ML18288A018

Upcoming Steam Generator Tube Inservice Inspection

ML18288A018
Person / Time
Site:	Palisades
Issue date:	10/16/2018
From:	Green K J Plant Licensing Branch III
To:	Entergy Nuclear Operations
Green K, 415-1627
References
EPID L-2018-LRO-0039
Download: ML18288A018 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Nuclear Operations, Inc. Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043-9530 October 16, 2018

SUBJECT:

PALISADES NUCLEAR PLANT-UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (EPID L-2018-LR0-0039)

Dear Sir or Madam:

lnservice inspection of steam generator (SG) tubes plays a vital role in assuring SG tube integrity.

A telephone conference will be arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming Palisades Nuclear Plant refueling outage. This call will occur after the majority of the tubes have been inspected, but before the SG inspection activities have been completed.

Enclosed is a list of discussion points to facilitate this call. The U.S. Nuclear Regulatory Commission (NRC) staff will document a publicly available summary of the conference call including any material that you provide to the NRC staff in support of the call. Should you have any questions you can contact me at 301-415-1627, or at Kimberly.G_reen@nrc.gov.

Docket No. 50-255

Enclosure:

SG Tube Inspection Discussion Points cc: ListServ Sincerely, Kimberly J. Green, Senior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation STEAM GENERA TOR TUBE INSPECTION DISCUSSION POINTS ENTERGY NUCLEAR OPERATIONS, INC. PALISADES NUCLEAR PLANT DOCKET NO. 50-255 The following discussion points have been prepared to facilitate the conference call that will be arranged with Entergy Nuclear Operations, Inc. to discuss the results of the steam generator (SG) tube inspections to be conducted during the upcoming fall 2018 refueling outage. This conference call will occur towards the end of the planned SG tube inspections but before the unit completes the inspections and repairs. The U.S. Nuclear Regulatory Commission (NRC) staff plans to document a publicly available summary of the conference call as well as any material that is provided in support of the call. 1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle. 2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results. 3. Discuss any exceptions taken to the industry guidelines.

4. For each SG, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion-transition, bends with a rotating probe), the scope of the inspection (e.g., 100 percent of dents/dings greater than 5 volts and a 20 percent sample between 2 and 5 volts), and the expansion criteria.

5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications identified to-date for each degradation mode (e.g., number of circumferential primary water stress corrosion cracking indications at the expansion transition).

For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the voltage, depth, and length of the indication).

In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit). 6. Describe repair/plugging plans. 7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).

Enclosure 8. Discuss the following regarding loose parts:

• what inspections are performed to detect loose parts

• a description of any loose parts detected and their location within the SG (including the source or nature of the loose part, if known)

• if the loose parts were removed from the SG

• indications of tube damage associated with the loose parts 9. Discuss the scope and results of any secondary side inspection and maintenance activities (e.g., in-bundle visual inspections, feedring inspections, sludge lancing, assessing deposit loading, etc). 10. Discuss any unexpected or unusual results. 11. Provide the schedule for SG-related activities during the remainder of the current outage.

SUBJECT:

PALISADES NUCLEAR PLANT-UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (EPID L-2018-LR0-0039)

DATED OCTOBER 16, 2018 DISTRIBUTION:

PUBLIC RidsAcrs_MailCTR Resource RidsNrrDorlLpl3 Resource RidsNrrDmlrMccb Resource RidsNrrPMPalisades Resource RidsNrrLASRohrer Resource RidsRgn3MailCenter Resource AHuynh, NRR AJohnson, NRR PKlein, NRR SBloom, NRR DHills, Region Ill ADAMS Accession No.: ML 18288A018

• via email/memo dated OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DMLR/MCCB/BC NAME KGreen SRohrer SBloom (MYoder for) DATE 10/15/18 10/15/18 10/16/18 OFFICE NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME DWrona KGreen DATE 10/16/18 10/16/18 OFFICIAL RECORD COPY