NL-16-055, Response to Request for Additional Information Regarding Relief Request IP2-ISl-RR-02 Alternate Examination Volume Required by Code Case N-729-1

Response to Request for Additional Information Regarding Relief Request IP2-ISl-RR-02 Alternate Examination Volume Required by Code Case N-729-1

ML16133A036
Person / Time
Site:	Indian Point
Issue date:	05/06/2016
From:	Coyle L Entergy Nuclear Northeast
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CAC MF7151, IP2-ISl-RR-02, NL-16-055
Download: ML16133A036 (5)

Text

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Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 254 6700 Lawrence Coyle Site Vice President NL-16-055 May 6, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11545 Rockville Pike, TWFN-2F1 Rockville, MD 20852-2738

SUBJECT:

Response to Request for Additional Information Regarding Relief Request IP2-ISl-RR-02 Alternate Examination Volume Required by Code Case N-729-1 (CAC No. MF7151)

Indian Point Unit 2 Docket No. 50-247 License No. DPR-26

REFERENCES:

1. NRG Letter to Entergy, Indian Point Nuclear Generating Unit No. 2- Request for Additional Information Regarding Relief Request IP2-ISl-RR-02 Alternative Examination Volume Required by Code Case N-729~1 (CAC NO. MF7151), April 26, 2016. .

2. Entergy Letter to NRG, NL-15-139, "Relief Request IP2-ISl-RR-02 Alternate Examination Volume Required by Code Case N-729-1," dated December 9, 2015 (Accession No. ML153498009).

Dear Sir or Madam:

The purpose of this letter is to provide a response to the NRG request for additional information (Reference 1) regarding Relief Request IP2-ISl-RR-02. The Entergy request for relief was transmitted in Reference 2.

There are no new commitments contained in this submittal. If you have any questions regarding this confirmation of receipt, please contact Mr. Robert Walpole, Manager, Regulatory Assurance at (914) 254-6710.

Respectfully, LC/sp Attachment and cc next page.

NL-16-055 Docket No. 50-247 Page 2 of 2

Attachment:

Response to Request for Additional Information on IP2-ISl-RR-02 cc: Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORL Mr. Daniel H. Dorman, Regional Administrator, NRC Region 1 NRC Resident Inspector Mr. John B. Rhodes, President and CEO, NYSERDA Ms. Bridget Frymire, New York State Dept. of Public Service

ATTACHMENT TO NL-16-055 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON IP2-ISl-RR-02 ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247

NL-16-055 Attachment Docket No. 50-247 Page 1 of 2 REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NO. IP2-ISl-RR-02 By letter dated December 9, 2015, (Accession Number ML15349B009), Entergy Nuclear Operations, Inc. submitted Relief Request IP2-ISl-RR-02 for Nuclear Regulatory Commission (NRC) review and approval. The request was to implement an alternative to the requirements of Title 10 of the Code of Federal Regulations, Section 50.55a(g)(6)(ii)(D)(3). The request pertains to the volumetric and/or surface examinations of reactor vessel upper head nozzles, most of which are used to.house control rod drive mechanisms. The requests and responses are as follows:

RAI 1

The NRC staff notes that a proposed alternative to the requirements of the code case is to be considered only when obstructions or limitations prevent meeting the requirements of Figure 2 of Code Case N-729-1. The staff also notes that the relief request does not identify the penetrations for which the requirements of Figure 2 cannot be met. Please provide a lii;;t of those penetrations for which the requirements of Figure 2 cannot be met and forWhich relief is requested.

Response

Based on Reactor Vessel head penetration examinations from 2R19 to 2R22, penetrations 1, 3, 4, 5,6, 7,8,9, 10, 11, 12, 13, 14, 15, 16, 17, 18, 19, 20,21, 22,23, 24,25, 26, 27,28,29, 30, 31, 32, 33, 34, 35, 36, and 37, do not meet the 1.5" examination volume criterion specified in Code Case N-729-1 for an incident angle of less than or equal to 30 degrees and penetrations 38, 39, 40, 41, 47, 52, 53, 58, 62, 64,65, 67,68, 70, 71, 74, 75, 77, 78, 79, 80, 81,82, 84,88, 89, 90, 93,94and 97 do not meet the 1.0" examination volume criterion specified in Code Case N-729-1 for an incident angle of greater than 30 degrees. Relief is requested for these penetrations.

Examinations performed from 2R19 to 2R22, examination volume coverage for penetrations 2, 42, 48, 50, 54, 56, 59, 60, 63, 66, 72, 76, 83, 85, 86, 87,91, 92 and 96 were measured to be within 0.080" of the examination volume criterion. Relief is also preemptively requested for these penetrations to avoid an exigent relief request. Entergy Letter NL-09-130 (Accession No. ML092800242) provides a diagram of these penetration locations.

The NRC staff notes that Table 1 of the relief request lists the minimum required ultrasonic testing*

(UT) coverage below the J-groove weld. The staff also notes that the request* states that UT coverage will extend down to "at least the top of the threaded region". The staff further notes that the request does not state that, for each penetration, the UT inspection which will be performed meets or exceeds the coverage requirement listed in Table 1. For each nozzle for which relief is requested, please confirm that UT coverage to "at least the top of the threaded region" meets or exceeds the requirements listed in Table 1.

NL-16-055 Attachment Docket No. 50-247 Page 2 of 2

Response

Entergy has confirmed that UT examination volume coverage to "at least the top of the threaded region" meets or exceeds the requirements listed in Table 1 of IP2-ISl-RR-02 for each nozzle identified in response to RAI 1 for which relief is requested.