ML103160093

Request for Additional Information Relief Request No. RR-SNUB-1, Snubber Inspection and Testing for Forth 10-Year Interval - Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 - (TAC Nos. ME4892 and ME4893)

ML103160093
Person / Time
Site:	Calvert Cliffs
Issue date:	11/17/2010
From:	Pickett D V Plant Licensing Branch 1
To:	Gellrich G H Calvert Cliffs
Pickett D V
References
TAC ME4892, TAC ME4893
Download: ML103160093 (4)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. NoveT"lher

17. Mr. George H. Gellrich, Vice President Calvert Cliffs Nuclear Power Plant, LLC Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUEST NO. RR-SNUB-1, SNUBBER INSPECTION AND TESTING FOR FORTH 10-YEAR INTERVAL -CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -(TAC NOS. ME4892 AND ME4893)

Dear Mr. Gellrich:

By letter dated October 11, 2010 (Agencywide Document Access and Management System Accession No. ML 102870107), Calvert Cliffs Nuclear Power Plant, LLC submitted Relief Request RR-SNUB-1 as an alternative to the American Society of Mechanical Engineers (ASME) Code requirements for snubber inspections and testing for the Fourth 10-Year Inservice Inspection Interval. Based upon the Nuclear Regulatory Commission (NRC) staff review, additional information will be necessary for the staff to complete its review. Enclosed is the NRC staff's request for additional information (RAI). Based on discussions with your staff, we understand that you plan to respond to the enclosed RAI no later than December 17, 2010. Please contact me at 301-415-1364 if you have any questions.

Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318

Enclosure:

As stated cc w/encl:

Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION CALVERT CLIFFS NUCLEAR POWER PLANT, LLC CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 RELIEF REQUEST NO. RR-SNUB-1 SNUBBER INSPECTION AND TESTING FOR FOURTH 10-YEAR INTERVAL DOCKET NOS. 50-317 AND 50-318 The applicable ASME Code for the inservice inspection (lSI) program at Calvert Cliffs is the American Society of Mechanical Engineers (ASME)Section XI, 2004 Edition. Article IWF-5000 of the ASME Section XI Code, contains inservice examination and testing requirements of snubbers. The licensee proposed to use Calvert Cliffs Technical Requirement Manual (TRM) Section 15.7.2 in lieu of the ASME Code requirements. The submitted Relief Request RR-SNUB-1 is only related to inservice snubber visual inspection examination, without mentioning inservice testing of snubbers. Article 5000 contains IWF-5200, "Preservice Examinations and Tests," IWF-5300, "Inservice Examination and Tests," and IWF-5400, "Repair and Replacement," requirements for snubbers. (a) Please explain whether and how the requirements of IWF-5200(a) and (b) will be met. Confirm that the VT-3 examination method described in IWA-2213 is being used for preservice examinations. (b) IWF-5300(b) states that "Inservice tests shall be performed in accordance with ASME/ANSI OM, Part 4." Please confirm that TRM Section 15.7.2 meets the 5300(b) requirement. (c) IWF-5400 requires that "Repair or replacement of snubbers shall be in accordance with IWA-4000. Repaired or replacement snubbers shall be examined and tested in accordance with the applicable requirements of Subarticle IWF-5200 prior to return to service." Please explain how TRM 15.7.2 meets the requirements of IWF-5400. (d) Please explain how TRM Section 15.7.2 meets the requirements of IWF-5200(c), and IWF-5300(c) requirements. ASME Section XI, IWF-5300(a) requires that inservice examinations shall be performed in accordance with ASME/ANSI OM, Part 4, using the VT-3 examination method described in IWA-2213. Please confirm that the VT-3 method is being used at Calvert Cliffs for inservice examinations.

Enclosure

-2TRM Section 15.7.2 only contains requirements related to "Hydraulic Snubbers Functional Test Acceptance Criteria." Please confirm that there are no mechanical snubbers installed at Calvert Cliffs 1 or 2. The requested alternative and TRM Section 15.7.2 do not address the requirements of OM-4, Section 2.3.4.3, "Examination Failure Mode Groups," and Section 3.2.4.2, "Test Failure Mode Groups," related to inservice examination and functional testing of snubbers. Please explain how the TRM meets these requirements. The applicable Code for the Calvert Cliffs lSI program is ASME Section XI, 2004 Edition. Please confirm that Calvert Cliffs meets the requirements of IWA-6230, "Summary Report Preparation," for snubber visual examination and testing.

November 17, 2010 Mr. George H. Gellrich, Vice President Calvert Cliffs Nuclear Power Plant, LLC Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUEST NO. RR-SNUB-1, SNUBBER INSPECTION AND TESTING FOR FORTH 10-YEAR INTERVAL -CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -(TAC NOS. ME4892 AND ME4893)

Dear Mr. Gellrich:

By letter dated October 11, 2010 (Agencywide Document Access and Management System Accession No. ML 102870107), Calvert Cliffs Nuclear Power Plant, LLC submitted Relief Request RR-SNUB-1 as an alternative to the American Society of Mechanical Engineers (ASME) Code requirements for snubber inspections and testing for the Fourth 1O-Year Inservice Inspection Interval. Based upon the Nuclear Regulatory Commission (NRC) staff review, additional information will be necessary for the staff to complete its review. Enclosed is the NRC staff's request for additional information (RAI). Based on discussions with your staff, we understand that you plan to respond to the enclosed RAI no later than December 17, 2010. Please contact me at 301-415-1364 if you have any questions.

Sincerely, IRA! Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegUlation Docket Nos. 50-317 and 50-318

Enclosure:

As stated cc w/encl: Distribution via Listserv Distribution:

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