formula. If Entergys revised analysis shows that the crack growth acceptance criteria are exceeded prior to the end of the operating cycle which follows the current refueling outage, this relaxation is rescinded and Entergy will, within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br />, submit to the NRC written justification for continued operation. If the revised analysis shows that the crack growth acceptance criteria are exceeded during the subsequent operating cycle, Entergy shall, within 30 days, submit the revised analysis for NRC review. If the revised analysis shows that the crack growth acceptance criteria are not exceeded during either the upcoming operating cycle or the subsequent operating cycle, Entergy shall, within 30 days, submit a letter to the NRC confirming that its analysis has been revised. Any future

F. G. Burford crack-growth analyses performed for the upcoming operating cycle and future cycles for RPV head penetrations will be based on an NRC-acceptable crack growth rate formula.

The staff's related Safety Evaluation (SE) is enclosed.

Pursuant to 2.390 of Title 10 of the Code of Federal Regulations (10 CFR), we have determined that the enclosed SE does not contain proprietary information. However, we will delay placing the SE in the public document room for ten working days from the date of this letter to provide you with the opportunity to comment on the proprietary aspects only. If you believe that any information in the enclosure is proprietary, please identify such information line by line and define the basis pursuant to the criteria of 10 CFR 2.390.

Be aware that when vessel head inspections are performed using American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) requirements, acceptance criteria, or qualified personnel, those activities and all related activities fall within the jurisdiction of the ASME Code. Therefore, Order-related inspection activities may be subject to third party review, including those by the Authorized Nuclear Inservice Inspector.

Sincerely,

/RA/

Herbert N. Berkow, Director Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313

Enclosure:

SE cc w/o encl: See next page

F. G. Burford crack-growth analyses performed for the upcoming operating cycle and future cycles for RPV head penetrations will be based on an NRC-acceptable crack growth rate formula.

The staff's related Safety Evaluation (SE) is enclosed.

Pursuant to 2.390 of Title 10 of the Code of Federal Regulations (10 CFR), we have determined that the enclosed SE does not contain proprietary information. However, we will delay placing the SE in the public document room for ten working days from the date of this letter to provide you with the opportunity to comment on the proprietary aspects only. If you believe that any information in the enclosure is proprietary, please identify such information line by line and define the basis pursuant to the criteria of 10 CFR 2.390.

Be aware that when vessel head inspections are performed using American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) requirements, acceptance criteria, or qualified personnel, those activities and all related activities fall within the jurisdiction of the ASME Code. Therefore, Order-related inspection activities may be subject to third party review, including those by the Authorized Nuclear Inservice Inspector.

Sincerely,

/RA/

Herbert N. Berkow, Director Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313

Enclosure:

SE cc w/o encl: See next page DISTRIBUTION:

PUBLIC RidsNrrLADJohnson (2) GHill (4)

PDIV-1 r/f RidsRgn4MailCenter (AHowell) RTadessee RidsOgcRp RidsNrrDlpmLpdiv (HBerkow) TChan RidsAcrsAcnwMailCenter RidsNrrDlpmLpdiv1 (RGramm) RidsNrrPMTAlexion RidsNrrLADBaxley GGeorgiev RGuzman Accession No.:ml041350296 *SE input with no major changes.

OFFICE PDIV-1/PM PDIV-1/LA EMCB/SC* OGC (NLO) PDIV-1/SC PDIV-1/D NAME TAlexion DBaxley TChan GLongo for RGramm HBerkow JGoldberg DATE 4/29/04 4/28/04 4/23/04 04/28/04 4/29/04 4/29/04 DOCUMENT NAME: C:\MYFILES\Copies\RELMC1915.wpd

OFFICIAL RECORD COPY Arkansas Nuclear One 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 Mr. Jeffrey S. Forbes Little Rock, AR 72205-3867 Site Vice President Arkansas Nuclear One Winston & Strawn Entergy Operations, Inc.

1400 L Street, N.W. 1448 S. R. 333 Washington, DC 20005-3502 Russellville, AR 72801 Mr. Mike Schoppman Framatome ANP, Richland, Inc.

Suite 705 1911 North Fort Myer Drive Rosslyn, VA 22209 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 November 2003