HNP-15-088, Submittal of 180-Day Steam Generator Tube Inspection Report

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Submittal of 180-Day Steam Generator Tube Inspection Report
ML15300A393
Person / Time
Site: Harris Duke energy icon.png
Issue date: 10/27/2015
From: O'Connor S
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-15-088
Download: ML15300A393 (6)


Text

Sean O'Connor

(_~DUKE General Manager, Nuclear Engineering ENERGYGD Harris Nuclear Plant 5413 Shearon Harris Road New Hill NC 27562-9300 919.362.2000 October 27, 2015 Serial: HNP-15-088 ATTN: Document Control Desk 10CFR 50.4 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ShearonHarris NuclearPowerPlant(HNP) Unit1 Docket No. 50-400/RenewedLicense No. NPF-63

Subject:

180-DaySteamGenerator Tube InspectionReport Ladies and Gentlemen:

In accordance with Harris Nuclear Plant (HNP) Technical Specifications (TS) Duke Energy Progrss,Inc.,submits the attached 180-Day SteamGenerator InspectionReport for HNP. This report has been prepared in accordance with TS6.9.1.7, Steam Generator Tube Inspection Report, and provides the complete results of HNP's RefuelingOutage No. 19.

This letter contains no new regulatory commitments.

Please address any comments or questions regarding this matter to John Caves at 919-362-2406 Sincerely, SeanO'Connor

Enclosure:

180-Day SteamGenerator Tube InspectionReport cc: Mr. J. D. Austin, NRG Sr. Resident Inspector, HNP Ms. M. Barillas, NRG ProjectManager, HNP Mr. V. M. Mccree, NRG RegionalAdministrator, Region II

HNP-15-088 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 Enclosure 180-Day Steam Generator Tube Inspection Report (5 pages including cover)

Harris Nuclear Plant HNP1 RFO119 Steam Generator Tube Inspection Report Pursuant to Harris technical specification 6.9.1.7 the following information is provided:

a. The scope of inspections performed on each SG For all three steam generators: Full length bobbin probe inspections of all tubes. Top of the tubesheet array probe inspections around the periphery extending five tubes into the bundle.
b. Degradation mechanisms found Degradation found included tube support plate (TSP) wear
c. Non-destructive examination techniques utilized for each degradation mechanism The Non-destructive examination techniques utilized bobbin coil and array probes for the detection of wear. The array probe was utilized to characterize wear indications.
d. Location, orientation (if linear), and measured sizes (if available) of service induced indications The complete listing for service-induced indications is attached.

Tubes with tube support plate wear SG 1A - 0 tubes /0 indications SG 1B - 1 tube /1 indication SG 1C -1 tube/1 indication Total - 2 tubes/2 indications No other indications of wear were reported

e. Number of tubes plugged during the inspection outage for each active degradation mechanism No tubes were plugged.
f. The total number and percentage of tubes plugged to date Steam Generator* A B C Total Plugs present prior to 5 4 3 12 RFO119 Plugs added in RFO119 0 0 0 0 Total Plugs 5 4 3 12

% Plugged 0.08 0.06 0.05 0.06

  • There are 6307 tubes per generator.
g. The results of condition monitoring, including the results of tube pulls and in-situ pressure testing.

The cumulative EFPY for RFO116 was 8.16, RFO117 was 9.59, RFO118 was 10.95 and RFO119 was 12.22.

As of RFO119, the Harris Unit 1 steam generators had operated 10.94 EFPY since the first in-service inspection after replacement. In total, the Harris Unit 1 steam generators had operated 12.22 EFPY since replacement.

Condition monitoring was met for the tube support plate degradation. All structural performance criteria were met with more than adequate margin projected through the next planned inspection at RFO122.

No degradation was detected in the plug visual or bowl cladding inspections.

No in-situ tests or tube pulls were performed.

FOSAR was performed at the top of tubesheet in all three steam generators. No new foreign objects were discovered. Two legacy parts were confirmed in the same location as the last inspection. They were evaluated and left in service.

Sludge lancing was performed in all three steam generators. A total of sixty -five (65) pounds of sludge was removed from all three steam generators. Twenty two (22) pounds of sludge was removed from the SG A. Eighteen (18) pounds of sludge was removed from SG B . Twenty-five (25) pounds of sludge was removed from SG C.

A steam drum, sludge collector and top of the tube bundle visual inspection was performed in SG B, no degradation was detected.

SG - B Attachment 1 - Service Induced Degradation Shearon Harris 1 RFO19 CQL 20150401 07/29/2015 13:30:39

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

l 58 131 .10 143 PCT 12 P5 05C .59 TEC TEH .560 NBAUC 5 H 13 WAR l l 58 131 .30 131 PCT 11 P33 05C .40 05C 05C .560 ZYAXP 54 C 7 WAR l

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

Tubes: 1 Records: 2 1 ST Max

SG - C Attachment 1 - Service Induced Degradation Shearon Harris 1 RFO19 CQL 20150401 07/29/2015 13:35:12

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

l 1 138 .28 133 PCT 17 P5 08H .39 09H TEH .560 NBAUL 7 H 8 WAR l l 1 138 .39 84 PCT 12 P18 08H .80 08H 08H .560 ZYAXP 12 H 7 WAR l

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

Tubes: 1 Records: 2 1 ST Max

Sean O'Connor

(_~DUKE General Manager, Nuclear Engineering ENERGYGD Harris Nuclear Plant 5413 Shearon Harris Road New Hill NC 27562-9300 919.362.2000 October 27, 2015 Serial: HNP-15-088 ATTN: Document Control Desk 10CFR 50.4 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ShearonHarris NuclearPowerPlant(HNP) Unit1 Docket No. 50-400/RenewedLicense No. NPF-63

Subject:

180-DaySteamGenerator Tube InspectionReport Ladies and Gentlemen:

In accordance with Harris Nuclear Plant (HNP) Technical Specifications (TS) Duke Energy Progrss,Inc.,submits the attached 180-Day SteamGenerator InspectionReport for HNP. This report has been prepared in accordance with TS6.9.1.7, Steam Generator Tube Inspection Report, and provides the complete results of HNP's RefuelingOutage No. 19.

This letter contains no new regulatory commitments.

Please address any comments or questions regarding this matter to John Caves at 919-362-2406 Sincerely, SeanO'Connor

Enclosure:

180-Day SteamGenerator Tube InspectionReport cc: Mr. J. D. Austin, NRG Sr. Resident Inspector, HNP Ms. M. Barillas, NRG ProjectManager, HNP Mr. V. M. Mccree, NRG RegionalAdministrator, Region II

HNP-15-088 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 Enclosure 180-Day Steam Generator Tube Inspection Report (5 pages including cover)

Harris Nuclear Plant HNP1 RFO119 Steam Generator Tube Inspection Report Pursuant to Harris technical specification 6.9.1.7 the following information is provided:

a. The scope of inspections performed on each SG For all three steam generators: Full length bobbin probe inspections of all tubes. Top of the tubesheet array probe inspections around the periphery extending five tubes into the bundle.
b. Degradation mechanisms found Degradation found included tube support plate (TSP) wear
c. Non-destructive examination techniques utilized for each degradation mechanism The Non-destructive examination techniques utilized bobbin coil and array probes for the detection of wear. The array probe was utilized to characterize wear indications.
d. Location, orientation (if linear), and measured sizes (if available) of service induced indications The complete listing for service-induced indications is attached.

Tubes with tube support plate wear SG 1A - 0 tubes /0 indications SG 1B - 1 tube /1 indication SG 1C -1 tube/1 indication Total - 2 tubes/2 indications No other indications of wear were reported

e. Number of tubes plugged during the inspection outage for each active degradation mechanism No tubes were plugged.
f. The total number and percentage of tubes plugged to date Steam Generator* A B C Total Plugs present prior to 5 4 3 12 RFO119 Plugs added in RFO119 0 0 0 0 Total Plugs 5 4 3 12

% Plugged 0.08 0.06 0.05 0.06

  • There are 6307 tubes per generator.
g. The results of condition monitoring, including the results of tube pulls and in-situ pressure testing.

The cumulative EFPY for RFO116 was 8.16, RFO117 was 9.59, RFO118 was 10.95 and RFO119 was 12.22.

As of RFO119, the Harris Unit 1 steam generators had operated 10.94 EFPY since the first in-service inspection after replacement. In total, the Harris Unit 1 steam generators had operated 12.22 EFPY since replacement.

Condition monitoring was met for the tube support plate degradation. All structural performance criteria were met with more than adequate margin projected through the next planned inspection at RFO122.

No degradation was detected in the plug visual or bowl cladding inspections.

No in-situ tests or tube pulls were performed.

FOSAR was performed at the top of tubesheet in all three steam generators. No new foreign objects were discovered. Two legacy parts were confirmed in the same location as the last inspection. They were evaluated and left in service.

Sludge lancing was performed in all three steam generators. A total of sixty -five (65) pounds of sludge was removed from all three steam generators. Twenty two (22) pounds of sludge was removed from the SG A. Eighteen (18) pounds of sludge was removed from SG B . Twenty-five (25) pounds of sludge was removed from SG C.

A steam drum, sludge collector and top of the tube bundle visual inspection was performed in SG B, no degradation was detected.

SG - B Attachment 1 - Service Induced Degradation Shearon Harris 1 RFO19 CQL 20150401 07/29/2015 13:30:39

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

l 58 131 .10 143 PCT 12 P5 05C .59 TEC TEH .560 NBAUC 5 H 13 WAR l l 58 131 .30 131 PCT 11 P33 05C .40 05C 05C .560 ZYAXP 54 C 7 WAR l

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

Tubes: 1 Records: 2 1 ST Max

SG - C Attachment 1 - Service Induced Degradation Shearon Harris 1 RFO19 CQL 20150401 07/29/2015 13:35:12

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

l 1 138 .28 133 PCT 17 P5 08H .39 09H TEH .560 NBAUL 7 H 8 WAR l l 1 138 .39 84 PCT 12 P18 08H .80 08H 08H .560 ZYAXP 12 H 7 WAR l

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l

+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+

Tubes: 1 Records: 2 1 ST Max