Text

B1R16 Lsi Outage Report, Bolts, Pumps, and Valves Outage Summary
	ML100050360
Person / Time
Site:	Byron
Issue date:	12/17/2009
From:	; Exelon Generation Co, Exelon Nuclear
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML10050043	List: ML100050360;
References
	BYRON 2010-0001
	Download: ML100050360 (31)
	v • d • e

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1

12117/2009 Byron Station Unit 1 B1R16 lSI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM:

Reactor Coolant System (RC)

B-G-1 B6.220 1RC80020/FLG SURF Valve Flange Surface OBS16-220 Valve disassembled under WO#01169301.

B-M-2 B12.50 1RC80020/lNT SURF Valve Body Interior VT-1 VT-3 VT-3 NRI RI NRI OBS16-222 Valve disassembled under WO#01169301. Complete examination per Table 2500-1 Category B-M-2 Note (2).

10 surface impression from disk guide. Ref. IR#0971222, RIR# B1R16-2009-344.

B-G-1 B6.230 1RC80020/NBW 1-24 Valve Nuts, Bushings, and Washers OBS16-221 Valve disassembled under WO#01169301.

1 VT-1 VT-1 NRI NRt

12117/2009 Exelon_

Byron Station Unit 1 B1 R16 lSI Outage Report Bolts, Pumps, and Valves Outage Summary SYSTEM:

Safety Injection System (SI)

B-G-2 B7.70 1S18948B/BLT 1-18 Valve Studs, Nuts, Bushings, and Washers OBS16-218 Valve dissasembled under WO#01267291.

B-M-2 B12.50 1S18948B/INT SURF Valve Body Interior OBS16-219 Valve dissasembled under WO#01267291. Partial examination per Table 2500-1 Category B-M-2 Note (2).

2 VT-1 VT-3 NRI NRI

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12117/2009 Exelon_

Byron Station Unit 1 B1 R16 lSI Outage Report Weld I Component Outage Summary (Preservice Inspections)

SYSTEM:

Reactor Coolant System (RC)

R-A R1.11 1RC30AC-1.5/W-01.01 1RC30AC-1.5 13R-02 B9.4O 100 SURF PT NRI Valve - Reducer 13T-01 VISL VT-2 NRI 13T-02 Baseline exam of new socket weld W-1. WO#01267305.

R-A R1.11 1RC30AD-1.5/W-01.01 1RC30AD-1.5 13R-02 B9.40 100 SURF PT NRI Valve - Reducer 13T-01 VISL VT-2 NRI 13T-02 Baseline exam of new socket weld W-1. WO#01267306.

12117/2009

-xelon..

Byron Station Unit 1 B1 R16 lSI Outage Report Weld I Component Outage Summary (Preservice Inspections)

SYSTEM:

Safety Injection System (SI)

R-A Ri.ii 1SIOBJC-i.5/W-4i.0i 1SIOBJC-1.5 13R-02 B9.40 100 SURF PT NRI Pipe - Elbow 13T-01 VISL VT-2 NRt 13T-02 Baseline exam of new socket weld W-4. WO#01267305.

R-A R1.11 1SI08JC-1.5/W-42.01 1SIOBJC-1.5 13R-02 B9.40 100 SURF PT NRI Elbow - Pipe 13T-01 VISL VT-2 NRI 13T-02 Baseline exam of new socket weld W-3. WO#01267305.

R-A RU1 1SIOBJC-i.5/W-43.01 iSIOBJC-1.5 13R-02 B9.40 100 SURF PT NRI Pipe - Valve 13T-01 VISL VT-2 NRI 13T-02 Baseline exam of new socket weld W-4.

267305.

R-A R1.1i 1SIOBJD-1.5/W-27.01 1SIOBJD-i.5 13R-02 B9.40 100 SURF PT NRI Pipe - Coupling 13T-01 VISL VT*2 NRI 13T-02 Baseline exam of new socket weld W-5. WO#01267306.

R-A R1.1i 1SI08JD-1.5/W-28.01 1SI08JD-1.5 13R-02 B9.40 100 SURF PT NRI Coupling - Pipe 13T-01 VISL VT-2 NRI 13T-02 Baseline exam of new socket weld W-3. WO#01267306.

R-A RU1 1SIOBJD-1.5/W-29.01 1SI08JD-1.5 13R-02 B9.40 100 SURF PT NRI Pipe - Valve 13T-01 VISL VT-2 NRI 13T-02 Baseline exam of new socket weld W-2. WO#01267306.

2 12117/2009

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12117/2009 Exelon..

Byron Station Unit 1 B1R16 lSI Outage Report Detailed Inservice Inspection Bolts, Pumps, and Valves Listing (PSI)

SYSTEM: Reactor Coolant System (RY)

B-G-2 B7.50 1RY03BA-6/FLG 1-12 Piping Flange Bolting Baseline exam for 1RY8010A replacement. WO#01120408.

B-G-2 B7.50 1RY03BB-6/FLG 1-12 Piping Flange Bolting Baseline exam for 1RY8010B replacement. WO#0113633.

1 PFB-RY PFB-RY VT-1 VT-1 NRt NRt 12i1712009

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12117/2009 Pressure Test Outage Summary SYSTEM:

Reactor Coolant System (RC)

Exelon..

Byron Station Unit 1 B1 R16 lSI Outage Report NA NA 1-AC-H Includes area under vessel in incore shaft.

VT-2 NAI 12117/2009

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12117/2009 SYSTEM:

Exelcn-Byron Station Unit 1 B1R16 lSI Outage Report Component Support Outage Summary Containment Spray System (CS)

F-A F1.40 1CS-01-PAlL1 1CS-01-PA VT-3 NRI CS PUMP 1A LUG 1 Concrete is painted F-A F1.40 1CS-01-PAlL2 1CS-01-PA VT-3 NRI CS PUMP 1A LUG 2 Concrete is F-A F1.40 1CS-01-PAlL3 1CS-01-PA VT-3 NRI CS PUMP 1A LUG 3 Concrete is painted

12117/2009 SYSTEM:

Exelon_

Byron Station Unit 1 B1R16 lSI Outage Report Component Support Outage Summary Safety Injection System (SI) 1SI04A-12 F-A F1.20 1SI04A-1211 SI18027X SEISMIC All welds painted. 10 - Minor surface rust 1 no degradation on stitch weld, bottom southwest side item# 6.

2 VT-3 NRI

12117/2009 Exelonu.

Byron Station Unit 1 B1 R16 lSI Outage Report Component Support Outage Summary SYSTEM:

Essential Service Water System (SX)

F-A F1.20 1SX06CA-14/1 SX06005X 1SX06CA-14 VT-3 NRI SEISMIC None F-A F1.20 1SX06CA-14/1 SX06006X 1SX06CA-14 VT-3 NRI SEISMIC None F-A F1.20 1SX06EA-1 0/1 SX06015X 1SX06EA-10 VT-3 NRI SEISMIC None 3

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12117/2009 Snubber Outage Summary (Page 1 of 7)

SYSTEM:

Chemical &Volume Control System (CV)

Byron Station Unit 1 Byron Station Outage B1R16 F-A F1.20 1CV05CB-6/1 CV08013S 1CV05CB-6 VT-3 NRI SNUBBER SR F-A F1.20 1CV05CB-6/1 CV08021 S 1CV05CB-6 VT-3 NRI SNUBBER SR NA NA 1CV15AB-3/4/1 CV28002S 1CV15AB-3/4 VT-3 NRI SNUBBER SR FT PASS NA NA 1CV15AB-3/4/1 CV28003S 1CV15AB-3/4 VT-3 NRI SNUBBER SR FT PASS NA NA 1CV15AC-3/4/1 CV29003S 1CV15AC-314 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 1CV45B-211 RY06124S 1CV45B-2 VT-3 NRI SNUBBER SR F-A F1.10 1CVA3B-211 CV09005S 1CVA3B-2 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 1CVA7AA-211 CV25009S 1CVA7AA-2 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 1CVA7AA-211 CV25016S 1CVA7AA-2 VT-3 NRI SNUBBER SR FT PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 1

12117/2009 Snubber Outage Summary (Page 2 of 7)

SYSTEM:

Main Steam System (MS)

Exelon..

Byron Station Unit 1 Byron Station Outage B1 R16 N/A SNUB 1MS01AB-32.75/1 MS06007-S1 1MS01AB-32.75 SNUBBER N/A SNUB 1MS01AB-32.75/1 MS06007-S2 1MS01AB-32.75 SNUBBER Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 2

DBL SR DBL SR VT-3 FT VT-3 FT NRI PASS NRI PASS

12117/2009 Snubber Outage Summary (Page 3 of 7)

SYSTEM:

Reactor Coolant System (RC)

Exelon-Byron Station Unit 1 Byron Station Outage B1R16 F-A F1AO 1RCOl BA-1A11 RC06S lRC01BA-1A VT-3 NRI SNUBBER SR F-A F1AO 1RCOl BA-l All RC07S lRC01BA-1A VT-3 NRI SNUBBER SR F-A F1AO 1RCOl BB-l Bll RC08S lRC01BB-1B VT-3 NRI SNUBBER SR F-A F1AO 1RCOl BB-l B/l RC09S lRC01BB-1B VT-3 NRI SNUBBER SR F-A F1AO 1RCOl BC-lC/l RCl OS 1RCOlBC-1C VT-3 NRI SNUBBER SR FT PASS F-A F1AO 1RCOl BC-lC/l RCll S 1RCOlBC-1C VT-3 NRI SNUBBER SR F-A F1AO 1RC01BD-1D/l RC12S lRC01BD-1D VT-3 NRI SNUBBER SR F-A F1AO 1RCOl BD-l 011 RC13S lRC01BD-1D VT-3 NRI SNUBBER SR NA NA 1RC08AB-3/4/1 RC17025S 1RC08AB-314 VT-3 NRI SNUBBER SR FT PASS NA NA 1RC08AD-3/4/1 RC19023S 1RC08AD-3/4 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 1RC14AB-211 CV15040S 1RC14AB-2 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 1RC14AC-211 CV09066S 1RC14AC-2 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 1RC14AD-211 CV25034S 1RC14AD-2 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 1RC16AA-211 CV12006S 1RC16AA-2 VT-3 NRI SNUBBER SR FT PASS NA NA 1RC20AA-3/4/1 RC1601 OS 1RC20AA-3/4 VT-3 NRI SNUBBER SR NA NA 1RC20AB-3/4/1 RC17012S 1RC20AB-3/4 VT-3 NRI SNUBBER SR FT PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF*2500 tables 3

12117/2009 Snubber Outage Summary (Page 4 of 7)

SYSTEM:

Reactor Coolant System (RC)

Exelon.

Byron Station Unit 1 Byron Station Outage B1R16 NA NA 1RC20AD-3/411 RC19004S 1RC2OAD-3/4 VT-3 NRI SNUBBER SR F-A F1.10 1RC21 AC-8/1 RC03006S 1RC21AC-8 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 1RC22AA-1.5/1 RC16016S 1RC22AA-1.5 VT-3 NRI SNUBBER SR F-A F1.10 1RC22AB-1.5/1 RC17003S 1RC22AB-1.5 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 1RC24AB-4/1 RY06032S 1RC24AB-4 VT-3 NRI SNUBBER SR FT PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 4

12117/2009 Snubber Outage Summary (Page 5 of 7)

SYSTEM:

Reactor Coolant System (RY)

Exelon-Byron Station Unit 1 Byron Station Outage B1R16 F-A F1.10 1RY01 AA-4/1 RY06059S 1RY01AA-4 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 1RY01AA-4/1 RY06121 S 1RY01AA-4 VT-3 NRI SNUBBER SR F-A F1.10 1RY06A-3/1 RY09012S 1RY06A-3 VT-3 NRI SNUBBER SR FT PASS F-A F1.10 1RY18A-211 RY06097S 1RY18A-2 VT-3 NRt SNUBBER SR FT PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 5

12117/2009 Snubber Outage Summary (Page 6 of 7)

SYSTEM:

Steam Generator Slowdown System (SO)

Byron Station Unit 1 Byron Station Outage B1 R16 NA NA 1SOOl CE-211 S022015S SNUBBER 1S001CE-2 SR VT-3 FT NRI PASS Note: Section XI Category numbers N/A-ed are exempt from IWF-1220 and IWF-2500 tables 6

12/17/2009 Snubber Outage Summary (Page 7 of 7)

SYSTEM:

Safety Injection System (SI)

Exelon-

~

~********** ~. __*

h Byron Station Unit 1 Byron Station Outage B1R16 F-A F1.10 1SI05DA-6/1 SI01 029S SNUBBER 1S105DA-6 SR VT-3 FT NRI PASS Note: Section XI Category numbers N/A*ed are exempt from IWF*1220 and IWF*2500 tables 7

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(This report is used to verify that the periodic I

requirements of Tables IWx-2412-1 will be met by the interval schedule.)

I

of ITotal I

l.tem No.

Comp Selected Min BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL I (The percentage requirements of Tables IWx-ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were applied to each Item only when practical.)

Exams Completed I

I

% Exams Completed Per 1 Max Min Per 2 Max Per 3

% Selected Period 1 I Period 2 I Period 3 Category B-A Non-Deferred Exams 81.30 1

1 0

0 1

1 0

100.00%

0.00%

81.40 1

1 0

0 1

1 0

100.00%

0.00%

Totals:

2 2

0 0

1 1

0 1

0 100.00%

0.00%

Category B-A Deferred Exams 81.11 3

3 N/A N/A N/A N/A 0

100.00%

0.00%

81.21 2

2 N/A N/A N/A N/A 0

100.00%

0.00%

Totals:

5 5

N/A N/A N1A N1A 0

100.00%

0.00%

Category B-B Non-Deferred Exams 82.11 2

2 0

0 1

1 0

100.00%

0.00%

82.12 2

2 0

0 1

1 0

100.00%

0.00%

82.40 4

1 0

1 1

1 0

25.00%

100.00%

Totals:

8 5

1 1

2 2

0 2

0 62.50%

20.00%

1.

(82.40) Per Examination Category 8-8, Note 1, examinations may be limited to one vessel among a group of vessels performing a similar function.

Category B-D Non-Deferred Exams 83.110 6

6 1

5 3

-2 0

-1 0

100.00%

83.33%

83.120 6

6 1

5 3

-2 0

-1 0

100.00%

83.33%

83.140 8

8 2

0 4

4 0

6 0

100.00%

0.00%

Totals:

20 20 4

10 10 0

0 5

0 100.00%

50.00%

1.

(83.120 & 83.140) Per 10 CFR 50.55a(b)(2)(xxi)(A), Table IW8-2500-1 examination requirements, the provisions of Table IW8-2500-1, Examination Category 8-0, Item Numbers 83.120 and 83.140 in the 1998 Edition must be applied when using the 1999 Addenda through the latest edition and addenda, and requires that a visual examination with enhanced magnification may be performed on the inside radius section in place of an ultrasonic examination.

Category B-D Deferred Exams 83.90 8

8 N/A N/A N/A N/A 0

100.00%

0.00%

83.100 8

8 N/A N/A N/A N/A 0

100.00%

0.00%

Totals:

16 16 N1A N1A N1A N1A 0

100.00%

0.00%

Section 3.0 Page 1 of 8

BYRON STATION UNIT 1 AND UNIT COMMON* 3RD INTERVAL ASME SECTION XI EXAMINATION STATUS REPORT

Exams Completed Per 1 Max Min Per 2 Max Per 3

% Selected 1.

(B3.90 & B3.1 00) Per Exam ination Category B-D, Note 5, for PWR's in the second and successive inspection intervals, these examinations may be deferred to the end of the interval provided no repair/replacement activities have been performed on the examination item, and no flaws or relevant conditions requiring successive inspections in accordance with IWB-2420(b) are contained in the examination item.

Category B*G*1 Deferred Exams B6.10 3

3 N/A 1

N/A N/A 0

N/A 0

100.00%

33.33%

B6.20 3

3 N/A 1

N/A N/A 0

N/A 0

100.00%

33.33%

B6.40 1

1 N/A 0

N/A N/A 0

N/A 0

100.00%

0.00%

B6.50 3

3 N/A 1

N/A N/A 0

N/A 0

100.00%

33.33%

B6.90 8

8 N/A 0

N/A N/A 0

N/A 0

100.00%

0.00%

B6.100 8

8 N/A 8

N/A N/A 0

N/A 0

100.00%

B6.110 8

8 N/A 0

N/A N/A 0

N/A 0

100.00%

0.00%

B6.170 1

1 N/A 0

N/A N/A 0

N/A 0

100.00%

0.00%

B6.180 4

1 N/A 0

N/A N/A 0

N/A 0

25.00%

0.00%

B6.190 4

0 N/A 0

N/A N/A 0

N/A 0

0.00%

B6.200 4

0 N/A 0

N/A N/A 0

N/A 0

0.00%

B6.210 8

2 N/A 0

N/A N/A 0

N/A 0

25.00%

0.00%

B6.220 8

1 N/A 1

N/A N/A 0

N/A 0

12.50%

100.00%

0.00%

B6.230 8

1 N/A 1

N/A N/A 0

N/A 0

12.50%

100.00%

0.00%

Totals:

71 40 N/A 13 N/A N/A 0

N/A 0

53.52%

32.50%

1.

(B6.10 & B6.20 & B6.50) Single components representing one third of the 54 Reactor Vessel Closure Head Nuts, Closure Studs, and Closure Washers, Bushings.

2.

(B6.40) A single component representing all of the 54 Reactor Vessel Threads in Flange to be examined.

3.

(B6.90 & B6.100 & B6.110) Eight components are tracked in the database, each representing all of the Bolts and associated Nuts, Bushings, and Washers and Flange Surfaces on one of the eight Steam Generator Manways. Each of the eight entries represents 20 bolts and associated parts for an individual manway.

4.

(B6.170) A single component represents the five sets of CETC column nuts.

5.

(B6.180) Four components are tracked in the database, each representing one of the 24 Bolts on one of the four Reactor Coolant Pumps (96 total) as reported in the lSI Program Plan. The volumetric examination of these components is limited to only one of the pumps per Examination Category B-G-1, Note 3 and Examination Category B-L-2, Note 1. Examination is required only once per inspection interval.

6.

(B6.190 & B6.200) Four components are tracked in the database, each representing all 24 associated Flange Surfaces and Nuts, Bushings, and Washers for one of the four Reactor Coolant Pumps (96 total) as reported in the lSI Program Plan. The visual examination of these components is limited to only one of the pumps per Examination Category B-G-1, Note 3 and Examination Category B-L-2, Note 1. Also, per Examination Category B-G-1, Note 4 and Examination Category B-L-2, Note 2, examination is required only when a pump is disassembled for maintenance, repair, or volumetric examination or bolting is removed.

Examination is required only once per inspection interval.

Section 3.0 Page 2 of 8

BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL ASME SECTION XI EXAMINATION STATUS REPORT

Exams Completed Per 1 Max Min Per 2 Max Per 3

% Selected 7.

(B6.210) Eight components are tracked in the database, each representing all of the Bolts and associated Nuts, Bushings, and Washers and Flange Surfaces on one of the eight Reactor Coolant Valves as reported in the lSI Program Plan. The volumetric examination of these components is limited to only one of the valves per Examination Category B-G-1, Note 3 and Examination Category B-M-2, Note 3. Examination is required only once per inspection interval.

8.

(B6.220 & B6.230) Eight components are tracked in the database, each representing all of the Bolts and associated Nuts, Bushings, and Washers and Flange Surfaces on one of the eight Reactor Coolant Valves as reported in the lSI Program Plan. The visual examination of these components is limited to only one of the valves per Examination Category B-G-1, Note 3 and Examination Category B-M-2, Note 3. Also, per Examination Category B-G-1, Note 4 and Examination Category B-M-2, Note 2, examination is required only when a valve is disassembled for maintenance, repair, or volumetric examination or bolting is removed.

Examination is required only once per inspection interval.

Category B-G-2 Deferred Exams B"1.10 2

2 N/A 0

N/A N/A 0

N/A 0

100.00%

0.00%

B7.20 1

0 N/A 0

N/A N/A 0

N/A 0

0.00%

B7.50 20 3

N/A 2

N/A N/A 0

N/A 0

15.00%

66.67%

B7.60 4

0 N/A 0

N/A N/A 0

N/A 0

0.00%

B7.70 26 2

N/A 2

N/A N/A 0

N/A 0

3.85%

100.00%

0.00%

66.67%

0.00%

100.00%

0.00%

66.67%

0.00%

100.00%

57.14%

Totals:

53 7

N/A 4

N/A N/A 0

N/A 0

13.21%

57.14%

1.

(B7.10) Two components representing the CETC and RVLlS Clamp Bolts and associated Nuts as reported in the lSI Program Plan.

2.

(B7.20) A single component is scheduled in the first inspection period, representing all 16 Pressurizer Manway Bolts and associated Nuts as reported in the lSI Program Plan.

3.

(B7.50) Per Examination Category B-G-2, Note 3, examination is required only when a bolted connection is disassembled or bolting is removed. Also, per Examination Category B-G-2, Note 3, examinations are limited to at least one bolted connection within each group of bolted connections that are similar in design, size, function, and service. Examination is required only once per inspection interval within each bolted connection group.

4.

(B7.60) Four components are tracked in the database, each representing all 36 Bolts and associated Nuts for one of the four Reactor Coolant Pumps (144 total) as reported in the lSI Program Plan. Per Examination Category B-G-2, Note 2 and Examination Category B-L-2, Note 2, examination is required only when a pump is disassembled for maintenance, repair, or volumetric examination or bolting is removed. Also, per Examination Category B-G-2, Note 2 and Examination Category B-L-2, Note 1, examinations are limited to at least one pump within each group of pump that are of the same size, design, manufacturing method, and function. Examination is required only once per inspection interval within each valve group.

5.

(B7.70) Per Examination Category B-G-2, Note 2 and Examination Category B-M-2, Note 2, examination is required only when a valve is disassembled for maintenance, repair, or volumetric examination or bolting is removed. Also, per Examination Category B-G-2, Note 2 and Examination Category B-M-2, Note 3, examinations are limited to at least one valve within each group of valves that are of the same size, design, manufacturing method, and function. Examination is required only once per inspection interval within each valve group.

Section 3.0 Page 3 of 8

BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL ASME SECTION XI EXAMINATION STATUS REPORT

Exams Completed Per 1 Max Min Per 2 Max Per 3

% Selected Category B-K Non-Deferred Exams 810.10 2

1 0

0 1

1 0

50.00%

0.00%

810.20 7

3 1

1 1

1 0

42.86%

33.33%

Totals:

9 4

1 1

2 2

0 2

0 44.44%

25.00%

1.

(810.10) Per Examination Category 8-K, Note 4, for multiple vessels of similar design, function and service, only one welded attachment of only one of the multiple vessels shall be selected for examination. Conservatively, a welded attachment of each type of welded attachment of one of multiple vessels will be examined.

2.

(810.20 & 810.30) Per Examination Category 8-K, Note 5, for piping, pumps, and valves, a sample of 10% of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined. This requirement is conservatively interpreted to mean that 10% of the total Class 1 welded attachments shall be examined. The interpretation is consistent with the previous NRC condition on the use of Code Case N-509.

Category B-L-2 Deferred Exams

of Total

Exams Completed

% Exams Completed Item No.

Comp Selected min Per 1 max min Per 2 max Per 3

% Selected Period 1 Period 2 Period 3 812.20 4

0 N/A 0

N/A N/A 0

N/A 0

0.00%

Totals:

4 0

N/A 0

N/A N/A 0

N/A 0

0.00%

1.

(812.20) The examination of pump casings is limited to only one of the pumps performing similar functions in the system per Examination Category 8-L-2, Note

1. Also, per Examination Category 8-L-2, Note 2, examination is required only when a pump is disassembled for maintenance, repair, or volumetric examination. Examination is required only once per inspection interval.

Category B-M-2 Deferred Exams

of Total

Exams Completed

% Exams Completed Item No.

Comp Selected min Per 1 max min Per 2 max Per 3

% Selected Period 1 Period 2 Period 3 812.50 37 4

N/A 4

N/A N/A 0

N/A 0

10.81%

100.00%

Totals:

37 4

N/A 4

N/A N/A 0

N/A 0

10.81%

100.00%

1.

(812.50) Per Examination Category 8-M-2, Note 2, examination is required only when a valve is disassembled for maintenance, repair, or volumetric examination. Also, per Examination Category 8-M-2, Note 3, examinations are limited to at least one valve within each group of valves that are of the same size, design, manufacturing method, and function. Examination is required only once per inspection interval within each valve group.

Category B-N-1 Non-Deferred Exams 813.10 1

1 0

1 1

1 0

100.00%

Totals:

1 1

0 1

1 1

0 1

0 100.00%

100.00%

1.

(813.10) "% Completed" exceeds 100% since the vessel interior is selected for examination once each period (three times during the interval).

Section 3.0 Page 4 of 8

BYRON STATION UNIT 1 AND UNIT COMMON* 3RD INTERVAL ASME SECTION XI EXAMINATION STATUS REPORT

Exams Completed Per 1 Max Min Per 2 Max Per 3

% Selected Category B*N*2 Deferred Exams 813.50 1

1 N/A 0

N/A N/A 0

N/A 0

100.00%

0.00%

813.60 1

1 N/A 0

N/A N/A 0

N/A 0

100.00%

0.00%

Totals:

2 2

NJA 0

NJA NJA 0

NJA 0

100.00%

0.00%

Category B-N-3 Deferred Exams 813.70 1

1 N/A 0

N/A N/A 0

N/A 0

100.00%

0.00%

Totals:

1 1

NJA 0

NJA NJA 0

NJA 0

100.00%

0.00%

Category B*O Deferred Exams 8'14.10 5

5 N/A 0

N/A N/A 0

N/A 0

100.00%

0.00%

Totals:

5 5

NJA 0

NJA NJA 0

NJA 0

100.00%

0.00%

1.

(814.10) 10% of the 45 CRD Housings (as reported in the lSI Program Plan) are required to be examined each interval per this Item Number.

components represent that 10% population.

0.00%

These 5 Category B-P Non-Deferred Exams 815.10 1

1 N/A 3

N/A N/A 0

N/A 0

100.00%

Totals:

1 1

NJA 3

NJA NJA 0

N/A 0

100.00%

1.

(815.10) "% Completed" exceeds 100% since Class 1 pressure tests are performed each refueling outage.

2.

(815.10) Five components representing the five systems in Class 1 as reported in the lSI Program Plan.

300.00%

3000.00%

300.00%

Category C-A Non-Deferred Exams C1.10 6

1 0

1 1

1 0

16.67%

0.00%

C*I.20 6

1 0

1 1

1 0

16.67%

0.00%

C1.30 4

1 0

0 1

1 0

25.00%

100.00%

Totals:

16 3

1 1

0 1

0 18.75%

33.33%

1.

(C1.10, C1.20, & C1.30) Per Examination Category C-A, Note 3, in the case of mUltiple vessels of similar design, size, and service, the required examinations may be limited to one vessel or distributed among the vessels.

2.

(C1.10 & C1.20) Two welds per item for the Residual Hear Removal Heat Exchanger are exempted from examination with the adoption of ASME Code Case N-l06. The remaining welds in the items are for the four steam generators and are selected for examination under #1 above.

Section 3.0 Page 5 of 8

(This report is used to verify that the periodic I

requirements of Tables IWx-2412-1 will be met by the interval schedule.)

1

of I Total I

Item No.

Comp Selected Min BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL I (The percentage requirements of Tables tWx*

ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were applied to each Item onlv when praclical.)

Exams Completed I

I

% Exams Completed Per 1 Max Min Per 2 Max Per 3

% Selected Period 1 I Period 2 I Period 3 Category CoB Non-Deferred Exams C2.21 12 1

0 0

1 1

0 1

0 8.33%

0.00%

C2.22 4

1 0

1 1

1 0

12.50%

100.00%

Totals:

16 2

0 1

1 1

0 1

0 12.50%

50.00%

1.

(C2.21 & C2.22) Per Examination Category CoB, Note 4, in the case of multiple vessels of similar design, size, and service, the required examinations may be limited to one vessel or distributed among the vessels.

2.

(C2.21) The capped Auxiliary Feedwater nozzle is exempted from examination selection per Examination Category CoB, Note 1 and Note 2.

3.

(C2.21) Two welds per item for the Residual Hear Removal Heat Exchanger are exempted from examination with the adoption of ASME Code Case N-706.

The remaining welds in the item are for the four steam generators and are selected for examination under #1 above.

Category C-C Non-Deferred Exams C3.10 2

1 0

1 1

1 0

50.00%

100.00%

C3.20 61 7

2 2

3 2

0 3

0 11.48%

28.57%

C3.30 20 2

0 0

1 1

0 1

0 10.00%

0.00%

Totals:

83 10 2

3 5

2 0

4 0

12.05%

30.00%

1.

(C3.10) Per Examination Category C-C, Note 4, for multiple vessels of similar design, function, and service, only one welded attachment of only one of the multiple vessels shall be selected for examination. Conservatively, a welded attachment of each type of welded attachment of one of multiple vessels will be examined.

2.

(C3.20 &C3.30) Per Examination Category C-C, Note 5, for piping, pumps, and valves, a sample of 10% of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined. This requirement is conservatively interpreted to mean that 10% of the total Class 2 welded attachments shall be examined. The interpretation is consistent with the previous NRC condition on the use of Code Case N-509.

Category C-H Non-Deferred Exams Ci7.10 29 29 N/A 29 N/A N/A 0

N/A 0

100.00%

Totals:

29 29 N/A 29 N1A N1A 0

N1A 0

100.00%

1.

(C7.10) "% Completed" exceeds 100% since Class 2 pressure tests are performed each inspection period.

2.

(C7.10) Twenty-nine components representing the twenty-nine systems in Class 2 as reported in the lSI Program Plan.

100.00%

1000.00%

100.00%

Category D-A Non-Deferred Exams 01.10 28 14 3

7 7

0 0

3 0

50.00%

01.20 120 14 3

3 7

4 0

7 0

11.67%

21.43%

01.30 12 2

0 0

1 1

0 1

0 16.67%

0.00%

Totals:

160 30 5

10 15 5

0 12 0

18.75%

33.33%

Section 3.0 Page 6 of 8

(ThiS report is used to verify that the periodic I

requirements of Tables IWx-2412-1 will be met by the interval schedule.)

BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL I (The percentage requirements of Tables IWx-ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were applied to each Item only when practical.)

I

of I Total I

Item No.

Comp Selected Min

Exams Completed I

I

% Exams Completed Per 1 Max Min Per 2 Max Per 3

% Selected Period 1 I Period 2 I Period 3 1..

(01.10& 01.20 & 01.30) Unit 0 (Common) components are scheduled with and included in the Unit 1 counts.

2.

(01.10) Per Examination Category, Note 3, for multiple vessels of similar design, function, and service, the welded attachments of only one of the multiple vessels shall be selected for examination. Conservatively, an integral attachment of each type of welded attachment of one of multiple vessels will be examined.

3.

(01.20) Per Examination Category, Note 3, for welded attachments of piping, pumps, and valves, a 10% sample shall be selected for examination. This requirement is conservatively interpreted to mean that 10% of the total Class 3 welded attachments shall be examined. The interpretation is consistent with the previous NRC condition on the use of Code Case N-509.

Category D-B Non-Deferred Exams 02.10 20 20 N/A 20 N/A N/A 0

N/A 0

100.00%

Totals:

20 20 N/A 20 N/A N/A 0

N/A 0

100.00%

1.

(02.10) "% Completed" exceeds 100% since Class 3 pressure tests are performed each inspection period.

2.

(02.10) Twenty components representing the twenty systems in Class 3 as reported in the lSI Program Plan.

100.00%

26.23%

30.30%

33.01%

20.00%

28.69%

26.23%

30.30%

33.01%

20.00%

28.69%

26.23%

30.30%

33.01%

20.00%

28.69%

26.12%

16.58%

10.23%

47.30%

16.73%

Category F-A Non-Deferred Exams F1.10 467 122 20 32 61 29 0

59 0

F1.20 598 99 16 30 49 20 0

44 0

F1.30 1007 103 17 34 51 18 0

43 0

F1.40 74 35 6

7 17 11 0

19 0

Totals:

2146 359 58 103 179 77 0

166 0

1.

(F1.30 & F1.40) Unit 0 (Common) components are scheduled with and included in the Unit 1 counts.

2.

(F1.40) Per Examination Category F-A, Note 3, for mUltiple components other than piping within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined.

Category R-A Non-Socket Welds 1

128 32 6

16 16 0

0 8

0 25.00%

50.00%

2 136 36 6

10 18 8

0 17 0

26.47%

27.78%

4 1400 146 24 68 73 5

0 41 0

10.43%

46.58%

5 71 10 2

0 5

5 0

7 0

14.08%

0.00%

Totals:

1735 224 36 94 112 18 0

74 0

12.91%

41.96%

1.

(BER Welds) The # of Comp and # Selected include all BER welds which have been integrated into the RISI Program and are selected in accordance with the Risk Informed BER methodology.

Section 3.0 Page 7 of 8

(This report is used to verify that the periodic I

requirements of Tables IWx-2412-1 will be met by the interval schedule.)

I

of I Total I

Item No.

Comp Selected Min BYRON STATION UNIT 1 AND UNIT COMMON - 3RD INTERVAL I (The percentage requirements of Tables tWx-ASME SECTION XI EXAMINATION STATUS REPORT 2412-1 apply to the Category and were applied to each Item only when practIcal.)

Exams Completed I

I

% Exams Completed Per 1 Max Min Per 2 Max Per 3

% Selected Period 1 I Period 2 I Period 3 Category R-A Socket Welds 2

91 38 N/A 114 N/A N/A 0

N/A 0

41.76%

300.00%

4 188 44 N/A 132 N/A N/A 0

N/A 0

23.40%

300.00%

5 339 34 N/A 102 N/A N/A 0

N/A 0

10.03%

300.00%

Totals:

618 116 N/A 348 N1A N1A 0

N1A 0

18.77%

300.00%

1.

Socket welds for Examination Category R-A piping structural elements are listed separately from butt welds because socket welds are selected for examination in "each" refueling outage. Including socket welds in the # of Comp, Total Selected, and # Selected fields with the butt welds would misrepresent the %

completed distributions for the remainder of the Examination Category. The n% Completed" exceeds 100% since they are examined each outage per ASME Code Case N-578-1, Table 1, footnote 12.

Section 3.0 Page 8 of 8

ML100050360

Text

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