ML082950386

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Acceptance Review Revised Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examinations (Relief Requests ISI-020 and ISI-021)-Calvert Cliffs Nuclear Power Plant, Unit No. 2
ML082950386
Person / Time
Site: Calvert Cliffs Constellation icon.png
Issue date: 10/24/2008
From: Pickett D
Plant Licensing Branch 1
To: Spina J
Calvert Cliffs
Pickett D
References
TAC MD9773, TAC MD9774
Download: ML082950386 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. James A. Spina, Vice President Calvert Cliffs Nuclear Power Plant, Inc.

Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702

SUBJECT:

ACCEPTANCE REVIEW RE: REVISED REQUEST TO EXTEND THE INSERVICE INSPECTION INTERVAL FOR REACTOR VESSEL WELD EXAMINATIONS (RELIEF REQUESTS ISI-020 AND ISI-021) - CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO.2 (TAC NOS. MD9773 AND MD9774)

Dear Mr. Spina:

By letter dated October 1, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082760280), the Calvert Cliffs Nuclear Power Plant, Inc.

resubmitted Relief Request Nos. ISI-020 and ISI-021 for the Calvert Cliffs Nuclear Power Plant, Unit No.2. The proposed relief requests would decrease the frequency of inspections by extending the American Society of Mechanical Engineers Boiler Pressure and Vessel Code (ASME Code),Section XI inservice inspection interval from the current 10 years to 20 years for ASME Code,Section XI examination Categories B-A and B-D reactor pressure vessel welds.

The letter also withdrew Relief Request Nos. ISI-020 and ISI-021 included in your application dated May 1, 2008 (ADAMS Accession No. ML081230381), that proposed deferring the subject weld examinations for one fuel cycle.

The purpose of this letter is to provide the results of the Nuclear Regulatory Commission (NRC) staff's acceptance review of these relief requests. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.

The NRC staff has reviewed your application and concluded that it provides technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.

J. Spina

- 2 If you have any questions, please contact me at 301-415-1364.

Sincerely,

.~J}~

Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-318 cc: Distribution via ListServ

J. Spina

- 2 If you have any questions, please contact me at 301-415-1364.

Sincerely,

/RA/

Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-318 cc: Distribution via ListServ Distribution:

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