ML14064A372

NRR E-mail Capture - Request for Additional Information - Palisades - RR 4-19 - Proposed Alternative to the Requirements of ASME Code Case N-638-4 - MF3517

ML14064A372
Person / Time
Site:	Palisades
Issue date:	02/28/2014
From:	Mahesh Chawla Division of Operating Reactor Licensing
To:	Erickson J Entergy Nuclear Palisades
References
MF3517
Download: ML14064A372 (4)

Text

NRR-PMDAPEm Resource From: Chawla, Mahesh Sent: Friday, February 28, 2014 1:55 PM To: ERICKSON, JEFFREY S (JERICKS@entergy.com); MIKSA, JAMES P (jmiksa@entergy.com); DOTSON, BARBARA E (bdotson@entergy.com)

Cc: Tsao, John; Lupold, Timothy; Cheruvenki, Ganesh; Carlson, Robert; Taylor, Thomas; Duncan, Eric; Scarbeary, April; Shah, Swetha

Subject:

Request for Additional Information - Palisades - RR 4 Proposed Alternative to the Requirements of ASME Code Case N-638 MF3517 Attachments: MF3517_RAI_1 .docx By letter dated February 26, 2014 (ADAMS Accession No. ML14057A766), Entergy Nuclear Operations, LLC (the licensee) requested relief for the proposed alternative to repair degraded weld PCS-6-PRS-1C1-1 of the pressurizer safety relief valve at the Palisades Nuclear Plant. The proposed alternative is documented in Relief Request RR 4-19. To complete its review, the Nuclear Regulatory Commission (NRC) staff requests additional information identified in the attached file. In case of any further questions, please contact me.

Mahesh Chawla Project Manager Phone: 301-415-8371 Fax: 301-415-1222 mahesh.chawla@nrc.gov 1

Hearing Identifier: NRR_PMDA Email Number: 1139 Mail Envelope Properties (Mahesh.Chawla@nrc.gov20140228135400)

Subject:

Request for Additional Information - Palisades - RR 4 Proposed Alternative to the Requirements of ASME Code Case N-638 MF3517 Sent Date: 2/28/2014 1:54:41 PM Received Date: 2/28/2014 1:54:00 PM From: Chawla, Mahesh Created By: Mahesh.Chawla@nrc.gov Recipients:

"Tsao, John" <John.Tsao@nrc.gov>

Tracking Status: None "Lupold, Timothy" <Timothy.Lupold@nrc.gov>

Tracking Status: None "Cheruvenki, Ganesh" <Ganesh.Cheruvenki@nrc.gov>

Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov>

Tracking Status: None "Taylor, Thomas" <Thomas.Taylor@nrc.gov>

Tracking Status: None "Duncan, Eric" <Eric.Duncan@nrc.gov>

Tracking Status: None "Scarbeary, April" <April.Scarbeary@nrc.gov>

Tracking Status: None "Shah, Swetha" <Swetha.Shah@nrc.gov>

Tracking Status: None "ERICKSON, JEFFREY S (JERICKS@entergy.com)" <JERICKS@entergy.com>

Tracking Status: None "MIKSA, JAMES P (jmiksa@entergy.com)" <jmiksa@entergy.com>

Tracking Status: None "DOTSON, BARBARA E (bdotson@entergy.com)" <bdotson@entergy.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 661 2/28/2014 1:54:00 PM MF3517_RAI_1 .docx 23400 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION RELIEF REQEUST NUMBER RR 4-19 ALTERNATIVE REPAIR OF WELD AT PRESSURIZER SAFETY RELIEF VALVE NOZZLE PALISADES NUCLEAR PLANT ENTERGY NUCLEAR OPERATIONS DOCKET NO. 50-255 By letter dated February 26, 2014 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML14057A766), Entergy Nuclear Operations, LLC (the licensee) requested relief for the proposed alternative to repair degraded weld PCS PRS-1C1-1 of the pressurizer safety relief valve at the Palisades Nuclear Plant. The proposed alternative is documented in Relief Request RR 4-19. To complete its review, the Nuclear Regulatory Commission (NRC) staff requests following additional information.

1. Relief Request RR-4-19 discussed the use of American Society of Mechanical Engineers (ASME) Code Case N-638-4 with deviations. However, it is not clear to the NRC staff from which articles in the ASME Code,Section XI, the relief is requested.

Section 3 of the relief request alluded to the hardship that would be encountered if the proposed repair were to follow IWA-4600 and IWA-4630 of the ASME Code,Section XI.

The Inquiry section of ASME Code Case N-638-4 referenced IWA-4400. Provide the articles and/or subarticles of the ASME Code,Section XI, from which the relief is requested.

2. Section 3 of the relief request stated that the new dissimilar metal weld will be installed and examined in accordance with the 1992 Edition of the ASME Code,Section III, Subsection NB. (a) Discuss why the 1992 edition of the ASME Code,Section III was selected for the installation and examination of the new weld. (b) Section 2 of ASME Code Case N-638-4 requires that the welding qualification follows ASME Code,Section IX. Discuss which edition of the ASME Code,Section IX, will be used for the welding qualification.

3. Figure 2, Note 9 stated that the final butt weld shall be radiographic and liquid penetrant examined per NB-5222 of the ASME Code,Section III. Note 9 further stated that if required, a PSI [pre-service inspection] ultrasonic examination shall be performed in accordance with NB-5111(b) of the ASME Code,Section III. (a) Discuss whether a liquid penetrant examination will be conducted after butter is installed. If not, discuss whether a visual examination will be performed on the butter to ensure no fabrication defect. (b) The proposed relief request did not specify an ultrasonic examination for the pre-service examination. The future inservice inspections of the subject weld will most likely be performed using ultrasonic testing. The result of a pre-service ultrasonic examination would provide the baseline information for the future ultrasonic examinations. Discuss whether an ultrasonic examination will be performed on the subject weld prior to placing the repaired weld in service. (c) Section 4 of ASME Code Case N-638-4 discusses a surface examination prior to welding and visual examinations.

However, the relief request did not mention the surface examination prior to welding and any visual examinations. Discuss whether the relief request will follow all the examination requirements as specified Section 4 of Code Case N-638-4.

4. Provide the inside and outside diameter of the nozzle, nozzle wall thickness (the thickness that is close to the pressurizer shell), and weld wall thickness of the repaired weld as shown in Figure 2.

5. Confirm that the two indications detected in the existing subject weld will be removed as result of the proposed repair.