ML082730800

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Upcoming Steam Generator Tube Inservice Inspection
ML082730800
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 10/28/2008
From: Wang A
Plant Licensing Branch IV
To:
Entergy Operations
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC MD9729
Download: ML082730800 (5)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 October 28, 2008 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802

SUBJECT:

ARKANSAS NUCLEAR ONE, UNIT NO. 1 - UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (MD9729)

Dear Mr. Sir or Madam:

lnservice inspections of steam generator (SG) tubes playa vital role in assuring SG tube integrity. The reporting requirements of plant Technical Specifications require submission of a report within 180 days following completion of the inspection. The content of the report normally includes the following:

1. The scope of inspections performed on each SG,
2. Active degradation mechanisms found,
3. Nondestructive examination techniques utilized for each degradation mechanism,
4. Location, orientation (if linear), and measured sizes (if available) of service induced indications,
5. Number of tubes plugged during the inspection outage for each active degradation mechanism,
6. Total number and percentage of tubes plugged to date, and
7. The results of condition monitoring, including the results of tube pulls and in situ testing.

A telephone conference call has been arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming Arkansas Nuclear One, Unit 1 refueling outage 1R21. This phone call will occur the week of November 3, 2008, after the majority of the tubes have been inspected, but before the SG inspection activities have been completed. Attached is a list of discussion points to facilitate this phone conference.

-2 The U.S. Nuclear Regulatory Commission (NRC) staff plans to document a summary of the conference call, including any material that you provide to the NRC staff in support of the call.

Sincerely,

~V\ tJ O"lV\

Alan B. Wang, Projed"Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-313

Enclosure:

SG Tube Inspection Discussion Points cc w/encl: Distribution via ListServ

OFFICE OF NUCLEAR REACTOR REGULATION STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS REFUELING OUTAGE 1R21 RENEWED FACILITY OPERATING LICENSE NO. DPR-51 ENTERGY OPERATIONS, INC.

ARKANSAS NUCLEAR ONE, UNIT NO.1 DOCKET NO. 50-313 The following discussion points have been prepared to facilitate the telephone conference call arranged with the Entergy Operations, Inc. (Entergy, the licensee), to discuss the results of the steam generator tube inspections to be conducted during the upcoming fall 2008, Arkansas Nuclear One, Unit 1 (ANO-1) refueling outage (1 R21). This conference call is scheduled to occur towards the end of the planned SG tUbe inspections, but before the Entergy completes the inspections and repairs.

The U.S. Nuclear Regulatory Commission staff plans to document a 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 steam generator, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion transition, U-bends with a rotating probe), the scope of the inspection (e.g., 100% of dents/dings greater than 5 volts and a 20% 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

-2 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).
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 steam generator (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, feed ring inspections, sludge lancing, assessing deposit loading, etc).
10. Discuss any unexpected or unusual results.
11. Provide the schedule for steam generator-related activities during the remainder of the current outage.
12. Discuss the results of the tie-rod bowing identified during the outage. Include the following in the discussion:
  • Was bowing identified in one or both SGs
  • Was bowing consistent with what was expected - if not explain
  • What areas of the SG has bowing
  • What is the maximum lateral bow identified
  • Is the current operability still bounding
  • What repairs if any will be required for startup

October 28, 2008

-2 The U.S. Nuclear Regulatory Commission (NRC) staff plans to document a summary of the conference call, including any material that you provide to the NRC staff in support of the call.

Sincerely, IRA I Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-313

Enclosure:

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