ML072540033

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Refueling Outage T1R17 Steam Generator Tube Inspection
ML072540033
Person / Time
Site: Crane Constellation icon.png
Issue date: 09/27/2007
From: Peter Bamford
NRC/NRR/ADRO/DORL/LPLI-2
To: Crane C
AmerGen Energy Co
Bamford, Peter J., NRR/DORL 415-2833
References
TAC MD6686
Download: ML072540033 (6)


Text

September 27, 2007 Mr. Christopher M. Crane President and Chief Executive Officer AmerGen Energy Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT 1 - REFUELING OUTAGE T1R17 STEAM GENERATOR TUBE INSPECTION (TAC NO. MD6686)

Dear Mr. Crane:

Inservice inspections of steam generator (SG) tubes play a vital role in assuring that adequate structural integrity of the tubes is maintained. As required by the plant technical specifications, such reporting requirements can range from submitting a special report within 15 days following completion of each inservice inspection of SG tubes and identifying the number of tubes plugged and/or repaired, to submitting a special report within 12 months following completion of the inspection and providing complete results of the SG tube inservice inspection.

We have requested a telephone conference with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming Refueling Outage T1R17. Your staff has agreed to participate. This discussion 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 phone conference. Upon completion of the discussion, we plan to prepare a brief summary of the conference call and docket any supporting material that you may have provided in support of the call.

If you need clarification of this matter, please feel free to contact me at 301-415-2833.

Sincerely,

/RA/

Peter J. Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-289

Enclosure:

Discussion Points cc w/encl: See next page

September 27, 2007 Mr. Christopher M. Crane President and Chief Executive Officer AmerGen Energy Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT 1 - REFUELING OUTAGE T1R17 STEAM GENERATOR TUBE INSPECTION (TAC NO. MD6686)

Dear Mr. Crane:

Inservice inspections of steam generator (SG) tubes play a vital role in assuring that adequate structural integrity of the tubes is maintained. As required by the plant technical specifications, such reporting requirements can range from submitting a special report within 15 days following completion of each inservice inspection of SG tubes and identifying the number of tubes plugged and/or repaired, to submitting a special report within 12 months following completion of the inspection and providing complete results of the SG tube inservice inspection.

We have requested a telephone conference with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming Refueling Outage T1R17. Your staff has agreed to participate. This discussion 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 phone conference. Upon completion of the discussion, we plan to prepare a brief summary of the conference call and docket any supporting material that you may have provided in support of the call.

If you need clarification of this matter, please feel free to contact me at 301-415-2833.

Sincerely,

/RA/

Peter J. Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-289

Enclosure:

Discussion Points cc w/encl: See next page DISTRIBUTION Public RidsNrrDorlLpl1-2 RidsNrrLAABaxter RidsNrrLACSola LPL1-2 R/F RidsNrrPMPBamford RidsAcrsAcnwMailCenter RidsRgn1MailCenter RidsOgcRp AJohnson, NRR KKarwoski, NRR ACCESSION NO.: ML072540033 OFFICE LPL1-2/PM LPL1-2/LA LPL2-2/LA LPL1-2/BC NAME PBamford ABaxter CSola HChernoff DATE 09/11/2007 09/13/2007 09/12/2007 9/27/2007 OFFICIAL RECORD COPY

Enclosure STEAM GENERATOR (SG) TUBE INSPECTION DISCUSSION POINTS PREPARED BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMERGEN ENERGY CO., LLC THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET NO. 50-289 The following discussion points have been prepared to facilitate the phone conference arranged with the licensee to discuss the results of the steam generator (SG) tube inspections to be conducted during the upcoming Three Mile Island, Unit 1 refueling outage. This phone call is scheduled to occur towards the end of the planned SG tube inspection interval, but before the unit completes the inspections and repairs.

The staff plans to document a brief 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, U-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 of 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).

(8)

Provide the schedule for SG-related activities during the remainder of the current outage.

(9)

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 if the loose parts were removed from the SG indications of tube damage associated with the loose parts the source or nature of the loose parts if known (10)

Discuss the results of any secondary side inspections.

(11)

Discuss any unexpected or unusual results.

(12)

Once Through Steam Generators:

If you have Babcock and Wilcox (B&W) welded plugs installed in the SGs, be prepared to discuss the actions taken in response to Framatomes notification of the effect of tubesheet hole dilation on the service life of B&W welded plugs.

Discuss any actions taken in response to the severed tube issue (NRC Information Notice (IN) 2002-02 and IN 2002-02, Supplement 1) during the outage. If actions are complete, please indicate so.

Three Mile Island Nuclear Station, Unit 1 cc:

Site Vice President - Three Mile Island Nuclear Station, Unit 1 AmerGen Energy Company, LLC P. O. Box 480 Middletown, PA 17057 Vice President - Operations, Mid-Atlantic AmerGen Energy Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Vice President - Licensing and Regulatory Affairs AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Regional Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Chairman Board of County Commissioners of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120 Chairman Board of Supervisors of Londonderry Township R.D. #1, Geyers Church Road Middletown, PA 17057 Senior Resident Inspector (TMI-1)

U.S. Nuclear Regulatory Commission P.O. Box 219 Middletown, PA 17057 Director - Licensing and Regulatory Affairs AmerGen Energy Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348 Director Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Plant Manager - Three Mile Island Nuclear Station, Unit 1 AmerGen Energy Company, LLC P. O. Box 480 Middletown, PA 17057 Regulatory Assurance Manager - Three Mile Island Nuclear Station, Unit 1 AmerGen Energy Company, LLC P.O. Box 480 Middletown, PA 17057 Ronald Bellamy, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Michael A. Schoppman Framatome ANP Suite 705 1911 North Ft. Myer Drive Rosslyn, VA 22209 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Eric Epstein TMI Alert 4100 Hillsdale Road Harrisburg, PA 17112 Correspondence Control Desk AmerGen Energy Company, LLC P.O. Box 160 Kennett Square, PA 19348

Three Mile Island Nuclear Station, Unit 1 cc:

Manager Licensing - Three Mile Island Nuclear Station, Unit 1 Exelon Generation Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348 Mr. Christopher M. Crane President and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Assistant General Counsel AmerGen Energy Company, LLC 200 Exelon Way Kennett Square, PA 19348 Associate General Counsel Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555