ML16130A717
| ML16130A717 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/05/2016 |
| From: | Jennivine Rankin Plant Licensing Branch III |
| To: | Miksa J Entergy Nuclear Operations |
| References | |
| MF7554 | |
| Download: ML16130A717 (3) | |
Text
NRR-PMDAPEm Resource From: Rankin, Jennivine Sent: Thursday, May 05, 2016 2:38 PM To: MIKSA, JAMES P (jmiksa@entergy.com); ERICKSON, JEFFREY S (JERICKS@entergy.com)
Subject:
Palisades Nuclear Plant - Request for Additional Information - 2015 Steam Generator Tube Inspection Report (CAC No. MF7554)
Attachments: Final RAIs.docx Mr. Miksa and Mr. Erickson, By letter dated March 30, 2016 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML16092A086), in accordance with Technical Specification Section 5.6.8, Steam Generator Tube Inspection Report, Entergy Nuclear Operations, Inc. (the licensee) submitted information summarizing the results of the fall 2015 steam generator tube inspections performed at Palisades Nuclear Plant (PNP). The U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call regarding the fall 2015 SG tube inspections at PNP in a letter dated October 27, 2015 (ADAMS Accession Number ML15294A300).
The NRC staff has reviewed the information provided and determined that additional information is required in order to complete its review.
A draft request for additional (RAI) was transmitted on April 29, 2016. Please submit your response to the RAIs within 60 days of this e-mail. If you wish to alter the date of your response, please contact me at (301) 415-1530. Please treat this e-mail as formal transmittal of the RAIs.
- Thanks, Jennie Jennie Rankin, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1
Hearing Identifier: NRR_PMDA Email Number: 2828 Mail Envelope Properties (Jennivine.Rankin@nrc.gov20160505143700)
Subject:
Palisades Nuclear Plant - Request for Additional Information - 2015 Steam Generator Tube Inspection Report (CAC No. MF7554)
Sent Date: 5/5/2016 2:37:34 PM Received Date: 5/5/2016 2:37:00 PM From: Rankin, Jennivine Created By: Jennivine.Rankin@nrc.gov Recipients:
"MIKSA, JAMES P (jmiksa@entergy.com)" <jmiksa@entergy.com>
Tracking Status: None "ERICKSON, JEFFREY S (JERICKS@entergy.com)" <JERICKS@entergy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1249 5/5/2016 2:37:00 PM Final RAIs.docx 27692 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION FALL 2015 STEAM GENERATOR TUBE INSPECTIONS PALISADES NUCLEAR PLANT DOCKET NO. 50-255 By letter dated March 30, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16092A086), in accordance with Technical Specification Section 5.6.8, Steam Generator Tube Inspection Report, Entergy Nuclear Operations, Inc. (the licensee) submitted information summarizing the results of the fall 2015 steam generator tube inspections performed at Palisades Nuclear Plant (PNP). The U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call regarding the fall 2015 SG tube inspections at PNP in a letter dated October 27, 2015 (ADAMS Accession Number ML15294A300).
In order to complete the review, the NRC staff requests responses to the following questions:
- 1. In your letter dated August 5, 2014 (ADAMS Accession Number ML14218A548), primary to secondary leakage was reported as 0.0003 gallons per minute (0.4 gallons per day) or less over operating cycle 23 (2012 - 2014). Your letter dated March 30, 2016, indicated that primary to secondary leakage was approximately 5 gallons per day at the start of operating cycle 24, and trended downward throughout the cycle.
- a. Please discuss any insights you have into why the amount of primary to secondary leakage at the start of cycle 24 was greater than the amount of leakage at the end of cycle 23.
- b. Please discuss any actions taken to identify the source of the primary to secondary leakage and the results of those actions.
- 2. A few of the axial outside diameter stress corrosion cracking indications had structural depths exceeding 50 percent through wall. Please discuss any trends in the number and sizes of axial outside diameter stress corrosion cracking indications. Please discuss whether data quality during the 2015 outage was comparable to the data quality in prior outages.
NRR-PMDAPEm Resource From: Rankin, Jennivine Sent: Thursday, May 05, 2016 2:38 PM To: MIKSA, JAMES P (jmiksa@entergy.com); ERICKSON, JEFFREY S (JERICKS@entergy.com)
Subject:
Palisades Nuclear Plant - Request for Additional Information - 2015 Steam Generator Tube Inspection Report (CAC No. MF7554)
Attachments: Final RAIs.docx Mr. Miksa and Mr. Erickson, By letter dated March 30, 2016 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML16092A086), in accordance with Technical Specification Section 5.6.8, Steam Generator Tube Inspection Report, Entergy Nuclear Operations, Inc. (the licensee) submitted information summarizing the results of the fall 2015 steam generator tube inspections performed at Palisades Nuclear Plant (PNP). The U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call regarding the fall 2015 SG tube inspections at PNP in a letter dated October 27, 2015 (ADAMS Accession Number ML15294A300).
The NRC staff has reviewed the information provided and determined that additional information is required in order to complete its review.
A draft request for additional (RAI) was transmitted on April 29, 2016. Please submit your response to the RAIs within 60 days of this e-mail. If you wish to alter the date of your response, please contact me at (301) 415-1530. Please treat this e-mail as formal transmittal of the RAIs.
- Thanks, Jennie Jennie Rankin, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1
Hearing Identifier: NRR_PMDA Email Number: 2828 Mail Envelope Properties (Jennivine.Rankin@nrc.gov20160505143700)
Subject:
Palisades Nuclear Plant - Request for Additional Information - 2015 Steam Generator Tube Inspection Report (CAC No. MF7554)
Sent Date: 5/5/2016 2:37:34 PM Received Date: 5/5/2016 2:37:00 PM From: Rankin, Jennivine Created By: Jennivine.Rankin@nrc.gov Recipients:
"MIKSA, JAMES P (jmiksa@entergy.com)" <jmiksa@entergy.com>
Tracking Status: None "ERICKSON, JEFFREY S (JERICKS@entergy.com)" <JERICKS@entergy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1249 5/5/2016 2:37:00 PM Final RAIs.docx 27692 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION FALL 2015 STEAM GENERATOR TUBE INSPECTIONS PALISADES NUCLEAR PLANT DOCKET NO. 50-255 By letter dated March 30, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16092A086), in accordance with Technical Specification Section 5.6.8, Steam Generator Tube Inspection Report, Entergy Nuclear Operations, Inc. (the licensee) submitted information summarizing the results of the fall 2015 steam generator tube inspections performed at Palisades Nuclear Plant (PNP). The U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call regarding the fall 2015 SG tube inspections at PNP in a letter dated October 27, 2015 (ADAMS Accession Number ML15294A300).
In order to complete the review, the NRC staff requests responses to the following questions:
- 1. In your letter dated August 5, 2014 (ADAMS Accession Number ML14218A548), primary to secondary leakage was reported as 0.0003 gallons per minute (0.4 gallons per day) or less over operating cycle 23 (2012 - 2014). Your letter dated March 30, 2016, indicated that primary to secondary leakage was approximately 5 gallons per day at the start of operating cycle 24, and trended downward throughout the cycle.
- a. Please discuss any insights you have into why the amount of primary to secondary leakage at the start of cycle 24 was greater than the amount of leakage at the end of cycle 23.
- b. Please discuss any actions taken to identify the source of the primary to secondary leakage and the results of those actions.
- 2. A few of the axial outside diameter stress corrosion cracking indications had structural depths exceeding 50 percent through wall. Please discuss any trends in the number and sizes of axial outside diameter stress corrosion cracking indications. Please discuss whether data quality during the 2015 outage was comparable to the data quality in prior outages.