ML15107A257

NRR E-mail Capture - Additional Draft RAI Questions for Quad Cities (TAC Nos. MF3397 and MF3398)

ML15107A257
Person / Time
Site:	Quad Cities
Issue date:	04/17/2015
From:	Mozafari B Plant Licensing Branch III
To:	Nicely K Exelon Corp
References
TAC MF3397, TAC MF3398
Download: ML15107A257 (4)

Text

NRR-PMDAPEm Resource From: Mozafari, Brenda Sent: Friday, April 17, 2015 9:31 AM To: Nicely, Ken M.:(GenCo-Nuc) (ken.nicely@exeloncorp.com); Simpson, Patrick R.:(GenCo-Nuc) (patrick.simpson@exeloncorp.com)

Cc: Tate, Travis; Purnell, Blake

Subject:

Additional DRAFT RAI Questions for Quad Cities (TAC Nos. MF3397 AND MF3398)

Ken, The NRC staff has reviewed and evaluated the information provided by, Exelon Generation Company, LLC (EGC) (the licensee) in its letter dated October 16, 2014. The licensee submitted additional information for Request for Relief (RR) I4R-20 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI for Quad Cities Nuclear Power Station, Units 1 and 2 (QCNPS 1 and 2). The requests for relief apply to the fourth 10-year inservice inspection interval, in which the licensee adopted the 1995 Edition through the 1996 Addenda of ASME Code Section XI as the code of record.

SECOND REQUEST FOR ADDITIONAL INFORMATION ON THE FOURTH TEN YEAR 10-YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF I4R-20 FOR EXELON GENERATION COMPANY, LLC.

QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NUMBERS: 50-254 AND 50-265

1. SCOPE By letter dated January 23, 2014, (Agencywide Documents Access & Management System (ADAMS)

Accession Number ML14023A865), the licensee, Exelon Generation Company, LLC (EGC), submitted Request for Relief (RR) I4R-20 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components for Quad Cities Nuclear Power Station, Units 1 and 2 (QCNPS 1 and 2). The request for relief applies to the fourth 10-year inservice inspection (ISI) interval, in which the licensee adopted the 1995 Edition through the 1996 Addenda of ASME Code Section XI as the code of record. The U. S. Nuclear Regulatory Commission (NRC) requested that the licensee provide further information, and the licensee provided a response to the Request for Additional Information (RAI) in a letter dated October 16, 2014, (ADAMS Accession Number ML14293A450).

However, certain requested information was not provided and/or requires clarification in order for the staff to complete the evaluation of the licensees request. Answer the following questions.

2. REQUEST FOR ADDITIONAL INFORMATION 2.1 Request for Relief I4R-17, Examination Category B-A, Items B1.40 and B1.51, Pressure Retaining Welds in Vessels in Reactor Vessels, QCNPS 1 and 2 Table 2.1.1- Examination Category B-A (Unit 1)

Code Item Coverage Weld ID Weld Type 1/REACTORVESSEL/BMR-0 B1.51 RPV WELD BELTLINE REPAIR 83 0%

1/REACTORVESSEL/BMR-1 B1.51 RPV WELD BELTLINE REPAIR 87 0%

1

2.1.1 Provide coverage plots for all RPV beltline repair welds listed in Table 2.1.1 above. From the coverage records provided in the licensees RAI response, it is difficult to tell which areas have been covered.

2.2 Request for Relief I4R-20, Part B, Examination Category B-D, Item B3.90, Full 2

Penetration Welded Nozzles in Vessels, QCNPS 1 and 2 Verify in that the base materials near the inside surface of the weld joints, particularly the high regions of stress, were examined in the B-D, Items B3.90 welds in QCNPS 1 and 2.

2.3 Request for Relief I4R-20, Part D, Examination Category R-A, Item R1.20, Risk Informed Piping Examinations, QCNPS 1 The licensee requested relief for limited examinations of dissimilar metal welds included in their risk-informed piping program. These welds are designated as R1.20, which indicates that no known degradation mechanism has been identified. The licensee obtained significant volumetric coverage on these welds (approximately 86 per cent); however, it is unclear whether the correct RI-ISI designation has been assigned. Please discuss the following:

a. What are the materials of construction for the nozzle, the safe end, and the weld metal?

b. If the welds contains alloy 82, discuss the designation of the weld as R1.20 considering operational experience with stress corrosion cracking in Alloy 82 welds in Boiling Water Reactors.

Brenda L. Mozafari Senior Project Manager, NRR/DORL U.S. Nuclear Regulatory Commission Dresden 2/3 and Quad Cities 1/2 301-415-2020 email: brenda.mozafari@nrc.gov 3

Hearing Identifier: NRR_PMDA Email Number: 2005 Mail Envelope Properties (Brenda.Mozafari@nrc.gov20150417093100)

Subject:

Additional DRAFT RAI Questions for Quad Cities (TAC Nos. MF3397 AND MF3398)

Sent Date: 4/17/2015 9:31:08 AM Received Date: 4/17/2015 9:31:00 AM From: Mozafari, Brenda Created By: Brenda.Mozafari@nrc.gov Recipients:

"Tate, Travis" <Travis.Tate@nrc.gov>

Tracking Status: None "Purnell, Blake" <Blake.Purnell@nrc.gov>

Tracking Status: None "Nicely, Ken M.:(GenCo-Nuc) (ken.nicely@exeloncorp.com)" <ken.nicely@exeloncorp.com>

Tracking Status: None "Simpson, Patrick R.:(GenCo-Nuc) (patrick.simpson@exeloncorp.com)"

<patrick.simpson@exeloncorp.com>

Tracking Status: None Post Office:

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