HNP-04-083, Day Special Report, Steam Generator Tube Plugging

Day Special Report, Steam Generator Tube Plugging

ML041560343
Person / Time
Site:	Harris
Issue date:	05/27/2004
From:	Mccabe B Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-04-083
Download: ML041560343 (4)

Text

CJ Progress Energy MAY 2 7 2004 Serial: HNP-04-083 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 15-DAY SPECIAL REPORT STEAM GENERATOR TUBE PLUGGING Ladies and Gentlemen:

In accordance with Technical Specification 4.4.5.5.a of the Harris Nuclear Plant (HNP),

Carolina Power and Light Company doing business as Progress Energy Carolinas, Inc.,

provides the attached 15-day special report, which reports the number of tubes plugged in each steam generator (SG) following the completion of a SG tube inservice inspection conducted during a mid-cycle outage in May 2004. In addition, this letter provides a correction to the one-year special report of steam generator tube inservice inspection results for refueling outage (RFO) 11 (May 2003) reported by letter HNP-04-076 dated May 7, 2004.

The complete results of the SG tube inservice inspection conducted during the mid-cycle outage in May 2004 will be submitted to the NRC within 12 months of completion as required by Technical Specification 4.4.5.5.b.

Attachment 1 provides the 15-day special report identifying the number of tubes plugged in each steam generator.

Attachment 2 provides the correction to the one-year special report of steam generator tube inservice inspection results for RFO- 11 (May 2003).

Please refer any question regarding this submittal to Mr. John Caves at (919) 362-3137.

Sincerely, B. C. McCabe Supervisor - LicensinglRegulatory Programs (Acting)

Harris Nuclear Plant BCM/jpy Progress Energy Carolinas, Inc.

Harris Nuclear Plant P.O.Box 165 New Hill, NC 27562

HNP-04-083 Page 2 Attachments:

1. 15-Day Special Report Identifying the Number of Tubes Plugged in Each Steam Generator

2. Correction to the one-year special report of steam generator tube inservice inspection results for RFO- 11 (May 2003)

C:

Mr. R. A. Musser, NRC Senior Resident Inspector Mr. C. P. Patel, NRC Project Manager Mr. L. A. Reyes, NRC Regional Administrator

Attachment 1 to SERIAL: HNP-04-083 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50400/LICENSE NO. NPF-63 15-DAY SPECIAL REPORT NUMBER OF TUBES PLUGGED IN EACH STEAM GENERATOR Technical Specification 4.4.5.5.a of the Harris Nuclear Plant (HNP) requires that within 15 days following the completion of each inservice inspection of steam generator (SG) tubes, the number of tubes plugged in each steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2 (10 CFR 50.4).

The first inservice inspection of the SGs following replacement in refueling outage (RFO) Number 10 (Fall 2001) was conducted during RFO-1 1 and completed on May 7, 2003. The second inservice inspection of the SGs was conducted during a mid-cycle outage and completed on May 14, 2004.

Number of Tubes Plugged Steam Generator A B C Current (May 2004 only) 0 0 3 Cummulative (through May 2004) 1 1 3 Identification of tubes plugged:

SG "A":

One tube plugged (pre-service): R106C85 SG "B":

One tube plugged (pre-service): R114C73 SG "C":

Three tubes plugged in May 2004: ROIC120, R02C121, and R03C120 Page Al-1 of 1

Attachment 2 to SERIAL: HNP-04-083 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 CORRECTION TO THE ONE-YEAR SPECIAL REPORT STEAM GENERATOR TUBE INSERVICE INSPECTION RESULTS FOR RFO-1 1 (MAY 2003)

Technical Specification 4.4.5.5.b of the Harris Nuclear Plant (HNP) requires the complete results of the steam generator (SG) tube inservice inspection shall be submitted in a special report within 12 months following completion of the inspection. The special report shall include:

1. Number and extent of tubes inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection, and

3. Identification of tubes plugged.

On May 7, 2004, HNP provided the required special report by letter HNP-04-076. Upon further review of the eddy current testing (ECT) data for refueling outage (RFO) number 11, it was discovered that one indication was missed on SG "C." Based upon review of the RFO-1 1 ECT (bobbin probe) data, the first sentence of Item 2 on Attachment 1, Page A1-2 of 2, of the special report should be deleted and replaced with the following:

2. Location and percent of wall-thickness penetration for each indication of an imperfection:

No recordable eddy current testing (ECT) indications with wall thickness penetration were identified from the results of this first inservice inspection. [Original Text]

One recordable eddy current testing (ECT) indication with approximately 37% wall-thickness penetration was identified from the results of this first inservice inspection. [Replaced Text]

Row 1 Column 120 indicated an NQI (non-quantifiable indication) located 0.64 inches above the Cold Leg top-of-tubesheet. Since this indication was missed at the time of the inspections, rotating coil examinations were not used to characterize the actual size and depth of this indication. Based on only the bobbin probe data that is available for this indication, the best estimate of wall-thickness penetration is approximately 37% with the primary frequency, 630 kHz. This depth estimate is derived from comparison to the American Society of Mechanical Engineers (ASME) calibration standard, and is not a qualified depth sizing technique. The missed indication data is as follows:

ROW COL VOLTS DEG IND CHN LOCN INCHI I BEGT I ENDT I PDIA PTYPE I CAL I LEG 1 120 0.43 126 l NQI 1 TSC +0.64 09H TEC .560 ZBACS 4 C 100% of the SG tubes were examined during RFO-1 1, and a re-review of the data did not identify any other missed indications that require reporting.

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