ML20207D234

Post Outage (90 Day) Summary Rept, for ISI Exams & Repair/Replacement Activities Conducted 981207-1205

ML20207D234
Person / Time
Site:	Quad Cities
Issue date:	03/01/1999
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20207D208	List: ML20207D234 SVP-99-022, Forwards Post Outage (90 Day) Summary Rept, for ISI Exams & Repair/Replacement Activities Conducted from Beginning of Second Period Through Q1R15 Refueling Outage
References
NUDOCS 9903090279
Download: ML20207D234 (150)

Text

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S' Quad Cities Nuclear Power Station - Unit 1 Post Outage (90 Day) Summary Report March 1,1999 Outage Start Date: November 7,199t Outage End Date: December 5,1998 9

W zien s

4. cr

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m Commercial Service Date: February 18,1973 22710 206* Avenue North s

Cordova,IL 61242 Commonwealth Edison Company P.O. Box 767 Chicago,IL 60690 Prepared By:

'If Reviewed By:

Approved By:

O-

{'s188H318Sjl4 g

F C mmonwealth Edison Quid Cities Nuclear Power Station P.O. Box 767 Unit I Chicago,IL 60690 22710 206* Avenue North Conunercial Service Date 2/18/73 Cordova,IL 61242 Table of Contents

1.0 INTRODUCTION

3

'l.1.

OUTAGE, PERIOD AND INTERVAL START AND END DATES =

.3 1.2.

EXAMINATION PROGRAM REQUIREMENTS...

.3 2.0 NIS-1 FORM 4

3.0 ABSTRACT OF EXAMINATIONS, CONDITIONS NOTED AND CORRECTIVE MEASURES.

6 3.1.

SECTION XI EXAMINAT10NS

SUMMARY

.6 3.2.

AUGMENTED EXAMINATIONS

SUMMARY

6 3.2.1. GENERJC LETTER 88 01.

..6 3.2.2. NUREG - 0619 -

7 3.3.

INVESSEL INSPECTIONS (IVI)...

.7 Table 3.1-1.,

.8 ASME Section XIOutage Scope.;

.8 Table 3.1-1 A..

. 13 ASME Section XI Limited Coverage Summary..

. 13 Table 3.1-2..

. I4 Pressure Testing Summary..

.I4 Table 3.13..

. I3 Snubber Functional Test.,

. 15

. Table 3.21.

.I6 GL 88-01 OutageScope..

. 16 Table 3.2 2..

. 18 GL 88 01 ExpandedScope..

. 18 Table 3.31.

.20 invesselInspection Scope....

.20 4.0 CONDITIONS NOTED AND CORRECTIVE MEASURES 21 Table 4.0-1.

. 21 Conditions Noted and Corrective Actions..

.' 21 5.0 REPAIR 1 REPLACEMENT

SUMMARY

22 5.1, NIS-2 INDEX.;

.22 Table $.I.I...

. 22 NIS-2 Index..

. 22 5.2.

NIS.2 FORMS,-

.25 i

I e

2 of 25

I?

Commonwalth Edison Quad Cities Nuclear Power Station P.O. Box 767 '

Unit 1

' Chicago,IL 60690 22710 206* Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242

~~1.0. INTRODUCTION 1.1.

Outage, Period and Interval Start and End Dates

! This Inservice Inspect. ion Summary Report addresses examinations performed

- between the end of the previous refueling outage September 1,1996 through the end of the current refueling outage. This current refueling outage was the 15* refueling outage for Quad Cities Nuclear Power Station Unit One. The outage staned November 7,1998 and ended December 5,1998.

This refueling outage is the only outage scheduled for the second inspection period of the third inspection interval. The second inspection period 'was originally scheduled to begin on February 18,1996 and scheduled to end on February 18,2000.

Due to the extended first period as repoded in the previous Inspection Summary,

- ESK-96-219 November 22,1996, the second period started on September 1,1996

. and will end on February 18,2000.

This Inservice Inspection Summary Report contains the test and examinations through December 5*,1998 and is not intended to close out the second inspection period.

Tests, examinations, repairs and/or replacements associated with ASME Section XI were witnessed or othenvise verified by Mr. Gordon Bosley, Mr. Duane Oakley or Mr. Raymond Spuhl. Non-ASME Section XI or augmented examinations were not witnessed or otherwise verified by Mr. Bosley, Mr. Oakley or Mr. Spuhl and are marked "Not Required" or "N/A" on the applicable examination reports. Mn Bosley, Mr. Oakley and Mr. Spuhl are inspectors of the Hartford Steam Boiler Inspection &

Insurance Company. The Hartford Regional Office is located at 2443 Warrenville Road, Lisle, Illinois,60532-9871.

1.2.

Examination Program Requirements

- The examination requirements of ASME Boiler and Pressure Vessel Code,Section XI, Division 1, " Rules for Inservice Inspection of Nuclear Power Plant Components,

" 1989 Edition, no addenda were implemented.

i 3 of 25

s Commonwecith Edison Quad Cities Nuclear Power Station

[

P.O. Box 767 Unit 1 Chicago,IL 60690 22710 206'" Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242

(

. 2.0 NIS-1 Form FORM NIS-1 OWNER'S REPORT FOR INSERVICE '.NSPECTIONS As required Tr, Ene Provisions of the ASME Code Rules

1. Owner Commonwealth Edison, P.O. Box 767, Chicago, IL 60690 (Name and Address of Owner)

[

2. Plant Quad Cities Nuclear Power Station,22710 206th, Ave. North, Cordova, IL 61242 (Name and Address of Owner)

(

3. Plant Unit One

4. Owner Certificate of Authorization (if required)

N/A

5. Commercial Service Date 2/18/73

6. National Board Number for Unit N/A

7. Components Inspected Component or Manufacturer Manufacturer State or Natmnal

[

Appurtenance Or Installer or Installer Province No.

Board No.

Serial No.

~

Reactor Pressure Babcock & Wilcox 610-0122-51-52 B0074099 N-140 Vessel Reactor Recirculanon Dravo Corp.

N/A - See Table 3.1-1 N/A N/A Core Spray Grinnell N/A - See Table 3.1-1 N/A N/A h

Feedwater Grmnell N/A - See Table 3.1-1 N/A N/A

' Main Steam Grinnell N/A - See Table 3.1-1 N/A N/A Residuallicat Grmnell N/A - See 1able 3.1 1 N/A N/A Removal Control Rod Dnve Gnnnell N/A - See Table 3.1-1 N/A N/A

[.

lingh Pressure Coolant Grinnell N/A - See Table 3.1-1 N/A N/A L

Injection Reactor Water Clean Grmncil N/A - See Table 3.1-1 N/A N/A Up Shutdown Coolmg Gnnnell N/A - See Table 3.1 1 N/A N/A

(

Reactor Core Isolation Gnnnell N/A - See Table 3.1-1 N/A

.N/A Cooling Note: Supplemental sheets in' form oflists, sketches, or drawings may be ur:d, provided (1) size is 8% in. x 11 % m.,

(2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of thp form.

[

4 of 25 l

Commonweilth Edison

- Quad Cities Nucle'_r Pow:r Station P.O. B:x 767 Unit 1 Chic:32,IL 60690 22710 206* Avenue N rth CommercialService Date 2/18/73 Cordova,IL 61242 FORM NIS-1 (Back).

t

8. Exanunation Dates:

9/1/96. to 12/5/98

9. Inspection Period Identification :

2nd Period - From 9/3/96 to 2/18/00

10. Inspection Interval identification :

3rd laterval - From 2/18/93 to 2/18/03

{.

I1. Applicable Edition of Section XI 1989 Addenda N/A

12. Date/ Revision oflaspection Plan:

1!!!8/98 Rev.3

13. Abstract of Exammation and Tests. Include a list of exammations and tests and a statement concerning status of work

. required for the laspection Plan. See Section 3.0 and Tables 3.1-1.

14. Abstract of Results of Exam. nations and Tests. See Section 3.0 and Tables 3.1 1 and 4.01

15. Abstract of Corrective Measures. See Section 3.0 and Table 4.0-1.

h We certify that a) the statement made in this report are correct, b) the exammations nd tests meet f

Inspection Plan as required by the ASME Code,Section XI, and c) corrective measures taken conform to the ASME

{'

Code, Seenon XI.

Cenificate of Authorization No. (if applicable)

N/A Expiration Date N/A Date M{ 19 @d)

Signed Commonwealth Edison Co.

l By (MM H, ;[/, u o,,,,

7--

f CERTIFICATE OF INSERVICE INSPECTION I

I, the under signed, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois And employed by H. S. B. L & L Co.

of Hanford, CT have inspected the components described in the Owner's Repon dunng the period 9/01/96 To 12/5/98

.., and state that to the best of my knowledge and belief, the Owner br.s performed exammations and tests and taken corrective measures descif5ed in this Owner's Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the exanunations, tests, and corrective measures described in this Owner's Report. Furthermore, neither the Wim nor his employer shall be liable in any manner for any personal injury or propeny damage or a loss of

{

any kind arising from or connected with this inspection.

D Counmssions IL 971 laspector's g ture National Board, State, Province, and Endorsements Date 'h

/

19 9f Sof25

Commonweahh Edison Quid Cities Nuclear Power Station

[

P.O. Box 767 Unit 1

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Chicago,IL 60690 22710 206* Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242 3.0 Abstract of Examinations, Conditions Noted and Corrective Measures.

3.1.

Section XI Examinations Summary A combination of ultiosonic (UT), liquid penetrant (PT), and magnetic particle (MT) testing was performed prior to and during QlR15 on 123 ISI Program components.

Examinations were perfonned by Lambert, MacGill, Thomas (LMT), General Electric (GE) and Commonwealth Edison (Comed) personnel. ISI inspections comprised of

~

' 70 UT,36 PT and 40 MT examinations. Forty visual examinations were performed by Comed certified personnel on Class 1 and 2 components. Table 3.1-1 summarizes these inspections and the results.

f Volumetric examinations listed in Table 3.1-1 that did not meet coverage requirements ofSection XI of the ASME, Code coverage of more than 90 percent of the specified

[

examination volume, are listed in Table 3.1-1 A. Supplemental examinations were performed on these components where practical to increase examination coverage.

Relief request will be generated and submitted as required by 10 CFR 50.55a(g)5(iii)

[

and 50.55a(g)5(iv).

Volumetric and surface examinations were compared with the recorded re<.is of f

previous examinations for all applicable Class 1 and 2 components.

Pressure testing VT-2 exams not related to repair / replacement activities are documented in Table 3.1-2.

Comed performed functional tests on a total of twenty-one snubbers for operability per Technical Specifications 10% sampling, Service Life Monitoring / Failure Trending Sample and ASME Section XI, Relief Request CR-09. Fourteen of the twenty-one snubbers were ASME Section XI. Four snubbers failed the functional test but were f

part of the Service Life Monitoring / Failure Trendmg sample so no sample expansion was required. Spare like-for-like snubbers were tested and used to replace the four failures. All snubbers were reinstalled and found acceptable for continued operation.

Table 3.1-3 summarizes these inspections and the results.

Table 4.0-1 summarizes the conditions noted and measures taken to correct the conditions.

3.2. Augmented Examinations Summary 3.2.1.

Generic Letter 88-01 Augmented examinations required by Generic Letter 88-01,"NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austentic Stainless Steel

(.

Piping," were performed as shown in Tables 3.2-1 and 3.2-2. The outage scope of l

thirty-five welds included 29 Category "C",3 Category "E" and 3 Category "F" welds.

Indications were found in geven welds and evaluated according to IWB-3640. The f

6 of 25

Commonwealth Edison Quid Cities Nuctear Power Station P.O. Box 767 Unit 1 Chicago,IL 60690 22710 206* Avenue North Conunercial Service Date 2/18/73 Cordova,IL 61242 indications in weld 02BS-Fl4, originally found during QlR14, had grown and were evaluated to be unacceptable. The indications identified in welds 02AS-F9,02 AD-F8 and 02BS-F7 were new and also determined to be unacceptable. All four welds were repaired with a weld overlay in accordance with Code Case N-504, Alternative Rules for Repair of Class 1,2, and 3 Austenitic Stainless Steel Piping Section XI, Division I, and a sample expansion was selected. The other three welds,02AD-F12,02AS-S4 and 02BS-F4 were evaluated and found to be acceptable for continued sen' ice. The sample expansion consisted of the remaining twenty-nine welds that were 28" diameter and had been Induction Heating Stress improvement treated (IHSI). Table 3.2-1 summarizes these inspections and the results.

A root cause was performed to evaluate the unexpected growth of the existing flaws in 02BS-F14, and to discuss the effectiveness of the IHSI process. As a result of the root cause evaluation, Quad Cities committed to and has changed all Unit 128"IHSI treated Category "C" welds to Category "D".

3.2.2.

NUREG - 0619 Augmented examinations required by NUREG - 0619, "BWR Feedwater Nozzle and Control Rod Drive Retum Line Nozzle Cracking", were performed on the inner radius and bore regions of the Feedwater Nozzles, N4A, B, C, and D. The examinations were performed utilizing GERIS 2000 OD system and manual UT examination techniques in accordance with Boiling Water Reactor Owners' Group (BWROG) report GE-NE-523-A71-0594, " Alternate BWR Feedwater Nozzle Inspection Requirements," approved with conditions by the NRC (Reference NRC SER dated June 5,1998). Previous data was reviewed with no change in results. No indications found required evaluation and were acceptable to the requirements of ASME B&PV code Section XI,1989, Category B-D inner radius and NUREG 0619.

3.3. InvesselInspections (IVI)

General Electric performed IVI on the following components; Reactor Pressure Vessel Interior, Jet Pumps, Core Spray Internal Piping, Core Spray Spargers, Top Guide, Shroud Repair Hardware, Fuel Support Castings and Dryer / Separator. Reportable indications were found on the reactor internal Core Spray piping, Jet Pumps 7/8 and 19/20. Table 4.01 summarizes these indications in more detail. Attachment 1 includes the required evaluations for the conditions noted above and are being l

transmitted for information only as required by the applicable BWRVIP I&E f

Guidelines.

l l

1 l

I 7 of 25

F Comm<macalth Edison Quad Cities Nuclear Power Statior.

P.O. Box 767 Unit 1 Chicago,IL 60690 22710 206* Avenue ftorth Commercial Service Date 2/18/73 Cordova,IL 61242 Table 3.1-1 Quad Cities Unit I ASME Section XI Outage Scope Drawing Component Class Category item inspection Date Results M 3121 Sht. I RPV TlitiF I

B-A Bl.40 UT-0*

11/12/98 NRI RPV TiltIF 1

B-A Bl.40 MT 11/11/98 Acceptable RPV-T11HF l

BA Bl.40 UT 45's,60's,70's 11/12S8 NRI M-3121 Sht. I N2C 1

B-D B3.90 UT#

11/2W98 NRI N2C 1

B-D B3.90 UT-45's 60's,70's 15/20/98 NRI N2CIR=

l B-D B3.100 UT-70's 11/20/98 NRI M-3121 Sht. I N2D 1

B-D B3.90 UT 0*

11/20/98 NRI N2D 1

BD B).90 UT-45's,60's,70's 11/20/98 NRl N2DIR I

B-D B3.100 UT-70's 11/20/98 NRI M 3121 Sht. I N2E I

B-D B3.90 UT O' 11/20/98 NRl N2E I

B-D B3.90 UT-45's,60's,70's 11/20/98 NRI N2EIR I

B-D B3.100 UT 70's 1I/20/98 NRI M-31215ht.1 N38 1

3-D B3.90 UT-0*

11/09/98 NPJ N38 I

B-D l B3.90 UT-45's,'es,70's 11/09/98 NRI N3BIR 1

B-D B3.100 UT-70's 11/09/98 NPJ M-3105 Sht. I N6A I

B-D B3.90 UT-0*

11/13/98 NRI N6A 1

B-D B3f; UT-45*s,60's,70's 11/13/98 NRI N6 AIR 1

B-D B3.100 UT-70's 11/13/98 NIU M-3121 Sht.1 NBA 1

B-D 83.90 UT#

11/21/98 NR1 NBA 1

B-D B3.90 UT-45's,60's,70's 11/21/98 NRI N8 AIR 1

B-D B3.100 UT-70's 11/21/98 NRI M 3103 Sht.1 02K-Fi i

B-F B5.10 PT 11/21/98 Acceptable 02K-F1 i

B-F B5.10 UT-45*s 11/21/98 ID & Root G'comety 02K-F1 1

B-F B510 UT-60*1 IIT21/98 NRI M-3103 Sht.1 02L-Fi i

BF B5.10 PT 11/21/98 Acceptable 021-Fi i

B-F B5.10 UT-45's 11/21/98 ID & Ruot Geometry 02L-Fi 1

B-F B5.10 UT-60*]

11/21/98 NRI

~

M-3103 Sht.1 02M-FI I

B-F B5.10 PT 11/21/98 Acceptable 02M-Fi B-F B5.10 UT-45's 11/21/98 ID & Root Geometry 02M-Fi 1

B-F B5.10 UT-60*1 11/21/98 NRI M-310$ Sht. )

N6A-SI 1

BF.

B5.10 PT 11/11/98 Acceptable N6A-SI I

B-F B5.10 UT-45's 11/12/98 ID Geometry N6A-SI 1

BF B5.10 UT-60*l 11/12/98 NRI M-3103 Sht. 4 N8A-Fl 1

B-F B5.10 PT 11/21/98 Acceptable NBA-F1 1

B-F B5.10 UT-45's 11/22/98 NRI NBA Fl i

BF B5.10 UT-45's 11/22/98 NRI NBA41 i

B-F B5.10 -

UT-45*!

11/22/98 NRI NBA-F1 i

B-F B5.10 UT-45*1 11/22/98 NR1 51-3104 Sht. I 14A-F3R 1

B-F B5.130 PT I1/09/98 Acceptable 14A-F3R I

B-F B5.130 UT-45's 11/09'98 ID Geometry l

14A F3R 1

Bf B5.130 UT-45*1 11/09/98 ID & koot Geometry Bof25

Cornmonwealth Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit 1 Chic:go,IL 60690 22710 206* Avenue North Cornmercial Service Date 2/18/73 Cordova,IL 61242 Table 3.1-1 Quad Cities Unit 1 ASME Section XI Outage Scope Drawing Component Cisss Category item Inspection Date Results M 3104 Sht. I 14 A-F4ER I

B-F B5.130 PT 11/09/98 Acceptable 14A-F4ER I

D-F B5.130 UT-45's 11/09/98 ID Geometry I4A-F4ER I

B-F B5.130 UT-4 5*1 11/09/98 ID & Root Geometry M 3105 Sht.1 0300-1 1

U-F B5.20 PT 11/21/98 Acceptable M-3131Sht.$

CRD ilousing 1

B-G-2 B7.50 VT-1 11/15/98 Acceptable M-3103 Sht. 3 Decon Flange "A" I

B G-2 B7.50 VT-1 11/25/98 Acceptable M-3103 Sht. 3 Decon Flange "B" 1

B-G 2 B7.50 VT-1 11/12/98 Acceptable M-3105 Sht. I N6A Flange i

B-G-2 B7.50 VT-1 11/25/98 Acceptable M 3105 Sht. I N6B Flange 1

B-G-2 B7.50 VT-1 11/20/98 Acceptable M-3103 Sht.1 02A-F5 B-J D911 PT 11/14/98 Acceptable 02A-F5 i

B-J D9.11 UT-45's 11/14/98 NRl 02A-F5 I

B-J B9.1 I UT-60*)

I1/14/98 NR1 M-3103 Sht. 3 02AS-512 1

B-J D9.ll UT-60*1 11/11/98 NRI 02AS-S12 i

B-J D9.11 PT 11/11/98 Acceptable M-3103 Sht. 2 02BD-F12 I

B4 8 9.11 PT 11/11/98 Acceptable 02BD-F12 1

D4 D9.l l UT-60*l 11/12/98 NRJ 02DD-F12 1

B4 D911 UT-45's 11/12/98 Root Geometry M-3103 Sht. 3 02BS-F6 1

D4 B9.11 PT I1/12/98 Acceptable 02BS-F6 i

B4 B9.11 UT-45's 11/13/98 ID Geometry 02BS-F6 i

B4 B9.11 UT-60*]

11/22/98 NRJ M 3103 Sht.1 02J-F2 i

B-J D9.11 PT 11/20/98 Acceptable 02J-F2 B4 B9.II UT-45's 11/20/98 ID & Root Geometry M-3103 Sht. 2 105 76 W3 i

B4 B9.11 PT 11/11/98 Acceptab!c 105-76-W3 I

B4 B9.11 UT-45*s 11/11/98 hRI M-3105 Sht. 2 10AD-S15 i

B4 B9.ll PT 10/30/98 Acceptable IDAD-SIS 1

B4 B9.11 UT-45*s,70's 11/06/98 NRI 10AD-S15 1

B-J D9.11 UT-60*1 11/06/98 NRI M-3105 Sht. 3 10BD-F16 1

B-J D9.11 PT 11/19/98 Acceptable 10BD-F16 i

B4 B9.11 UT-60*)

11/14/98 NRI 100D-F16 i

B4 B9.11 UT-45's 11/14/98 Root Geometry M 310$ $ht.3 10BD-S17 I

B4 B9.11 FT 11/06/98 Acceptable 10BD-$17 1

B4 D9.11 UT 45*s,70's 11/06/98 NRJ 10BD-S17 i

B-J D9.ll UT-60*l 11/06/98 NRI M-3103 Sht. 3 10S-F6 1

B-J 89.11 PT 11/18/98 Acceptable 10S-F6.

I B4 B9.11 UT-45's l l/l R'98 ID Geometry 10S-F6 i

B4 B9.11 UT-60*l 11/18/98 NRI M-3109 Sht. I 125-F28R I

B4 D9. ll PT I1/22/98 Acceptable 12S-F28R I

B-J 89.1I UT-45's 1I/22/98 NRI 12S-F28R 1

B-J B9.11 UT-60*l 11/22/98 Nk!

M-3109 Sht i 125-$13R 1

D4 B9.11 PT 11/20/98 Acceptable 12S-S13R 1

DJ D9.ll UT-45's,70's i1/20/98 ID & Root Geometry, Cll M-3109 Sht. I 12S-S8R I

B4 B9.11 PT 11/20/98 Accer'. 4le 125-S8R I

BJ B9.11 UT-45*s,70's 11/20/98 ID & Rom deometry,CD M-3108 Sht. I 23S-F23 I

B-J D9.11 Mf i1/19/98 Acceptable 23S-F23 1

B4 D9. l l UT-0*. 45's, 60's 11/18/98 Root Geometry M 3108 Sht. I 23S-S9 I

B4 B9.11 PT 11/19/98 Acceptable 235-S9 1

BtJ B9.11 UT-45*s 11/20/98 NRI r

l 9 0f 25 i

i Commonwealth Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit 1 Chicago,IL 60690 22710 206* Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242 Table 3.1-1 Quad Cities Unit 1 ASME Section XI Outage Scope Drawing Component Class Category item inspection Date Results M 3101 Sht. I 30A-F31 1

B-J B9.11 MT 11/19/98 Acceptable 30A-F31 1

B-J B9.11 UT 0*,45's i1/20'98 ID & Root Geometry M-3101 Sht. I 30B-Fi i

BJ B9.11 MT 11/09/98 Acceptable 30B-Fi 1

B-J B9.11 UT-45*s 11/09/98 Root Geometry M-3101 Sht. I 308-F27 1

BJ 8 9.11 MT 11/19/98 Acceptable 30B-F27 1

B-J 8 9.11 UT-45's 11/19/98 ID & Root Geometry M 3101 Sht.1 30B-S10 1

B-J B9.11 MT 11/19/98 Acceptable 30B-S10 i

B-J 8 9.11 UT-45's 1In9/98 ID & Root Geometry M 3101 Sht. I 30B-517 I

BJ B9.11 MT 11/19/98 Acceptable 30B-S17 i

B-J B9.l l UT 0*,45's 11/21/98 NRI M-3101 Sht. 2 30C-F31 i

B-J B9.11 MT II/19/98 Acceptable 30C-F31 1

BJ B9.1I UT-0*. 45's Ii/19/98 ID & Root Geometry 30C-F31 1

BJ B9.11 UT-60's 11/19/98 ID & Root Geometry M 3101 Sht.2 30C-S10 i

B-J -

B911 MT 11/19/98 Acceptable 30C S10 1

B-J B9.11 UT-45's 11/19/98 ID & Root Geometry M-3101 Sht. 2 30D-SO 1

B-J 8 9.11 MT 11/19/98 Acceptable 30D-50 1

B-J B9.11 UT-45's 11/19/98 NRI M-3101 Sht. 2 30D-Sil 1

B-J 8 9.11 MT 11/20/98 Acceptable 30D-Si l 1

B-J B9.11 UT-0",45's 11/20'98 NRI M 3101 Sht.2 30D S2 i

B.J 8 9.11 MT 11/09'98 Acceptable 30D-S2 i

BJ B9.1I UT-45's 11/09/98 NRI M 3102 Sht. I 32A-S10 1

B-J B9,11 MT II/19/98 Acceptable 324-S10 1

B-J B9.11 UT-0*,45's 11/20'98 ID & Root Geometry M 3102 Sht.2 32B-F16 i

BJ 89.11 MT 11/19/98 Acceptable 32D-F16 i

B-J B9.1I UT-0*. 45's i1/20/98 ID & Root Geonstry M 3102 Sht.2 32D-S0 i

B-J 89.11 MT 11/21/98 Acceptable 32D40 1

B-J B9.11 UT-45's 11/21/98 ID Geometry M-3102 Sht.1 32F-:n) 1 BJ 8 9.11 MT 11/20/98 Acceptable 32F-S0 1

D,'

B9.II'l UT-45S 11/21/98 ID Geometry M-3103 Sht 4 N8A-S3 i

B-J E9.Il ~

PT 11/21/98 Acceptable NBA-S3 1

fi-J B9.11

'UT45's 11/22/98 NRI M-3103 Sht. 4 N8A 54 i

BJ 0 9.11 PT 11/21/98 Acceptable NBA-S4 1

BJ B9.11 UT-45's 11/22/98 NRI N/A RPV Studs 1-92 i

B-J BO.ll UT-O' 11/08/98 NRI M-3109 Sht. 2 1265-F18 i

B-J 8 9.21 PT 11/18/98 Acceptable M-3101 Sht. I 30B-Sl6 i

BJ 89.31 MT 11/19/98 Acceptable 308-S16 i

B-J B9.31 UT-45's 11/19/98 NRI M-3109 Sht.1

- 12S-F4BF 1

B-J B9.32 PT 11/19/98 Acceptable M-3103 Sht. 3 0204A-Fl.

1 BJ B9.40 PT ll/II/98 Acceptable M-3103 Sht. 3 0204A-F2R 1

B-J 89.40 PT 11/11/98 Acceptable M-3103 Sht. 3 0204B-F6 i

B-J B9.40 PT 11/11/98 Acceptable M 3103 Sht. 5 0209A-F5 I

B-J B9 40 PT 11/19/98 Acceptable M-3103 Sht. 5 02098 Fil i

BJ 89.40 PT 11/19/98 Acceptable M 3109 Sht. 2 1265-F14 I

B-J B9.40 PT 11/19/98 Acceptable M-3109 Sht. 2 1265-F22 1

B-J 89.40 PT 11/09/98 Acceptable M-3109 Sht. 2 1265-F24 1

B-J B9.40 PT 11/19'98 Acceptable M 3131 Sht.4 RPV Interior 1

B-N-1 B13.10 VT-3 11/10/98 Acceptable f

10 cf 25

r Commonwealth Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit 1 Chicago,IL 60690 22710 206thAvenue North Commercial Service Date 2/18/73 Cordova,IL 61242 Table 3.1-1 Quad Cities Unit 1 ASME Section XI Outage Scope Drawing 03mponent Clef,s Category item laspection Date Results M-3131 Sht. 4 -

J/P Riser Brace /RPV

.I D-N 2 B13.20 VT-3 11/25/98 Acceptable M-3131 Sht.13 1 A 1003A-2 2

C-A Cl.10 UT 0*.45*s i1/03/98 NRI M-3140 Sht. 2 1025 50 2

C-B C2.31 MT 11/24/98 Acceptable M-3140 Sht. 2 1025-54 2

C-B C2.31 MT 11/24/98 Acceptable M 3131 Sh*.13 N8A-Fi RHRilX 2

C-B C2.31 MT l d04/98 Acceptable M-3131 Sht.13 1003A-W-203A 2

C-C C3.10 MT 11/05/98 Acceptable M 3130 Sht. 3 1401 W-202.! A 2

C-C C3.20 MT 11/25/98 Acceptable M 3134 Sht.2 0318A-W-201 A 2

C-C C3.20 MT 11/26/98 Acceptable M 3130 Sht.1 1404-W-214 A 2

C-C C3.20 MT 11/08/98 Acceptable M 3130 Sht. 2 1403-30 2

C-F-1 C5.Il PT 11/06/98 Acceptable I403-30 2

C-F-1 C5.Il UT-0*,45's,70*s 11/07/98 NRI 1403-30 2

C-F-1 C5.Il UT-60*1 11/07/98 NRI M330 Sht.1 1404-43 2

C-F-1 C5.l t PT 10/28/98 Acceptable 1404 43 2

C-F-1 C5.l t UT-0*,45*

10/29/98 NRJ 1404 43 2

C-F-l C511 UT-55*1 10/29/98 NRI M-3134 Sht. 2

'0320-1 2

C-F-2 C5.51 MT 11/08/98 Acceptable 0320-1 2

C-F-2 C5.51 UT-0*,45*s 11/08/98 NRJ M 3134 Sht.1 0328-5 2

C-F-2 C5.51 MT I1/04/98 Acceptable 0328-5 2

C-F-2 C5.51 UT-0*, 45*s 11/04/98 NRI

- M 3131 Sht. 8 1008A-3 2

C-F-2 C5.51 MT 11/07/98 Acceptable 1008A-5 2

C-F-2 C5.51 UT-0*. 45's 1I/07/98 1D & Root Geometry M-3131 Sht. 9 1009A 1 2

C-F-2 C5.51 MT 11/07/98 Acceptable 1009A-1 2

C-F-2 C5.51 UT 0*,45's,60's 11/07/98 ID & Root Geometry M 3131 Sht. 5

. 10098-26 2

C-F 2 C5.51 MT 11/04/98 Acceptable 10098-26 2

C-F-2 C5.51 UT-0*,45*s 11/04/98 NRI M 3131 Sht.4 1013A-5 2

C-F-2 C3.51 MT 11/06/98 Acceptable 1013A-5 2

C-F-2 C5.51 UT-0*. 45's, 60's 11/06/98 NRI M 3131 Sht. I 1015B-9 2

C-F-2 C5.51 MT 11/04/98 Accepuable 1015B-9 2

C-F-2 C5.5I UT-0*, 4 5's 11/04/98 ID & Root Geometry M 3131 Sht. I 1024A-1 2

C-F-2 C5.51 MT 11/06/98 Acceptable 1024 A-1 2

C-F-2 C5.51 UT-0* 45's. 60's 11/0 &98 ID & Root Geometry M-3131 Sht. I 1024As2 2

C-F-2 C5.51 MT 11/06/98 Acceptable 1024A-2 2

C-F-2 C5.51 UT 0*,454,60's 11/0 & 98 ID & Root Geometry M 3130 Sht. 3 1401-8 2

C-F-2 C5.51 MT 11/02/98 Acceptable 1401 8 2

C-F-2 C5.51 UT 0*,45's 70's 11/02/98 NRJ M 3130 Sht. 2 1403-1 2

C-F-2 C5.51 MT 11/02/98 Ac :eptable 1403 1 2

C-F-2 C3 51 UT 0*,45's 11/06/98 ID & Root Geometry M 3130 Sht 2 1403-2 2

C-F-2 C5.51 MT 11/02/98 Acceptable 1403-2 2

C-F-2 C5.51 UT-0*,45's,70's 11/02/98 ID & Root Geometry M 3130 Sht.1 1404-8 2

C-F-2 ' C5.51 MT 11/02/98 Acceptable M 3130 Sht.1 1404-8 2

C-F-2 C5.01 UT-0*. 45*s, 70*s 11/02/98 NRJ M-3132 Sht. I 2302 14 2

C-F-2 C5.51 MT 10/30/98 NRI 2302-14 2

C-F-2 C5.51 UT-60's 10/31/98 ID Geometry 2302-14 2

C-F-2 C5.51 UT 0*.45's 10/31/98 ID Geometry M-3131 Sht. I 1016D 7A 2

C-F-2 C5.70 MT 11/10/98 Acceptable M 3131 Sht. I 1016D-8 2

C-F-2 C5 81 MT 11/la'98 Acceptable M-3103 Sht. 2 0200-G-139 '

I l'A F1.10 VT-3 11/07/98 Pass ll of 25

Commonwealth Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit 1

. Chicago,IL 60690 22710 206* Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242 Table 3.1-1 Quad Cities Unit 1 ASME Section XI Outage Scope Drawing Component Class Category item Inspection Date l

Results M-3103 Sht.1 0200-M-150 I

FA Fl.10 VT 3 11/07/98 Pass M-3103 Sht.1 0200-M-171 1

FA Fl.10 VT-3 11/07/98 Pass M-3103 Sht. 3 0200-W-104 A&B 1

FA Fl.10 YT 3 11/07/98 Pass

[

M 3105 Sht. 3 1012B W-104 I

FA Fl.10 VT 3 11/07/98 Pass

(.

M-3103 Sht. 3 1025-M-104.1 1

FA Fl.10 VT 3 11/09/98 Pass M 3109 Sht.1 1202-M 103 i

FA Fl.10 VT-3 11/07/98 Pass M-3109 Sht. I 1202 M-108.1 1

FA Fl.10 VT 3 11/09/98 Pass M-3101 Sht.1 3001 A-M-102.1 1

FA Fl.10 VT 3 11/07/98 Pass M-3101 Sht. 2 3001C-W-101 A&B 1

FA Fl.10 YT-3 11/07/98 Pass M-3102 Sht. 2 32048-M-104 1

FA Fl.10 VT-3 11/09/98 Pass M 3102 Sht.1 3204F-W-102 I

FA Fl.10 VT-3 11/07/98 Pass M-3131 Sht. 3 1013A-W 201 2

FA Fl.20 VT-3 11/02/98 Pass M-3131 Sht. 2 1018A-W 201 2

FA Fl.20 VT-3 11/03/98 Pass

(

M 3140 Sht. I 1025~M-204 2

FA Fl.20 VT-3 11/02/98 Pass

(

M-3140 Sht. I 1025-M-205 2

FA Fl.20 VT 3 11/02/98 Pass M 3140 Sht. 2 1025-M-227 2

FA Fl.20 VT-3 11/02/98 Pass M 3131 Sht.15 1086-O-204 2

FA Fl.20 VT-3 11/03/98 Pass M 3130 Sht. 3 1401 W-201 A&B 2

FA Fl.20 VT-3 11/02/98 Pass M-3130 Sht. 2 1403-W 201 2

FA Fl.20 VT-3 11/03/98 Pass M-3130 $ht. I 1404-M-205 2

FA F l.20 VT-3 11/02/98 Pass M 3132 Sht.2 2304-M-203 A&B 2

FA Fl.20 VT-3 10/27/98 Pass M 3132 Sht. 2 2304-W-204 2

FA Fl.20 VT-3 10/27/98 Pass M 3132 Sht.4 2305-M-201.1 2

FA Fl.20 VT-3 11/02/98 Pass M-3132 Sht. 3 2306-M-203 2

FA Fl.20 VT 3 11/03/98 Pass M-3103 Sht. 2 0200-M-110 1

FA FIA0 VT3 11/11/98 Pass M-3103 Sht. 2 0200-M-111 1

FA FI A0 VT-3 11/09/98 Pass M 3121 Sht.2 0200 W-178 i

FA FIA0 VT-3 11/08/98 Pass M-312i Sht.1 0200-W W9 1

FA FIA0 VT-3 11/08/98 Pass M 3121 Sht.1 0200-W-180 I

FA FIA0 VT-3 11/08/98 Pass M-3131 Sht. 2 1016A-M-202 2

FA F140 VT-3 11/03/98 Pass

(

M-3132 Sht. 2 2302-M-207 2

FA FI40 VT-3 10/27/98 Pass t,

M 3132 Sht.2 2302-W-206 2

FA FIA0 VT 3 10/27/98 Pass L

{

i

(

12 0f 25 li..

l Commonwnhh Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit 1

' Chicago,IL 60690 '

22710 206* Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242 f

Table 3.1-1 A j

Quad Cities Unit I t

ASME Section XI Limited Coverage Summary Drawing Component l Class Category item.

losPection ASME %

ASME % Coterage Coverage w/ Supplemental M 3121 Sht.1 RPV-T11HF 1-B-A Bl.40 UT 58.18 52.99 M 3121 Sht.1 N2C 1

B..D B3.90 UT

.19.45 40.26 N2CIR 1

B-D B3.100 UT 36.90 N/A M-3121 Sht. I N2D I

BD B3.90 UT 19.45 40.26 N2DIR 1

B-D B3.100 UT 36.90 N/A M-3121 Sht.1 N2E 1

B-D B3.90 UT 19.45 40.26 N2E1R I

B-D B3.100 UT 36.90 N/A M 3121 Sht. I N3B 1

B-D B3.90 UT 46.65 41,13 N3BIR 1

B-D B3.100 UT 28.10 N/A M-3105 Sht. I N6A 1

B-D B3.90 UT 43.07 38.68 N6 AIR I

B-D B3.100 UT

$0.40 N/A M-3121 Sht.1 NBA I

B-D B3.90 UT 21.71 38.5 NBAIR 1

B-D B3.100 UT 62.30 N/A M-3103 Sht. 3 02BS-F6 i

BJ B9.11 UT 39.97 N/A M-3103, Sht. 3 IOS-Fl i

B-J B9.11 UT 86.00 N/A M-3103, Sht. 3 10S-F5 1

BJ B9.11 (H

87.00 N/A M-3109 Sht. I 12S F28R 1

BJ B9.11 UT 90.00 N/A M-3103 Sht. 4 NBA-53 I

BJ B911 UT 75.00 N/A M-3105, Sht. 2 10AD Fl 1

B-J B9.11 UT 83.75 N/A M-3105, Sht. 2 10AD-F4 1

B-J B9.11 UT B5.00 N/A M-3103, Sht. 2 02AD-Fi I

Il J B9.ll UT 85.00 N/A M 3103, Sht. 2 02BD Fl 1

B-J B9.ll UT 75.00 N/A M-3103, Sht. 2 02AD-S2 i

B-J 89.!!

UT 86.35 N/A M 3130 Sht. I 1404-43 2

C-F-1 C5.ll UT B7.50 N/A M-3131 Sht. I 1016D-8 2

C-F-2 C5.81 MT 86.70 N/A 1L i

t ft 13 of 25

Conunonwealth Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit 1 Chicago,IL -60690 22710 206* Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242 Table 3.1-2 Quad Cities Unit 1 Pressure Testing Summary Component inspection item Number Procedure Exam Date Relief Request Remarks RX & CLASS 1 Visual, VT 2 B15.10-B i5.71 QCOS 0201-08 5/29/98 PT-01, PR-07, Class 1 System PR-09 Leakage Test Line 1-0236-!

Visual, VT-2 C7.30-C7.40 VT Report 11/25/98 PR-02 Rx Vessel C7.70-C7.80 981V20179 Ilead Flange Seal Leak Detection System Control Rod Visual, VT-2 C7.30-C7.40 QCTS 0762-03 12/2/98 PT-01,PT-02, Class 2 System Drive System C7.70-C7.80 PR-09 Leakage Test RX & CLASS 1 Visual, VT-2 B15.10-B15.71 QCOS 0201-08 12/2/98 PT-01, PR-07, Class 1 System PR-09 Leakage Test i

14 of 25

Commonwealth Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit 1 Chicago,IL 60690 22710 206* Asenue North Conunercial Service Date 2/18/73 Cordova,IL 61242 Table 3.1-3 Quad Cities Unit i Snubber Functional Test Drawing Component Class Category item Inspection bate 'i ested Results M-3130 Sht. 4 1403-W 103 A&B 1

FA F1.10 FT 11/19/1998 Passed M 3103 Sht. 2 0200-W.l lo 1

FA Fl.40 FT 11/11/1998 Passed M-3103 Sht.1 0200-M-172 i

FA Fl.10 FT l l/09/199b Passed M-3103 Sl?t.1 0200-M 175 i

FA Fl.10 FT I1/08/1998 Failed M-3103 Sht.1 0200-M-174 I

FA F l.10 FT 11/10/1998 Passed M 3101 Sht. I 30018-M 101.1 1

FA F l.10 FT 11/14/1998 Passed M-3101 Sht.1 3001B-M-101.2 1

FA Fl.10 FT 11/10/1998 Passed M 3108 Sht. I 2305-M-101.1 1

FA Fl.10 FT 11/16/1998 Failed M 3131 Sht. 5 1012B M-203.1 2

FA Fl.20 FT 11/09/1998 Passed M-3103 Sht. 3 1025-M 101 A&B 1

FA

~Fl.10 1T 11/14/1998 Failed M-3103 Sht. 3 1025-M-101 A&B 1

FA Fl.10 FT 11/14/1998 Failed M 3103 Sht 3 1025-M 102 A&ll 1

FA Fl.10 F1 11/14/1998 Passed M 3103 Sht.3 1025-M 102 A&B 1

FA Fl.10 FT 11/14/1998 Passed M-3134 Sht.1 0328-M 201 2

FA Fl.20 FT 11/14/1998 Passed N/A l033' N/A N/A N/A FT 11/14/1998 Passed N/A 1-039' N/A N/A N/A FT 11/07/1998 Passed N/A l-055' N/A N/A N/A FT 11/11/1998 Passed N/A l-056' N/A N/A N/A FT 11/11/1998 Passed N/A i-059' N/A N/A N/A FT 11/10/1998 Past.ed N/A 1 081*

N/A N/A N/A FT 11/09/1998 Passed N/A 1-061*

N/A N/A N/A FT 11/10/1990 Passed oComponent Tech. Spec. Number, i

15 of 25

Commonwealth Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit 1 Chicago,IL 60690 22710 206* Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242 Table 3.2-1 Quad Cities Unit 1 GL 88-01 Outage Scope Drawing Component Class Category item inspection l

Date Results/ Comments M-3103, Sht. 2 02AD-FI 1

C D9.ll UT-45's 11/14'98 ID Geometry 02AD-Fi C

B9.11 UT-60*]

11/14/98 NRI M-3103, $ht. 2 02AD-F12 1

F D9.11 UT 45's 11/11/98 CIRC lGSCC 02A D-F12 i

F D9,il UT 60*]

11/11/98 CIRC IGSCC 02AD-F12 1

F B9.11 Evaluation 11/11/98 Acceptable M-3103, Sht. 2 02AD-F8 I

C D9.11 UT-45's 11/11/98 Axial 02AD-F8 1

C B9.11 UT-60*l 11/11/98 NRI 02AD-F8 1

C D9.11 Evaluation 11/1I/98 Apphed Overlay 02AD-F8 I

E B9.11 PT 11/27/98 Acceptable 02AD-F8 1

E D9.11 UT-0*

11/27/98 Acceptable 02AD-F8 I

E D9. ll UT45's 11/28 S 8 Acceptable 02AD-F8 I

E D9.11 UT-60* ODC 11/28/98 Acceptable M-3103, ShL 2 02AD-F9 1

C B9.11 UT-45's 11Il1/98 ID Geornetry 02AD-F9 1

C B911 UT-60*]

11/11/93 NRI M 3103,Sht.1 02A-Fi C

B9.11 UT-45's 11/14/98 NRI 02A Fi 1

C D9.11 UT-60*1 11/14/98 NR1 M 3103,Sht.1 02A-F5 i

C 8 9.11 PT 11/14/98 Acceptable 02A-F5 i

C D9.ll UT-45's 11/14/98 NRI 02A-F5 l

C D9.11 UF-60*1 11/14/98 NRI M-3103, Sht.1 02A-S3 I

C B9.11 UT-45's 11/14'98 NRI 02A-S3 i

C D9.11 UT-60*l 11/14/98 NRJ M-3103, Sht. 3 02AS-F14 1

C B9.11 UT-60*]

11/11/98 NRI M-3103, Sht. 3 02AS-F2 1

C D9.11 UT-60*1 11/04/98 NRI M-3103, Sht. 3 02AS-F5 1

C B9.11 UT-45's 11/14/98 ID & Root Geometry F

M 3103, Sht. 3 02AS-F8 1

C B9.11 UT-60*l 11/13/98 NRl 02AS-F8 1

C D9.11 UT-45's 11/13/98 NRI M-3103. Sht. 3 02AS-F9 1

C B9.11 UT-60*l 11/12/98 Linear 02AS-F9 1

C D9.11 UT-45's 11/12/98 Linear 02AS-F9 1

C B9.11 UT-45's

!!/13/98 Rejected 02AS-F9 1

C B9.11 Evaluation 11/12/98 Apphed Overlay 02AS-F9 I

E B9.l l PT 11/27/98 Acceptable 02AS-F9 1

E B9.11 UT-0*,60*l,70*1 12/1/98 NRI M-3103, Sht. 3 02AS-S!2 i

C D9.1i UT-60*1 11/lI/98 NPJ 02 AS-S12 1

C B9.11 PT 11/11/98 Acceptable M 3103, Sht. 3 02AS S3 1

C B9.11 UT 45's 11/11/98 ID & Root Geometry M 3103, Sht. 3 02AS-54 1

F B9.11 UT-45*s 11/11/98 Linear 02AS-S4 I

F D9.11 Evaluation 11/11/98 Acceptable M-3103, Sht. 2 02BD F12 I

C D9.ll PT 11/11/98 Acceptable 02BD-F12 1

C j D9.11 UT-45's 11/12/98 Ror* 7eometry 16 of 25

Commonwealth Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit 1 Chicago,IL 60690 22710 206* Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242 Table 3.2-1 Quad Cities Unit 1 GL 88-01 Outage Scope Drawing Component l Class l Category l Item inspection Date Result 6L'mments 02BD-F12 1

C B9.11 UT-60*]

11/12/98 NR M-3103,Sht. 3 02BS-F14 1

F B9.11 UT-45*s ll/lW98 Lmear 02BS-F14 1

F B9.1 i UT-60*]

11/10/98 Linear 02BS-F14 i

F B9.11 Evahiation ll/lW98 Applied Overlay 02BS-F14 1

E B9.11 PT 11/27/98 Acceouble 02BS-F14 1

E B9.11 UT-0*,60*l,70*l 11/30/98 NRI M 3103, Sht. 3 02BS-F6 i

C B9.ll PT 11/12/98 Acceptable 02BS-F6 I

C B9.11 UT 45's 11/13/98 ID Geometry 02BS-F6 I

C B9.11 UT 60*1 11/22/98 NRI M-3103, Sht. 3 02BS-F7 1

C B9.11 UT 45's 11/13/98 Circ. IGSCC 02BS F7 1

C B9.ll UT-60*l 11/13/98 Cire. IGSCC 02BS-F7 1

C B9. li Evaluation 11/13/98 Apphed Overlay 02BS-F7 1

E B911 PT 11/29/98 Acceptable 02BS-F7 1

E B911 UT-0*,60*l,70*1 12/2/98 NRI M-31oJ, Sht.1 02D-F2 C

B9.11 UT-45*s 11/26/98 ID & Root Geometry M 3103,Sht.1 02E-F2 C

B9.11 UT 45's 11/26/98 ID Georxtry M-3103, Sht.1 02-Fi i

C B9.11 UT-45's 11/14/98 NRI 02-F1 1

C B9,Il UT-60*1 11/14/98 NRI M-3103, Sho 1 02J-F2 I

C B9.11 PT I1/20/98 Acceptable 023-F2 I

C B911 UT 45's 11/20/98 ID & Roa Geometry M 3103,Sht.1 02K-F2 C

B9.11 UT-45's 11/25/98 ID & Root Geometry M-3103, Sht.1 02L-F2 C

B9.Il UT-45's 11/25/98 ID & Root Geometry M 3103, Sht.1 02L-F6 I

C B9.11 UT-45's 11Il4/98 ID & Root Geometry 02L-F6 1

C B9.11 UT-60*l 11/14'98 NR)

M 3!03, Sht.1 02L-S3 1

C B9.11 UT-45's

!!/24/98 ID & Root Geometry M-3103, Sht.1 02L-SSA I

C B911 UT-45's 11/14/98 ID & Root Geometry M 3103.Sht. I 02M-F2 i

C F til UT-4 5*s 11/24/98 ID & Root Geometry M 3105. Sht. 2 10AD-F1 1

C B9.11 UT-45's 11/14/98 ID Geometry 10AD-Fi 1

C B9.11 UT-60*l 11/14/98 NRI M 3105, Sht. 2 10AD-F4 i

C B9.l l UT-45's 11/14/98 ID Geometry 10AD-F4 1

C B9.11 UT-60*1 11/14/98 NRI M-3105, Sht 10AD-S3 i

C B911 UT-45*s 11/14/98 ID Geometry M 3103, Sht. 3 10S-Fi C

B9.11 UT-45's 11/15/98 ID & Root Geometry,CB 10S-F1 1

C B9.11 UT-60*l 11/15/98 ID & Rout Geometry M 3103, Sht. 3 10S-F5 1

C B9.ll UT-45's 11/15/98 ID & Root Geometry,CB 10S-F5 1

C B9.11 UT-60*l 11/15/98 NRl M-3103, Sht. 3 10S-S4 1

C B9.11 UT-45's ll/15N8 ID & Root Geometry, CB i

17 of 25

7..

Commonwe:lth Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit 1

- Chic go,IL 60690 22710 206* Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242 Table 3.2-2 Quad Cities Unit 1 GL 88-01 Expanded Scope Drawing Component Class l Cat item Inspettien Date Results/ Comments n

a M 3103, Sht. 2 02AD-S2 i

C B9.11 UT-45's ll/14S8 ID Geometry f.

02AD-52 1

C B9. ll UT-60*]

11/14/98 NRI M-3103, Sht. 2 02AD-S6 I

C B9.ll UT-45"s 11/14/98 ID Geometry M-3103, Sht.1 02A-59 i

C B9.11 UT-45's 11/24/98 Root Geometry f

M-3103, Sht. 2 02BD-Fi 1

C B9.11 UT-45's 11/14/98 NR1 M 3103, Sht. 2 02BD-F8 I

C B9.11 UT-45's 11/13/98 ID & Root Geometry 02BD-F8 1

C B9.11 UT 60*1 11/14/98 NRI f

M-3103, Sht. 2 02BD-F9 1

C B9.11 UT-45's 11/13/98 ID Geometry 02BD-F9 1

C D9.11 UT 60*1 lir13/98 NRI M-3103, Sht. 2 02BD-S2 i

C B9.11 UT-45's 11/13/98 ID Geometry 02BD-$2 1

C B9.11 UT-60*1 11/13/98 NRI M-3103, Sht. 2 02BD-56 I

C B9.!!

UT-45's 11/14/98 ID Geometry M-3103, Sht.1 02B-F5 1

C B9.11 UT-60*1 11/14/98 NRI 02B-F5 1

C B9.11 UT 45's 11/13/98 ID Geometry M 3103, Sht. 3 02BS-F2 i

C B9.ll UT-45's 11/15/98 NRI M-3103. Sht. 3 02BS-F4 1

F B9.11 UT-60*l 11/15/98 NRI

.02BS-F4 I

F B9.11 UT-45's 11/15/98 Root Geometry M-3103, Sht. 3 02BS 53 1

C B9.ll IR-45's ll/25/M ID Geometry M-3103, Sht.1 02C-F2 1

C B9.11 UT-45%

11/14/98 Cire. IGSCC M-3103, Sht.1 02C-F6 1

C B9.1I UT-45's 1I/24/98 Root Geometry 02C-F6 1

C B9.11 UT-60*]

11/24/98 Root Geometry M 3103,Sht.1 02D-F6 1

C B9.11 UT-45's 11/24/98 ID Geometry 02D-F6 I

C D9.Il UT-60*1 11/24/98 Root Geometry M-3103, Sht,1 02E-F6 1

C B9.ll UT-45's 11/24/98 ID Geometry 02E-F6 1

C B9.ll UT-60*l 11/24/98 ID Geome'ry M-3103, Sht.1 02-F2 1

C.

B9.Il UT-60*1 11/13/98 NRI 02-F2 1

C B9.11 UT-45's 11/13/98 Root Geometry M 3103,Sht.1 02F-F2 1

C B9.ll UT-45*s 11/26/98 Root Geometry M-3103, Sht.1 -

02F-F6 1

C 09.11 UT 45's 11/24/98 Root Geometry 02F-F6 -

1 C

B9.11 UT-60*l 11/24/98 NRI M-3103, Sht.1 02G-F2 1

C B9.ll UT-45's

!!/24/98 ID Georretry M 3103, Sht. ) 02G-F6 I

C B9.11 UT-45's 11/24/98 ID Geometry L2G-F6 I

C B9.11 UT-60*]

11/24/98 NRI M 3103, Sht. I 62ff-F2 I

C B9.11 UT 45's 11/26/98 ID Georretry M-3103 Sht. I 02H-F6 1

C B9.11 UT-454 11/26/98 ID Geometry 0211-F6 1

C B9.11 UT-60*1 11/26/98 1D Geometry M-3103. Sht.1 02M-F7 1

C B9.11 UT-45's 11/25/98 ID Geometry 02M-F7 1

C-B9.11

. UT-60*1 11/25/98 Root Geometry M 3105, Sht.'3 10BD-Fi 1

C B9.11 UT-45's 11/15/98 NRI

~

10BD-Fi 1

'C B9.Il UT 60*l 11/15/98 NRI 18 cf 25 -

Commonwealth Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit 1 Chicago,IL 60690 22710 206* Avenue North Commercial Service Date 2/18,73 Cordova,IL 61242 Table 3.2-2 Quad Cities Unit 1 GL 88-01 Expanded Scope Draning Component Class Cat item inspection l

Date Results/ Comments M-3105, Sht. 3 10BD-F5 i

C B9.11 UT 45*s 11/15/98 Root Geometry 10BD-F5 1

C B9.11 UT-60'l 11/15/98 NRI M-3105, Sht. 3 1011D-S2 i

C 139.11 UT-45's 11/15/98 Root Geometry M 3105, Sht. 3 10BD-S3 i

C B9.11 UT-45'l 11/15/98 NRI M-3105, Sht. 3 10BD-S4 I

C B9.11 UT-45's 11/15/98 Root Geometry i

19 0f 25

Commonwealth Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit I Chicago,IL 60690 22710 206* Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242 Table 3.3-1 Quad Cities Unit 1 InvesselInspection Scope AMI A ION ESUMS of COMPONENT REQUIREMENT METilOD EXAMINATION,

~I RPV Interior 3,1O See PIF Q1998-05268 &

Augmented Automated UT with Calculation QDC-0200-M-0768 Core Spray Piping BWRVIP-18 Supplemental Visual for evaluation ofindications at Core Spray Piping Welds.

Core Spray Spargers VT-1 (1 mil resolution)

NRI R

-8 Jet Pump Beams Augmented UT NRI R

41 See 2 for B-N 2, B13.20 and Jet Pumps

'T-1 (1 mil resolution) evaluation ofindications at Jet d

Pump 7/8 Riser.

^"E See PIF Q1998-05257 for Jet Pump Riser Welds EVT-1 Remote Camera evaluation ofindications at Jet R\\'

1 Pump 19/20 RS-1 weld.

VT (1 mil tesolution) or Shroud Repair Hardware BWRVIP-07 NRI Fuel Support Pieces (FSP) when removed for Augmented VT-3 NRI CRB Change-Out I gmnent Augmented VT-1 (1 mil resolution)

NRI Dryer / Separator Augmented VT-1 or VT-3 NRI i

20 0f 25

Commonwealth Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit 1 Chicago,IL 60690 22710 206* Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242 4.0 Conditions Noted and Corrective Measures Table 4.0-1 Quad Cities Unit 1 Conditions Noted and Corrective Actions Component ID Description / Resolution 1

Pressure Test LPRM-1-0756-3233, During the pressure test walk down the listed components were identified to be CRD's 1-300-2659,5023,5027, leaking. PIFs were generated and corrective actions were taken as required.

HCU 18 47, Corrective actions included tightening and'or replacing bolting material, CRD's 18-43,20-27,34-19 and performance of VT-3 of bolting and weld repair associated with a CRD line.

34-35, HCU's 1407,1431,18-23,22-Reference QCOS 0201-08 dated 12/2/98 and VT report #981V20240.

27,22-23,22-59,26-03,26-23, 26-27,30-11,30-27 and 30 59.

HCU Manifolds 06-43-120 and 38-31-120.

HCU Bonnets 22-03,2203-101, 26-43-102 and 50-19-126.

LPRM's 48-25,32-17,24-09, 24-57 and 40-09.

GL 88-01 Flaws previously identified durmg Q1R14 were evaluated and found acceptable for continued operation for approximately five years. These same flaws were examined 02AS-S4,02AD-F12 during QlRIS and did not exhibit growth. The existing evaluation was reviewed and it was determined that the two welds are acceptable for continued operation.

These welds are classified as Category "F" in the GL 88-01 Program and will be inspected during the next refueling outage.

Flaws exceeding r,cceptance stands ofIWB-3514 were identified. These fiaws were 02BS-F7 evaluated in accordance with IWB-3640 and found to be acceptable for at least one more cycle. This weld is classified as Category "F" in the GL 88-01 Program and will be inspected during the next refueling outage.

Flaws exceeding the acceptance standards ofIWB-3514 were evalr.ated in 02AS-F9,02AD-F8,02BS-F7 acc rdance with IWB-3640 and found unacceptable. These weld mere Category and 02BS-F14 "C" or "F" in the GL 88-01 program and were weld overlay repaired during Q1R15.

A baseline UT was performed and these welds have been re-classified as Category "E"in the GL 88-01 Program.

IVI Reportable indications on the Riser Brace to Riser weld. 'lhe indications were Jet Pmnps 7-8 evaluated by GE/ Comed in accordance with BWRVIP-28," Assessment of BWR Jet Pump Riser Elbow to Thermal Sleeve Weld Cracking", for limited operation. Plans are being made to repair the riser brace during QlP02 scheduled for 4/99.

Reportable indications on weld RS-1, Elbow to Thermal Sleeve, were evaluated by Jet Pumps 19-20 GE/ Comed in accordance with BWRVIP-41,"BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines", and determined to be acceptable for at least 24 months ofcontinued operation.

Reportable mdications were detected in the reactor intemal Core Spray piping welds, specifically, the downcomer elbow to thermal sleeve, weld (P4d) at the 110,

260*and 290* downcomers.

Core Spray Pipmg These indications were evaluated by Comed in accordance with BWRVIP-18, i

"BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines", and determirled to be acceptable for at least 48 months of continued operation.

21 of 25

Cdmmonwzalth Edison -

Quad Cities Nuclear Power Station P.O. Box 767 Unit 1

' Chicago,IL 60690 22710 206'" Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242 5.0 Repair / Replacement Summary 5.1.

NIS-2 Inder Table 5.1-1 Quad Cities Unit 1 NIS-2 Index Program Number Component EPN Work Request Number ASME XI Class Nurber 95-212 1-100134A 930066247-01 2

96-185 1-203-3B 930061018-01 1

97-040 1-1106-A 970041921-01 2

97-044 1 2301-45 970043427-01 2

g 97-062 1 1301-17 970047068-01 1

97-072 1-1001-36A 940105587-01 2

97-076 1-1001-36A 930066249-01 2

97-077 1 100136A 940105587-01

.2 97-103 1-0203-4H 970082995-01 1

97-104 1-0203-4C 970082998-01 1

97 105 1-0203-4G 970083011 01 1

97-106 1-0203-4E 970086489-01 1

97-107 1-0203-4D 970086447-01 1

97-108 1-02034F.

970086492-01 1

97-109 1-0203-4B 970086483-01 1

97 110 1-0203-4A 970086482-01 1

97-121 1-2300 970110578-01 2

97-125 1 1301 16 960034705-03 1

98-001 1-1301-16 960034705-01 1

98-002 1-1025-125 980000353-01 1

98-003 1 1025-125 980000353-02 1

98-004 1-0203-4D 970086447-02 1

98-005 1 2301-29 970125804-03 2

98-006 1-0301 980008084-01 2

98-007 1-1402-28B 970115354-01 2

98-008 1-0203-3A 970041151 01 1

98-009 l-2399-16 980008089-01 2

98-014 1-0300 980028387-01 1

98-017 1-1265-2" 980021522-01,3 1

98-018 1-0203-4F 980026249-01 1

98-019 l-0203-4E 980026254-01 98-020 10203-4B 980026256-01 1

98-021 1-0756 980026266-01 1

98-022 1-0203-4A 980021123-01 1

98-025 1-1400 980020099-01 1

98 033 -

1-3026-B 980026256-02 1

98-034 13026-E 980026254-02 1

98-035 1-3024-F 980026249-02 1

I 22 of 25 a....

Ccmmonwealth Edison Quad Cities Nuclear Power Station 1

~

P.O. Box 767 Unit 1 1

Chic!go,IL 60690 _

22710 206* Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242 f

Table 5.1-1 Quad Cities Unit 1 NIS-2 Index Program Number Component EPN Work Request Number ASME XI Class Number 98-036 1-3026 A 980021123-03 1

98-037 1-1402-35B 980022693-01 1

f 98-039 1-1106-B 980033792-01 2

98-040 1-2301-51 980022479-01 2

98-045 1-2301-34 980044515-01 2

98-051 1-0263-2-42B 980051285-01 1

98-076 1-1106A 980063567-02,03 2

98-079 l-0300-5457 980027855-01 1

98-080 1-0300-0627 970019145-02 1

98-081 1-0300-5027 970019145-01 1

98-082 1-0300-1023 970019145-03 1

98-083 1-0300-1035 970019145-04 1

98-084 1-0300-1047 970019145-05 1

98-085 1-0300-1443 970019145-06 1

98-086 1-0300-1823 970019145-07 1

98-087 1-0300-1855 970019145-08 1

98-088 1-0300-2227 970019145-09 1

98-089 l-0300-2231 970019145-10 1

98-090 1-0300-2235 970019145-11 1

98-091 1-0300-2623 970019145-12 1

98-092 1-0300-2659 970019145-13 1

98-093 1-0300-3431-970019145-14 1

[

98-094 1-0300-3811 970019145-15 1

1 98-095 1-0300-4235 970019145-16 1

98-096

'l-0300-4239 970019145-17 1

98-097 1-0300-4247 970019145-18 1

98-098 1-0300-4623 970019145-19 1

98-099 l-0300-5023 970019145-20 1

98-100 1-0300-5035 970019145-21 1

98-101 1-0300-5423 970019145-22 1

98-102 1-0300-5427 970019145-23 1

98-103 1-0300-5827 970019145 24 1

98-105 1-0203-3E 980016263-01 1

98-115 1-0200 980088960-01 1

98-117 1-1307-17 960038277-03 1

98-121 1-0756-4809 980061950-01 1

98-123 1 1402-35A 960083129-01 1

98-124 1-1307-17 960038277-01 1

98 138 1-0203-3B 970107392-01 1

98-139 l-1025-122 980024210-01 1

98-141 1 1025-123 980023968-01 1

98-146 1-0203-4D 980113021-01 1

98-147 1-0203-4C 980113020-01 1

98-148 1-0203-3A 980065960-01 1

98-151 1-0300-1827 980027857-01 1

98-154 1-0201'-M45 980023966 01 1

l.

l 23 of 25

Commonwecith Edison Qu-d Cities Nuclear Power Station P.O. Box 767 Unit 1 Chicago,IL 60690 22710 206*' Avenue North Commercial Service Date 2/18/73 Cordova,IL 61242 1

f Table 5.1-1 Quad Cities Unit 1 NIS-2 Index Program Number Component EP'N Work Request Number ASME XI Class Number 98-155 1-2301 71 980116146-02 2

98-158 1-0201-1 970124981-04 1

l'98-160 1-0202-B228A 960033587-02 1

98-162 1-0202-B228A 980120826-02' I

98-163 1-0202-A28A 980120638-02 1

98 K,

1-0201-A28-A 980120637-02 1

98-165 1-0203-4G 980113022-01 1

98-166 1-0203-4H 980113023-01 1

98 167 1-2305-67 980024516-01 1

98-168 1-2106A-1/2" 980120950-05 1

98-169

' l-2301-53 980010827-01 1

98-170 1-0204-B2 960091915-01 1

98-171 1-02106B-1/2 980120951-05 1

98-172 1-02310 970054567-01 2

98-173 1-0263-242B 980126319-01 1

98-174 1-0301 980126593-01 1

24 of 25

I Commonwealth Edison Quad Cities Nuclear Power Station P.O. Box 767 Unit 1 Chicago,IL 60690 22710 206* Avenue North CommercialService Date 2/18/73 Cordova,IL 61242 5.2.

NIS-2 Forms 3

1

[

25 of 25 l

FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by th: Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 95 212 WR# 930066247-01

,. Owner:

Commonwealth Edison Date: 02/12/1999 P.O. Box 767, Chicago,IL 60690 Sheet: 1 of 1 Umt:

1

. Plant:

Quad Cities Nuclear Power Statim Comed 22710 206th Ave. North, Cordova, IL 61242 hpair orsanaauon P.O. Na, Job No., ac.

Type Code Symbol Stamp:

M/A

. Work Performed by:

Quad Cities Nuclear Station Authonzation No.:

N/A 22710 206th Ave. North, Cordova, IL 61242 Expirauen Date:

N/A

. Identificanon of System Residual Heat Removal, Class 2

. (a) Applicable Construction Code: USAS B31.1 1967 Edition, Ncne Addenda, N/A Code Case (b) Applicable Edition of Section XI Utihzed ror Repairs or Replacements: 1989 Edition,.F,/A, Addenda, N/A Code Case Identification of Components Repared or Replaced, and Replacement Compments:

Name of Nanie of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Gate Valve Crane 33-1/2 N/A 1-1001-34A UNK Replacement No Description of Work: Replaced valve wedee. stem. voke as recuired by ECN s 1-00997M and WR.

'"-sts Cmductei Hydrostatic Pneumatic Nominal Operatmg Pressure Other @

Pressure 50 psi Test Temp. Ambient *F Remarks: Performed a LLRT.

CERTIFICATE OF COMPLIANCE fe certify that the statements made in this report are com:ct and this replacement conforms to the rules of ASME Code Section XI repair crreplaccar.n

1. of Code Symbol Stamp N/A -Comed 10CFR50 Ann B. O A ProPram

=rtificate of Authcrtzation No.

N/A Expiratim Date N/A Ned MAlkW mw 1st tn: w Lc h Date

$2Mvm,LV l&

19 A4 F

'p oner or o*ner speasnee Due e

<a l

CERTIFICATE OF INSERVICE INSPECTION 33 undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors y the State of Ibois. and employed by Hanford Steam Boiler insnection & hsurance Co of Hartford CT have inspected the mpon sts descnbed in this Owner's Report during the period

• /h /W to 2 Pf

, and state that to the best of my knowledge and lief, the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requirenents of the iME Code, Sectico XI.

signing this certificate, neither the inspector nor his employer makes any warranty, expressed a implied, conceming the exammations and corrective ures described in this Owner's Report. Furthemure, neither the Inspector ncr nis employer shall be liable in any manner for any personal iqjury or certy damage or aloss of any kind arising fnrn or connected with this inspection.

Coninissions U 97/

o M ' / 0 '- 19 'IT ite

FORM NIS-2 OWNERS REPORTCF REPAIR CR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 96-185 WR# 930061018-01 Owner Commonwealth Edison Date: 02/03/1999 P.O. Box 767, Chicago,IL 60690 Sheet: 1 of 1 Unit:

1 Plant-Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 Raper Orpm-F.O. No, Job No, ac.

Type Code Symbol Stamp:

N/.A Work Performed by:

Quad Cities Nuclear Station Autharizasson No.:

El6 22710 2%th Ave. North, Conlova,IL 61242 Expiration Date:

Nf6 Identification of System: Main Steam Class 1 (a) Applicable Construction Code: ASME Section III 1%5 Edition...S-L966 Addenda,.N!6. Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements:.1989. Edition,.N!A. Addenda, N/A Code Case identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

ReliefValve DresserInc.

BX00291 N/A 1-0203-3B N/A Replaced No Relief Valve Dresser Inc.

BK7070 N/A 10203-3B N/A i

Replacement No Descripti:n of Work: Replaced the relief valve and boltine as raanhed by the WR.

Te ts Conducted: Hydrostatic O Pneumatic 0 NominalOperating Pressure Other @

Pressure 100J psi Test Temp.191 'F Remarks r: rfonned VT-1 on boltina Performed a VT-2 during the system La*==e Test. 'Ihis form cunercadae the NIS-2 simeA 11/07/19% as reauired by PIF 1997-02950 CERTIFICATE OF COMPLIANCE

'e cerufy that the statements made in'this report are correct and this raal=~maar conforms to the rules of ASME Code Section XI repair or., _

me cf Code Symbol Stamp N/A - Comi:A 10FFR50 Ano B. O A Program stificate of Authorization No.

N/A Expiration Date N/A gned dN frf ^ *

• f4.ao Date GaWMF &

19 44 ror..

a

/

lowner or Uwner's Designee. Istle E 8 l

CERTIFICATE OF INSERVICE INSPECTION

, nad%=aad. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors s the State rf Illinois, and employed by Hartford Sea== baar inna & la=== ace Co.

of Hartford. CT have inspected the Niponents desenbed in this Owner's Report during the period j-17-T3 to / ? ?, and state that to the best of my knowledge and bef, thuwner has performed exammations and taken corrective mesures described in this Owner's Reput in accordance the requirements of the M5 Code,Section XI.

signing this certificate, neither the inspector nor his employer makes any warranty, exp:essed or implied, concernmg the exammations and corrective asures desenbed in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or l xrty damage or a loss of any kmd arising from or connected with this inspection.

II 7/

C ssions enspessors senaars

[

hanansi scent sisir. Pnmnse, and ~

n J. - P

• 19 0

FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section X1 OCAP 0307-20 Revision 6 CGE

}

Program # 97-040 WR# 970041921-01 l1. Owner:

Commonwealth Edison Date: 02-09-99 l

P.O. Box 767, Odcago,IL 60690 Sheet: I of 1 Unit:

1

[ Plant:

Quad Cities Nuclear Power Statim Comed j

22710 206th Ave. North, Cordova, IL 61242 Repau Orsamzauon P.O. No., Job No., ac.

Type Code Symbol Stamp:

UfA L Work Perfcrmed by.

Quad Cities Nuclear Station Authorizatim No.:

N/A 22710 206th Ave. North, Cordova, IL 61242 Erpiration Date:

Uf/A I. Identificauon of Systerrr Standby Liquid Control System, Class 2

. (a) Apphcable Constructim Code: USAS B31.1 1967 Edition, UgleAddenda, N/A,, Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition N/A Addenda, N/A Code Case

' Identification of Compments Repaired or Replaced, and Replacement Compments:

Neme of Name of Mfrs. Scr.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificatim Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Valve inlet Plug Canax CN 19446 N/A 1 1106-A N/A Replacement No 1 Trigger Assembly Canax S/N 79 N/A 1 1106-A N/A Replacement No Desmption of Werk: Replaced the tnreer assembly and plur after the surveillance as recuired by the WR.

Tests cmM~& Hydrostatic Pneumauc 0 NominalOperaung Prasure Other @

Pressure 1300 psi Test Temp. M*F

. Remarks: Performed a VT-2 durine the system functimal test.

CERTIFICATE OF COMPLIANCE Ve cenify that the statements made in this report are correct and this replacement cmforms to the ruirs of ASME Code Section XI repair or repiacement Spe of Code Symbol Stamp N/A - Comed 10CFR50 Are B. O A Procram ertificate of Authorizaticri No.

N/A Expiration Date N/A igned d)N fM-4enP 04AD Date f-E M v M # f f 19 99

/

Ow)cr or Owner's Demgace. Title ii CERTIFICATE OF INSERVICE INSPECTION the undersigned, holding a valid commission issued by the Natimal Board of Boiler and Picssure Vessel Inspectors y the State of mimis. and employed by Har' ford Steam Boiler Insnection & hsurunee Co of Hartford CT have inspected the enpanents described in this Owner's Report during the period 411') /67 to 2,h lo 4. and state that to the best of my knowledge and belief, 3

e owner has performed exammations and taken corrective measures described in this Owner's Report in accordance the requirements of the ASME ade,Section XI.

r signing this certificate, ceither the inspector nor his employer makes any warranty, expressed or implied, concernmg the examinations and corrective casures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any ma tner for any persmal injury or operty damage or a loss of any kind arising from or emnected ujth this inspection.

L d-fr Commiss!Als 7dj 4

- - ~ - - - -

M lhi ifN 19 ite

)

FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Sectior; XI QCAP 0307-20 Revisim 6 CGE Program # 97-044 WR# 970043427-01

1. Owner: Commanv ealth Edison Date:

11/06/98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed

,- 22710 206th Ave. Nath, Cordova,IL 61242 Repar orsa==uan P.O. Na. Joe Na. esc.

Type Code Symbol Stamp:

N/A

3. Work Pr4u use by:

Quad Cities Nuclear Station Authorization No.:

N_%

22710 206th Ave. Nwth Cordova,IL 61242 Expiration Date:

E%

4. Identification of System High Pressure Coolant lajection, Class 2

5. (a) Applic60le Construction Code: USAS B31.11%7 Edition, Egig,, Addenda, N/A Code Case (b) Applicable Editim of Section XI Utihzad for Repairs or Replacements: 1989 Edition. E%. Addenda, Ef% CodeCase

6. Identification of Componets Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replamd, or Code No.

Replacement Stamped (Yes or No)

Check Valve Triantric Div.

Serial # J4 N/A 1 2301-45 N/A Replacemmit No

7. Description of Work: Replaced check valve by boltine as reouired by WR.

. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other @ Pressure 2.3 psi Test Temp. j}6 *F 3

Remarks: Performed VT-2 durine pressure test.

}

CERTIFICATE OF COMPLIANCE Ve certify that the statements made in this report are correct and this replacement confcrms to the rules of ASME Code, Sectice XI repen arsi rype of Code Symbol Stamp N/A - ComF410CFR50 Aon B. O A Program Macate of Authorizatico No.

N/A Expiration Date N/A igned M nd t'af..

1r*4 Map tsAo Date hhwada 7 1948 y

Oujer er Owaar s Dengasc. Intle 8

I l

CERTIFICATE OF INSERVICE INSPECTION the undersigned, holding a valid cxrrrnission issued by the National Board of Boiler and Pressure Vessel Inspectors the State of minsa. and employed by Hartimd Steam Bdler inenenian & Insurance Co.

of Hartfwd. CT have inspected the ts described in this Owner's Report during the period L/u/F7 to ///9/ff

, and state that to the best of my knowledge and lief, the owner has i.Jau.4 exarranations and taken corrective measures described in this Owner's Report in accordance the requirements of the SME Code Section XI.

y signing this certificate. neither the inspector nor his employer makes any warranty, expressed w implied, concerning the exarrunations and rrective measures described in this Owner's Repcrt. Puren neither the Inspector nor his employer shall be liable in any manner fw any

' rscnal irsury or property damage or a loss of any kind arising from or manected with this inspection.

e

'd Corrknissions

/F c

b,/#

-~

ble 19 U l

FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Secuan XI

)

QCAP 0307-20 Revision 5 CGE Program # 97-062 WR# 970047068-01 1 Owner: Commonwealth Edison Date:

11/04/98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1 olant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Ccrdova, IL 61242 Repar ors.= muon to. sa. Jab sa. etc.

Type Code Symbol Stamp:

N/A

3. Work Pafwand by.

Quad Cities Nuclear Station Authorization No.:

E/6 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

4. Identificatim of System-Peacrer Core Isolation Cooling, Class 1

5. (a) Applicable Construction Code: USAS B31.1 1%7 Editian, None Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition,,H/&,, Addenda. N/A Code Case

6. Identification of Cornpanents Repaired or Replaced, and Replacement Compculents:

Name of Nameat Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Gate Valve Crane N/A N/A 1-1301-17 N/A Reparted No

7. Description of Wcrk: Laoped/ machined the bannet. disc and valve seat. and tack welded voke to the valve body.

ests Conducted: Hydrostatic Pneumatic O Nominal Operating Pressure Othe @ Prt.ssure 1009 psi Tes6 Temp. 210 *F

. Remarks: Performed MT of voke to body tack welds & VT-2 inspection during class I leak test.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair conforms to the rules of ASME Code, Sectica XI per er.--/

Type of Code Symbol Stamp N/A - CnmM 10CFR50 Ano B. O A Prorram Mficate of Authorization No.

N/A Expiration Date N/A signed

' N 4 din d re c, TfJ uw Ino,Date Adm/6* k:w- ~7 19e A V

Odeur or Owaar's Designac. Tale i

CERTIFICATE OF INSERVICE INSPECTION h the undersigned. holding a valid commission issued by the Natimal Board of Boiler and Pressure Vessel Inspectors nd the State of 111ias and eniployed by Hartford Steam Boiler lamection & Insuraice Co.

of Hartford. CT have inspected the unpanents described in this Owner's Report during the period V/u h r to e h e/ W

, and state that to the best of my knowledge and

lief, the owner has puh.ud exarrunations and taken corrective measures described in this Owner's Report in accordance the r% ts of the sSME Code.Section XI.

y signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied. concemmg the exammations and xrective measures described in this Owner's Report. Purthermore, neither the inspector nor his employer shall be liable in any manner for any onal injury or property damage or a loss of any kind arising frorn or connected with this inspection.

Corrimissions

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FORM NIS-2 OWNERS REPORT OF REPAIR CR REPLACEMENT l

As Required by the Provisions cf ASME Code Section XI I

QCAP 0307-20 Revision 6 CGE

~

Program # 97-072,076,077 WR# 940105587 & 930066249

1. Owner: Commonwealth Edison Date: 02/09/1999 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 I. Plant-Unit:

1 2

Quad Cities NuclearI war Station Comed 22710206th Ave. North,Cordova,IL 61242 Mar ursanusuon r.u. no., son no., cic.

I 3. Work Performed by:

Type Code Symbol Stamp:

N/A Quad Cities Nuclear Station Authorization No.:

N_/A 22710206th Ave.Nonh,Cordova,IL 61242 Expiration Date:

N/A

4. Identification of System: Residual Heat Removal, Class 2.

I. (:) Applicable Construction Code:

5 USAS B31.1.1967 Edition, None Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A Code Case

6. Identification of Components Repatred or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l

. Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code I

No.

Replacement Stamped (Yes or No)

Globe Valve Crane CV-09022-N/A 1-1001-36A 1968 Replacement No l

8-06 l7. Description of Work: Modifv valve by machhine valve body to accept new anti-cavitation trim and replaced bonnet as reauired by I 7#04-00994M and WR's.

8. Tests Conducted: Hydrostatic [

Pneumatic 0 Nominal Operating Pressure Z Other O Pressure J,B psi Test Temp. Ambiant *F

9. Remarks: Performed VT-2 system leakare test.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code,Section XI repair or replacement Type cf Code Symbol Stamp N/A -Comed 10CFR50 Ann B. O A Program Certificate of Authorization No.

N/A Expiration Date N/A Signed

/1I//lMd af, Af ue Im Date tleeAgV 9 19 M

{ " gwnct of Owner's Designec, fede

=a i

CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the N%..{ Board of Boiler and Pressure Vessel Inspectors and the State of Illinois. and employed by Hartford Steam Boiler Inspection & Insurance Co of Hartford. CT have inspected the components described in this Owner's Report during the period F19-f9 to 2

• 77

• f f, and state that to the best of my knowledge and helief. the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the ASME Code,Section XI.

t (By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective isures described in this Owner's Report. Furthermore. neither the inspector not his employer shall be liable in any manner for any personal injury or goperty damage or a loss of anu kind arisin from or connect &d with this inspection.

Commissions o

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I FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisi:ns of ASME Code Section XI QCAP 0307 20 Revision 5 CGE Program # 97-103 WR# 970082995-01 1

1. Owner:

Commonwealth Edison Date: 06-03-98 P.O. Box 767. Chicago,IL 60690 Sheet: I of 1 Unit 1

.:.. at:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North,Cordova,IL 61242 xepan organuanon ru. no.. ;oo r o., cu Type Code SymbolStamp:

E/A_

3. Work Performed by:

Quad Cities Nuclear Station Authorization No.:

N/A 22710 206th Ave. North,Cordova,IL 61242 Expiration Date:

N/A

t. Identihcation of System: Main Steam, Class 1

5. (a) Applicable Construction Code: ASME Section III 1965 Edition, S-l%6 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition, _E/&, Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Safety Valve Consolidated BK 6249 N/A l-0203-4H UNK Replaced Yes Safety Valve Consolidated BK 6251 N/A l 0203-4H UNK Replacement Yes

7. Description of Work: Reelaced the Main Steam Safety Valve in accordance with WR.

• s Conducted: Hydrostatic O Pneumatic 0 NominalOperating Pressure O Other G Pressure.LOQ psi Test Temp.2.2 'F Q

. Remarks: Performed VT-l-1 insoection on inlet boltine.

&ned VT-2-1 durine Class! System Lenhoe Test.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this Replacement conforms to the rules of ASME Code,Section XI repair orreplacement Type cf Code SymbolStamp N/A - Comed 10CFR$0 Ano B. O A Piciriuii "ertificate ef Authorization No.

N/A Expiration Date N/A igned Od4Ak

raE, "r." ma' Date dvut. D 1946

(/

0+cr orUwntr's Desagnec, nue CERTIFICATE OF INSERVICE INSPECTION

, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors x1 the State cf Illinois. and employed by Hartford Steam Boiler Insocetion & Insurance Co of Hartford. CT have inspected the nponents described in this Owner's Report during the period

/- 3-T&" to 4 - /6-W, and state that to the best of my knowledge and clief. the owner has perturmed examinations and taken corrective measures described in this Owner's Report in accordance the requirements LSME Code,Section XI.

y signig this certificate, neither the inspector nor his employer makes any warranty, expressed or implied. conceming the examinations and correc

,casures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any p roperty damage or a lo s of any kind arising from or connected with this inspection.

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FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions cf ASME Code Section XI QCAP 0307 20 Revision 5 CGE Program a 97104 WRa 970082998-01

1. Owner:

Commonwealth Edison Date: 06-03-98 P.O. Box 767, Chicago 4 60690 Sheet: 1 of 1 Unit: 1 2

it:

Quad Cities Nuc% rower Station Comed 22710206th Ave. North,Cordova,IL 61242 xepair ursanaanon r.o. r.o..;ou r o cw Type Code Symbol Stamp:

Ff_6

i. Work Performed by:

Quad Cities Nuclear Station

/.uthorization No.:

N/_6 22710 206th Ave. North.Cordova,IL 61242 Expiration Date:

EL6

l. Identification of System: Main Steam, Class 1

5. (a) Applicable Construction Code: ASME Section III 1965 Edition, S-1966 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Safety Valve Consolidated BK 7163 N/A 1-0203-4C UNK Replaced Yes Safety Valve Consolidated BK 6531 N/A l-0203-4C UNK Replacement Yes

7. Description of Work: Reolaced the Main Steam Safety Valve in accordance with WR.

's Conducted: Hydrostatic 0 Pneumatic O NominalOperatingPressure O Other 2 Pressure 10H psi Test Temp.2R 'F

. Remarks: Performed VT-I-1 insoection on inlet boltine Performed VT-2-1 durine Class 1 System Leakare Test.

CERTIFICATE OF COMPLIANCE Ve certify that the statements made in this repon are correct and this Reolacement conforms to the rules of ASME Code.Section XI Itpaar of TCplacement rype of Code SymbolStamp N/A -Comed 10CFR50 Ano B. O A Procram Certificate cf Authorization No.

N/A Expiration Date N/A j ned M

g gal.

u*e im Date b.e. 4 194A y

>Whc] or UWnct iDesagnee; Iaue s-E CERTIFICATE OF INSERVICE INSPECTION

, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors the State cf Illinois. and employed by Hartford Steam Boiler Inspection & Insurance Co of Hartford. CT have inspected the ponents described in this Owner's Repon durinF the period to

, and state that to the best of my knowledge and lief, the owner has performed examinations and tak6n corrective measures described in this Owner's Report in accordance the requirements of kSME Code,Section XI.

y signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corre casures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any perso ropeny damage or a loss of any kind arising from or connected with this inspection.

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FORM NIS-2 OWNEP.S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisi:ns ef ASME Code Section XI QCAP 0307-20 R; vision 5 CGE Program n 97-105 WR# 970083011-01 Owner:

Commonwealth Edison Date: 06-03-98 P.O. Box 767, Chicago,IL 60690 Sheet: 1 of 1 Unit:

I ut:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North,Cordova,IL 61242 Kepair ursanuauon r.v. 30.. J.o so etc Type Code Symbol Stamp:

N/A

Work Performed by:

Quad Cities Nuclear Station Authorization No.:

Ff6 22710 206th Ave. North, Cordoc. IL 61242 Expiration Date:

F,f6 Identificzion of System: Main Steam, Class I (a) Applicable Construction Code: ASME Section III 1965 Edition, S-1966 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A Code Case identification of Components Repaired or Replaced, and Replacement Components:

Namecf Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Safety Vrive Consolidated BK 7167 N/A 1-0203-4G UNK Replaced Yes Safety V;Ive Consolidated BK 6529 N/A l-0203-4G UNK Replacement Yes Description of Work: Replaced the Main Steam Safety Valve in accordance with WR.

's Conducted: Hydrostatic Pneumatic NominalOperatingPressure O Other 5 Pressure.19.Q psi Te-t Temp. 2.g *F Remarks: Performed VT-1-1 inspection on inlet boltine Performed VT-2-1 durine Class i System Leakace Test.

CERTIFICATE OF COMPLIANCE G ecrtify that the statements made in this report are correct and this Replacement conforms to the rules of ASME Code.Section XI repair or replaccrnent ype of Code Symbol Stamp N/A - Comed 10CFR$0 Ano B. O A Procram xtificate cf Authorization No.

N/A Expiration Date N/A gned NOM

mm6,

/n *

• La4o Date d o u e_ 4 1948

' ~ Owr)ct or Owner s Ucsignec, hec' CERTIFICATE OF INSERVICE INSPECTION undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors the State e f Illinois. and employed by Hartford Steam Boiler intnection & Insurance Co of Hart ord. CT have inspected the f

sponents described in this Owner's Report during the period

/- 4 4'Y to

/ /f-VY, and state that to the best of my knowledge and lief, the cwner has performed examinations and taken corrective measures desenbed in this 0.<ncr's Report in accordance the requireme iME Code,Section XI.

bgning this certificate, neither the inspector nor his employer makes any warranty, expressed or implied. conceming the examinations and co Esures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any mann petty damage or ajoss of any kind arising from or connected with this inspection.

Compiissions bN

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s FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP0307 20 Revision 6 CGE Program # 97-106 WR# 970086489-01

. Owner:

Commonwealth Edison Date:

12 22-98 P.O. Box 767, Chicago, IL 60690 Sheet: I of 1 Unit: 1

2. Plant-Quad Cities Nue: car Power Station Comed 22710 206th Ave. North. Cordova, IL 61242 R=pur orsanusuon P.O. No.. Job No., ac.

Type Code Symbol Stamp:

N/A

3. Work Fwfu ua by-Quad Cities Nuclear Station Authcrizaum No.:

M/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date EA

4. Identification of System Main Steam, Class 1

5. (t) Applicable Constmetion Code ASME Sect III 1%5 Edition, S-19% Addenda, E/. Code Case A

(b) Applicable Editim of Section XI Utihzed for Repairs or Replamments: 1989,Editim, N!A.Addeda, and N/.6. Code Case o

5. Identification of Components Repaired or Replaced, and Replacement Compcments:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificaticn Built Replaced, or Code No.

Replacement Statnped (Yes or No)

Safety Valve Consolidated Valve BK6318 N/A 1-0203-4E UNK Replamd Yes Safety Valve Consolidated Valve BK7163 N/A 1-0203-4E UNK Replamment Yes

7. Description of Work: 'The Safety Valve and bottine was replaced in accordance with the WR.

.. Tests Ccnducted: Hydrostatic Pneumatic Nominal Operating Pressure Other @

Pressure 1014 psi Test Temp.2J2 *F P. Remarks: Performed VT-2 dortnr the Class I f_emiraoe Test.

Pwfu ud VT-1 on replacement boltine.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this repurt are correct and this replacement cmforms to the rules of ASME Code.Section XI sepair orreplacement Type of Code Symbol Stamp N/A - Comed 10CFR50 Ann B. O A Program

".'ertificate of Authcrizatics No.

N/A Expiration Date N/A signed M w-ter Asa em Date Mrs.ae 46 19 en y

IPwmer or Owmer~ s Demgnes. Tide CERTIFICATE OF INSERVICE INSPECTION the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors ud the State of minois. and employed by Hartford >mm Boiler Insnection & Insurane Co.

of Hartford. CT have inspected the nmponents described in this Owner's Report during the period o s"-9 ~7 to /-Y 99, and state that to the best of my knowledge and

lief the owner has performed exammations and taken corrective measures described in this Owner's Report in acccrdance the requirements of the SME Code,Section XI.

y signing this certificate, neither the inspector nor his employer makes any warrapty, expressed or implied, concerning the exammations and corrective wasures described in this Owner's Report. Furthermcre, neither the Inspector nor his employer shall be liable in any manner for any personal irdury or perty damage or a loss of any kind arising from or connected with this inspection.

4O Cor'unissions Y8Fe ?

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions rif ASME Code Section XI OCAP 0307-20 Revision 6 CGE Program # 97-107 & 98-004 WRW 970086447-01 & 02

1. Owner:

Commonwealth Edison Date: 07/21/98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Powu Station Comed 22710 206th Ave. North, Cordova,IL 61242 kcPar Orgammon P O. No., Job No., etc.

Type Code Symbol Stamp:

N_/2

3. Work Performed by:

Quad Cities Nuclear Station Authorization No.:

U_/6 22710 2%th Ave. North, Coedova, IL 61242 Expiration Date:

FfA

4. Identification of System: Main Steam, Class 1

5. ( ) Applicable Construction Code: ASME Section UI 1%5 Edition. Summer 1966 Addenda N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements:.].9.H9. Edition. E!A. Addenda, E!.A. Code Case 9

6. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat1 Other Year Repaired.

ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Safety Valve Dressor BK 7155 N/A 1-0203-4D 1%5 Replaced Yes Safety Valve Dressor BK 6295 N/A l-0203-4D 1%5 Replacement Yes

7. Description of Work: Reolaced the Saferv Valve. machined eine flance. and reolaced bo! ting Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Q Pressure IQQ1 psi TestTemp.21Q 'F

9. Remarks: Performed VT-1-1 inspection on inlet boltine. VT-3-1 on oice flance after machinine.

Performed VT-2-1 durine Class 1 System Lenkn=e Test.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this Jenlacement conforms to the rules of ASME Code,Section XI repair or replacernen Type cf Code Symbol Stamp N/A - Comed 10CFR50 App B. O A Program Certificate of Authorization No.

N/A Expiration Date N/A Signed rb J

Dwner or Owner's Designee. Tide Date MYU 194 A shf.

f6iffe N /*6

/

CERTIFICATE OF INSERVICE INSPECTION

=, the undersigned, holdmg a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors bnd the State cf Illinois. and employed by Hartford Steam Boiler Insoeetion & Insurance Co of Hartford. Cr have inspected the emponents desenbed M this Owner's Report during the period 11% 97 ~ to P'4 'lI, and state that to the best of my knowledge and clief, the owner has performed exarninations and taken corrective measures described in this Owner's Report in accordance the requirements of the MIME Code Section XI.

By sigmng this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, conceming the exanunations and corrective neasures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be lis.ble in any manner for any personal injury or w dama r a loss of any kind arising from or connected with this inspection.

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4 19 i8

FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Pronsions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 97-108 WR# 970086492-01 Owner:

Commonwealth Edison Date:

12-22 98 P.O. Box 767 Chicago,IL 60690 Sheet: I of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Statim Comed 22710206th Ave. North,Cordova,IL 61242

%=r ursaamon P.O. Na, Job No., ac.

Type Code Symbol Stamp:

M

l. Work Psh d by-Quad Cities Nuclear Station Authori:atim No.:

M 22710206th Ave. North, Cordova, IL 61242 Expiration Date:

M

l. Identificauan of System Main Steam. Class 1

i. (a) Applicable Construction Code: ASME Smt III 1%5 Edition, E:L966,,,, Addenda, N/A Code Case (b) Applicable Editim of Section XI Utilized for Repairs or Replacements: 1989, Edition, N.QLAddeda, and N/.6 Code Case

4. Identification of Compcnents Repaired or Replaced, aad Replacement Compments:

Name of Name of Mfrs. Ser.

Nat'l

. Other.

Year Repaired.

ASME Component Mfr.

No.

Bd.

Identification Built Reolaced, or Code No.

Replacement Stamped (Yes or No)

Safety Valve Consolidated Valve BL2471 N/A 1-0203-4F UNK Replaced Yes Safry Valve Cmsolidated Valve BK6249 N/A 1-0203-4F UNK Replacement Yes

' Descnption of Werk The Safety Valve and bolting was replaced in accordance with the WR.

. Tests Cmducted: Hydrostatic Pneumatic Nomiral Operating Pressure Other @

Pressure 1014 psi Test Temp.212 'F

. Remarks: Performed VT-2 during the Class 1 i rakare Test.

Performed VT 1 on replaced bolting.

CERTIFICATE OF COMPLIANCE Ve cenify that the statements made in this report are correct and this replacement confonns to the rules of ASME Code.Section XI repair orspiacemen rype of Code Symbol Stamp N/A - Comed 10CFR50 Ann B. O A Program httficate of Authorizatim No.

N/A Expiration Date N/A igned e d U m:st.,

f'er h-*

• s Date Cut,ammhra 'la 19 4A

{ " IOwaar or Owner's Demgnet, Tatle-CERTIFICATE OF INSERVICE INSPECTION the undersigned. holding a valid cmunission issued by the Naticeal Board of Boiler and Pressure VesselInspectors si the State of Ihoit 2 and errplopd by Hartford Steam Boiler Insocction & Insurance Co of Hartford. CT have inspected the unponents described in this Owner's Repat during the period o-r47 to / f9-f4

, and state that to the best of my knowledge and clief. the owner has performed examinations and taken corrective rneasures described in this Owner's Report in accordance the requirements of the SME Code.Section XI.

y signing this certificate, neither the inspector nor his emplopt makes any warranty expressed cc implied, concerning the exarranaticris and corrective

.asures described in tids Owner's Report. Furtbennare, neither the Inspector nor his emplopt shall be liable in any rmaner for any personal injury or perty dannge or a loss of any kind arising from or emnected with this inspection.

M f. bib Codnissions Md./

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FORM NIS 2 OWNERS REPORT OF REPA1R OR REPLACEMENT As Requ red by the Provisions of ASME Crxle Section XI 1

QCAP 0307 20 Revision 6 CGE Program # 97109 WR# 970086483-01 Owner: Commonwealth Edison Date:

12 22-93 P.O. Box 767, Chicago IL 6%90 Sheet: I of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Str.ucn Comed 22710 206th Ave. North, Cordova IL 61242 Res=1 orzmuauon P.O. bo.. Job No.. etc.

Type Code Symbol Stamp:

UfA

3. Work Performed by:

Quad Cities Nuclear Station Authorizatim No.:

F.a 22710 206th Ave. North. Cordova. IL 61242 Expiration Date:

FM

t. Identification of System Main Steam. Class 1 F. C) Applicable Construction Code: ASME Sect III 1%5 Edition, S-1966 Addenda, F]&, Code Case (b) Applicable Editim of Section XI Utihred for Repairs or Replacements: 1989,. Edition NA/ Addenda, and N./.6. Code Case

5. Identification of Compments Repaired or Replaced, and Replacement Compments:

Name of Name of Mfrs. Ser-Nat'l Other..

Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificatim Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Safety Valve Consohdated Valve BL1132 N/A 1-0203-4B UNK ReplaM Yes Safety Valve Constlidated Valve BK7155 N/A 1-0203-4B UNK Replacement Yes 1 Description of Work: The Safety Valve was replaced as reoutred by the WR.

Tests Cmducted: Hydrostatic Pneumatic O Nominal Opwating Pressure Other @

Pcessure 1014 psi Test Temp. 212 'F

' Remarks: Performed VT-2 dunne the Class 1 leakare Test.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement confams to the rules of ASME Code.Section XI sepair orreplacement Type of Code Symbol Stamp N/A -Comed 10CFR50 Ano B. O A Program

'ertificate of Autharization No.

N/A Expiration Date N/A iigned IM

<-*z At se h Date M_'e-9 dB 19 48

[~

l Owner or Owner s Desagnee. Tade CERTIFICATE OF INSERVICE INSPECTION l the undersigned. ho. Jing a valid cornmission issued by the National Board of Boiler and Piessure Vessel inspectors the State of tilinois. and employed by Hartford Steam Boiler Insnection & Insurance Co.

of Hartford. CT have inspected the ents described in this Owner's Report during the period

>>$~ - f i to /- M-9f, and state that to the best of my knowledge and belief, the owner has performed exammations and taken ccm:ctive measures described in this Owner's Report in accordance the requirements of the

,SME Code.Section XI.

y signing this certificate. neithen the inspector nor his employer makes any warranty. expressed or implied. concerning the exarranations and corrective wasures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or perty damage or a loss of any kind arising from or connected with this inspection.

dr( O Corrrnissions M443

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Prograrn # 97110 WR# 970086482-01 Owner: Commonwealth Edison Date:

12-22-98 P.O. Box 767 ChicaFo,IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 hpur Orgazauon P.O. No.. Job No., uc.

Type Code Symbol Stamp:

N/A

3. Work Performed by-Quad Cities Nuclear Station Authorization No.:

N/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

6. Identification of System: Mam Steam, Class 1

5. (:) Applicable Construction Code: ASME Sect III 1%5 Edition, S-1966 Addmda, N/A Code Case (b) Applicable Edition of Sectim XI Utilized for Repairs or Replacemmts: 1989.Editicrt, N!A. Addenda, and N!6 Code Case E. Identificaticut of Compments Repaired or Replaced, and Replacement Compments:

Name of Name of Mfts. Ser.

Nat'l

. Other -

Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificatam Built Replaced, a Code No.

Replacement Stamped (Yes or No)

Saf y Valve Consolidated Valve BL1120 N/A 1-0203-4B UNK Replaced Yes Saf 'y Valve Consolidated Vnive BK7167 N/A 10203-4B UNK Replacement Yes P. Description of Wak The Safety Valve and bolting was renlaced in accordance with the WR.

. Tests Conducted: Hydrostatic 0 Pneumatic O NominalOperatmg Pressure Other Q Pressure 1014 psi Test Temp. 2)l F

. Remarks: Performed VT-2 durme the Class 1 Leakare Test.

Performed VT-1 on replacement bottine.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code,Section XI arpair orreplacement Type of Code Symbol Stamp N/A -Comed 10CFR50 Arv B O A Program

ertificate of Authcrtzation No.

N/A Expiration Date N/A

,igned Adlib nr W %

Date bs -

--a sb 19 48

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pwner or Owner a Designee. IstIs CERTIFICATE OF INSERVICE INSPECTION j the undersigned holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors nd the State of tilinois and employed by Hartford Steam Boiler Insoeetion & Insumnce Co of Hartford CT have inspected the xnponents described in this Owner's Report during the period r.th /M7 to /-24 '/(,_, and state that to the best of my knowledge and clief. the owner has performed exammations and taken corrective rneasures described in this Owner's Report in accordance the requirements of the SME Code.Section XI.

y signing this certificate, neither the inspector nor his employer makes any warranty expressed or implied. conceming the examinations and contetive

• asures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or perty damage u a loss of any kind arising from or connected with this inspectim.

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by thi Provisions of ASME Code Section X1 QCAP 0307-20 Revision 6 CGE Program # 97-121 WR# 970110578-01,970103408-01 S Owner: Commonwealth Edison Date:

10/21/98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1 S. Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North. Cordova, IL 61242 kcPau Orgamnuon P.R tm. M Na, ac, Type Code Symbol Stamp:

NM

@. Work Performed by Quad Cities Nuclear Station Authorization No.:

NB 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

3. Identification of System High Pressure Coolant injection. Class 2 1 (t) Apphcable Construction Code: USAS B31.1 1967 Edition, N/A Addenda, N/A CodeCase (b) Applicable Edition of Section XI Utihzed for Repairs or Replacements: 1989 Editim, N/A Addenda, N/A CodeCase

). Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat1 Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Pipe Support N/A N/A N/A SI # 783A91 UNK Replacement No

. Description of Work: Jeplaced U-Bolt on a 2" Dia pipinc as reouired by the WR

. Tests Cmducted: Hydrostatic Pneumatic Nominal Operatmg Pressure Other C Pressure __ psi Tat Temp. _ 'F

. Remarks: None CERTIFICATE OF COMPLIANCE 5e cenify that the statements made in this trport are cTrect and this replacement confoms to the rules of ASME Code,Section XI mper w nptscemes Type of Code Symbol Stamp N/A - Comed 10CFR50 App B. O A Procram bertificate of Authorization No.

N/A Expiration Date N/A gned

}W[ SOL 16f' MAP LEAD Date Curvyc Gl 19 96 j

y ' 04m:r w owmr s Demgme, hue CERTIFICATE OF INSERVICE INSPECTION

! the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors

% the State of minois,,, and employed by Hartford Steam Boiler Insoection & Insurante Co of,,,,,ligtford. CT have inspected the

],,t.7(/f")

to i/18/4 4, and state that to the best of my knowledge and

/

omponents described in this Owner's Report during the period

! lief. the owner has performed exammations and taken corrective measures described in this Owner's Report in a-hce the requirements of the

,SME Code,Section XI.

y signing this certificate, neither the inspector nx his employer makes any warranty, expressed or implied, concerning the examinations and Errective measures described in this Owner's Report. Purthermore, neither the inspector nor his employer shall be liable in any manner for any ersonal injury or propeny damage or a loss of any kind arising from or connected with this inspection.

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Nancent DounL Ems. Pnmara and 8 - -

late 40 19 99 t/

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provinons of ASME Code Section XI QCAP 0307-20 Revision 6 CGE j

ProFram # 97125 & 98-001 WR# 960034705-01.03

' Owner:

Comrnanwealth Edison Date:

10-20-98 P.O. Box 767, Chicago, IL 6%90 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 Repaa orsanamuon P.O. bo-, Job bo, etc.

Type Code Symbol Stamp:

Ji/6

3. Work Performed by-Quad Cities Nuclear Station Authortzatim No.:

N/A 22710 2%th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

4. Identification of System Reactor Core Isolation Cooling, Class 1

5. (a) Appbcable Construction Code: USAS B31.11%7 Edition, & Addeuda N/Ar CodeCase.

(b) Applicable Edition of Section XI Utihzed fx Repairs or Replacements: 1989 Edition, N/A Addenda, N/A Code Case S. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Net'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificatim Built Replaced, or Code No.

Rep'acement Stamped (Yes or No)

Valve Disc Model Crane C6219 N/A 1-1301-16 UNK Replacement No

1. 783U

' Desenption of Work: Overhauled the Valve # 1-1301-16. replaced disc. tack welded voke to the body as reouired by the WR I. Tests Conducted-Hydrostatic Pneumatic Nominal Operating Pressure Other C Pressure 1009 psi Test Temp.210 *F

>. Remarks: Performed a VT-2-1 dunne Class 1 System Leakare Test CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to tbc rules of ASME Code.Section XI repaar orsupisceanent Type of Code Symbol Stamp N/A - Comed 10CFR50 Ann B. O A Procram Mrtificate of Authwization No.

N/A E::piration Date N/A iigned etdl N e nr4sta.F fAs Date

/btn=rz 10 1916 y

Qwact orUWnct s Desagnee. Inde CERTIFICATE OFINSI

'CE INSPECTION the undersigned, holding a valid commission issued by the National Board of Aer end Pressure VesselInspectors

, the State of minnis and employed by Hartford Steam Boiler insocction & Insurance Co of Hutford. CT have inspected the

• l.2 L. l$ to

, and state that to the best of my knowledge and nrnponents described in this Owner's Report dunng the period ilief. the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the SME Code,Section XI.

g signing this certificate. neither the inspector nor his employer makes any warranty, expressed or implied, concerning the exammations and corrective casures described in this Owner's Report. Purthennare, neither the inspector nor his employer shall be liable in any manner for any personal irsuty or openy damage or a loss of any Lind arising from or connected,with this inspection.

d4O Commissions N

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FOlM NIS,2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI OCAP 0307-20 Revision 6 CGE j

Program # 98-002 & 98-003 WR# 980000353-01 & 02 I

1. Owner: Commonwealth Edison Date: 07/22/98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 2 Unit:

1 LPJtat:

Quad Cities Nuclear Power Station Comed 22710206th Ave. North.Cordova.IL 61242 Repasr organsmon P O No.. Job ho etc.

Type Code Symbol Stamp:

N/A

l. Work Performed by:

Quad Cities Nuclear Station Authorization No.:

N/A 22710 206th Ave. North.Cordova.IL 61242 Expiration Date:

N/A

l. Identification of System: Residual Heat Removal. Class 1

' (a) Applicable Construction Code: ASME Section III 1974 Edition. S-1974 Addenda, 1644 & 1651 Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: _12L9_ Edition. E/A Addenda, E!A Code Case

b. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year J epaired.

ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Mechanical Pacific Scientific 161 %

N/A 1025-M-102 1981 Replaced Yes Snubber A&B Mechanical Pacific Scientific 11709 N/A 1025-M-102 1980 Replacement Yes SYubber A&B Description of Work: Removed and replaced with a snare snubber as reauired by the WR.

. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other O Pressure E/6 Psi TestTemp.E!A *F

. Remarks: Performed a VT-3/4-1 on the replacements.

No cressure testine reauired.

CERTIFICATE OF COMPLIANCE Ve cenify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code.Section XI repair oraplacenent rype ef Code Symbol Stamp N/A - Comed 10CFR50 Ano B. O A Program

' rtificate cf Authorization No.

N/A Expiration Date N/A e

igned M,

{47 MavP Ints Date SL4 'Zk 19 90 y

Qwner or owner's Dcugnee. Titic CERTIFICATE OF INSERVICE INSPECTION the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors k the State of Illinois. and employed by Hanford Steam Boiler Inspection & Insurance Co.

of Hanford CT have inspected the Lmponents desenbed in this Owner's Report during the penod /-Io-9C to 7-1Y-48. and state that to the best of my knowledge and tlief, the cwner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the SME Code.Section XI.

v signmg this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, conceming the examinations and corrective ures described in this Owner's Report. Furthermore, ncider the inspector nor his employer shall be liable in any manner for any personal injury or openy damage or oss of any kind arising from or connected with this inspection.

Commissions IL 17 I o

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT (Supplement)

As Required by the Provisions of ASME Code S:ction XI Program # 98-002 & 98-003 WR# 980000353-01 & 02

1. Owner:

Commonwealth Edison Date:

07/22/97 P.O. Box 767, Chicago, IL 60690 Sheet: 2 of 2 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North,Cordova,IL 61242 Repair orgamzanon P.O. No Job No.. cic Type Code Symbol Stamp:

FL/6

3. Work Performed by:

Quad Cities Nuclear Station Authorization No.:

N/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

Fj/A

4. Identification of System: Residual Heat Removal. Class !

5. (t) Applicable Construction Code: ASME Section III 1974 Edition, S-1974 Addenda, 1644 & 1651 Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements:.123.9. Edition.Ff2L Addenda,.F//A Code Case 9

6. Identification of Components Repaired or Replaced, and Replacement Components: Continued Name of Name of Mfrs. Ser.

Nat1 Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Mechanical Snubber Pacific Scientific 30695 N/A 1025-M-102 1991 Replaced Yes A&B Mechanied Snubber Pacific Scientific 7333 N/A 1025-M 102 1979 Replacement Yes A&B l

l l

l

FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-005 WR# 970125804-03

l. Owner: Commonwealth Edison Date:

10/21/98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

I LPlant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 lovar orsamuuoe r.o. m. Job tm. cis.

Type Code Symbol Stamp:

,N.B L. Work Perfuiusd by-Quad Cities Nuclear Station Authorization No.:

N/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

Ed L. Identification of Systent High Pressure Coolant Injectim, Class 2

. (a) Applicable Cmstruction Code: USAS B31.11%7 Edition, EM,, Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A CodeCase

,. Identificatim of Components Repaired or Replamd, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, cr Code No.

Replacement Stamped (Yes or No)

Control Valve Copes - Vulcan N/A N/A 1 2301-29 UNK Repatred No

. Desaiption of Woric Welded Care Retainer in Valve 1-2301-29 as recuired by the WR

. Tests Cmducted-Hydrostatic 0 Pneumatic 0 Nominal Operatmg Pressure Other Pressure,,,,,,,, psi Test Temp. _,,,, F

. Rem % N,one CERTIFICATE OF COMPLIANCE Ve certify that the statements made in this report are correct and this repair. conforms to the ntles of ASME Code,Section XI rger erneancessni Spe of Code Symtol Stamp N/A - Comed 10CFR50 Aon B. O A Procram ertificate of Authorization No. _

N/A Expiration Date N/A igned Nll (ab f6f6@vP!An Date O t.ro w 'll 19 16

/ IfamererOwner'sDengues. Tale CERTIFICATE OF INSERVICE INSPECTION

the undersigned. holding a valid ccanission issued by the National Board of Boiler and Pressure Vessel Inspectors

' the State of Illinois - and enployed by Martf&d Steam Boiler inroection & Insurance Co.

of Hartford. CT have inspected the ts described in this Owner's Report during the period

/ /* 4IfO to 1/tdff

, and state that to the best of my knowledge and plief, the owner has grformed exammations and taken corrective measures described in this Owner's Report in acccrdance the requirements of the SME Code,Section XI.

r signing this cenificate, neither the inspector nor his enployer rnakes any warranty, expressed or implied, concerning the exammations and rrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any honal irsury or property damage or a loss of any kind arising from or emnected with this inspection.

• d I h I-Cminissions MW new numman.

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l FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions ef ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-006 WR# 980008084-01

1. Owner: Commonwealth Edison Date: 08/10/98 P.O. Box 767. Chicago, IL 60690 Sheet: I of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North,Cordova,IL 61242 Repair Organuanon P.O. No., Job No etc.

Type Code Symbol Stamp:

N/A

3. Work Performed by:

Quad Cities Nuclear Station Authorization No.:

N/A 22710206th Ave. North,Cordova.IL 61242 Expiration Date:

N/A

4. Identification of System: Scram Discharge Header, Class 2

5. (r) Applicable Construction Code: USAS B31.11%7 Edition..Emigt Addenda,.N/A, Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: J2)S., Edition.E/A. Addenda,.HlA Code Case

6. Identification of Components Repained or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced. or Code No.

Replacement Stamped (Yes or No)

Bolting.

N/A Various N/A Sl# 7%D77 N/A Replacement No 7%D03

7. Description of Work: Reolaced studs and nuts as reauired by the WR.

Ests Conducted: Hydrostatic Pneumatic O Nominal Operating Pressure Other O Pressure E!A psi Test Temp. H/A 'F

9. Remarks: No testine reauired.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this repon are correct and this reDlacement Conforms to the rules of ASME Code.Section XI repast orreplacement Fype cf Code Symbol Stamp N/A - Comed 10CFR50 Ano B. O A Program Certificate of Authorization No.

N/A Expiration Date N/A Signed

' Nil fat.

A(4hP h Date Av4.u # U 19 4 6 Ur - 04ner or Owner a Designee. Title 8

CERTIFICATE OF INSERVICE INSPECTION the undersigned, holdmg a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors md the State cf filinois and employed by Hartford Steam Boiler Insoeetion & Insurance Co of Hartford. CT have inspected the

omponents desenbed in this Owner's Repon during the penod M -98 to I~28 49. and state that to the best of my knowledge and ief the owner has performed exarmnations and taken corrective measures desenbed in this Owner's Report in accordance the requirements of the ME Code.Section XI.

y signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, conceming the examinations and corrective g

sures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or wrty damage or a loss of any kind arismg from or connected with this inspection.

i

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FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions cf ASME Code Section XI QCAP 0307 20 Revision 5 CGE Program # 98-007 WR# 970115354-01

1. Owner:

Commonwealth Edison Date: 06-23-1998 P.O. Box 767, Chicago, IL 60690 Sheet:--! of 1 Unit:

1 2.Hant:

Quad Cities Nuclear Power Station Comed 22710206th Ave. North,Cordova,IL 61242 nepair visana.on r.v. r.o., son r.o., cic Type Code SymbolStamp:

FL/6

3. Work Performed by:

Quad Cities Nuclear Station Authorization No.:

UL/6 22710206th Ave. North,Cordova,IL 61242 Expiration Date:

F_/A

4. Identification of System: Core Spray, Class 2

5. (a) Applicable Construction Code: USAS B31.1 1967 Edition, None Addenda, N/A Code Case (b) Applicabi: Edition of Section XI Utilized for R pairs or Replacements: 1989 Edition, N/A Addenda, N/A CodeCase

6. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Ccmponent Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Relief Valve Consolidated TC 46092 N/A l 1402 28B N/A Replaced Yes R", lief Valve Consolidated TH78259 N/A 1-1402 28B N/A Replacement Yes

7. Description of Work: Replaced the relief valve in accordance with the WR.

8. Tests Conducted: Hydrostatic 0 Pneumatic NominalOperatingPressure O Other D Pressure 252 psi Test Temp.21 *F

9. Remarks: Performed VT-2 inspection.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this repon are correct and this replacement conforms to the rules of ASME Code,Section XI repaar orreplacement Type ef Code Symbol Stamp N/A - Comed 10CFR50 Ano B. O A Program Certificate cf Authorization No.

N/A Expiration Date N/A Signed s2 f4f ha r m Date dLME N 19 T6

[/

ewner'or Owner s Designec. Tsue '

CERTIFICATE OF INSERVICE INSPECTION

,1. the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors

! md the State of Illinois. and employed by. Hartford Steam Boiler Insocction & Insurance Co of Hartford. CT have inspected the omponents described in this Owner's Report during the period f-lia & to & * /& '/3. and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the

' SME Code,Section XI.

A 3y signing Cis cenificate. neither the inspector nor his employer makes any warranty, expressed or implied. conceming the examinations and corrective nessures described in this Owner's Repon. Furthermore neither the inspector nor his employer shall be liable in any manner for any personal injury o property d e or a loss of any kind arising from or connected with this inspection.

Commissions bi7/

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FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 5 CGE Program

• 98-008 WR# 970041151-01

1. Owner:

Commonwealth Edison Date: 06-04-98 P.O. Box 767, Chicago,IL 60690 Sheet: I of 1 Unit:

1 Li nt:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova,IL 61242 Kepmr Urgannon F.U. No. Job S0 etc Type Code Symbol Stamp:

_N/6

l. Work Performed by:

Quad Cities Nuclear Station Authorization No.:

N/.6 22710206th Ave. North,Cordova,lL 61242 Expiration Date:

H./6

l. Identification of System: Main Steam, Class I

i. (a) Applicable Construction Code: ASME Section III 1968 Edition, W-1968 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A Code Case

i. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Safety Valve Target Rock 198 N/A 1-0203-3 A UNK Replaced Yes Safety Valve Target Rock 120 N/A 10203 3A UNK Replacement Yes

. Description of Work: Reelaced the Tarcet Rock Valve in accordance with WR.

• s Conducted: Hydrostatic O Pneumatic O Nominal Operating Pressure Other @

Pressure 1013 psi Test Temp.212 'F

. Remarks: Performed VT 1-1 inspection on inlet boltine.

Performed VT-2-1 durine Class i System Leak =ee Test.

CERTIFICATE OF COMPLIANCE Ve certify that the statements made in this report are correct and this Reolacement conforms to the rules of ASME Code,Section XI repaar or replacement rype cf Code Symbol Stamp N/A -Comed 10CFR50 Ado B. O A Procram

ertificate cf Authorization No.

N/A Expiration Date N/A igned YM Fod, 5+r % * =

Date duue. d 1946 y Ow11er or Ownct's Designec, huc CERTIFICATE OF INSERVICE INSPECTION the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors sd the State of Illinois. and employed by Hartford Steam Boiler Irispection & Insurance Co of Hartford. CT have inspected the Hnponents described in this Owner's Report during the period

/ -6 V B' to 4 - /5 4 E, and state that to the best of my knowledge and plief, the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requiremer of the

$ME Code Section XI.

y signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, conceming the examinations and corrective casures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal in operty damag or a loss of any kind arising from or connected with this inspection.

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-009 WR# 980008089-01 h Owner: l Commonwealth Edison Date: 07/23/98 P.O. Box 767. Chicago IL 60690 Sheet: 1 of 1 LPlant:

' Quad Cities Nuclear Power Station Comed 22710 206th Ave. North. Cordova. it 61242 Repair Orgami.auon P.O. No Job No..etc Type Code Symbol Stamp:

N/A L Work Performed by:

Quad Cities Nuclear Station -

Authorization No.:

N/A 22710 206th Ave. North. Cordova. IL 61242 Expiration Date:

N_/A i

L Identification of System: High Pressure Coolant Injection. Class 2 -

l (c) Applic ble Construction Code: USAS B31. I 1%7 Edition. Ng,g., Addenda..NJA, Code Case

( (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: _1282,, Edition..N/A Addenda N_/i Code Case

( Identificition of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year Repaired.

ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code j

No.

Replacement Stamped l

(Yes or No)

Pipe N/A Ht# 535lW N/A l-2303 1/2"-DX N/A Replacement No l

Coupling N/A Lot # K531 N/A l-2303-1/2"-DX N/A Replacement No j

l.

1 l Description of Work: Reolace nine nipole and nine to 2399-16 valvq as rW ed by WR.

ists Ccnducted: ' Hydrostatic Pneumatic Nominal Operating Pressure Other

- Pressure FjA psi Test Temp. N/A 'F I

' Remarks: No oressure testine reauired. no weldine to the numo naiar.

A check for leaks was nerformed durine numo run.

I CERTIFICATE OF COMPLIANCE fe certify that the statements made in this report are correct and this iedK aan^ conforms to the rules of ASME Code.Section XI mper or --

l gpe of Code Symbol Stamp N/A - ComF2I IOCFR50 Ano B. O A Prorram l

L qific:.te of Authorization No.

N/A Expiration Date N/A gned r ILIJA ma.

fer " a e~s Date J w _v f'l>

1946 l.

/

Uwner or owner's Designee. T) le i

i l

[.

CERTIFICATE OF INSERVICE INSPECTION '

the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors p the State cf-UHan and employed by Hartford p noin.,Irie--*iaa & laanr=- Co.

of Hartford. Cr have inspected the mponents described in this Owner's Report during the period 4-5-Ifa ' to 1 2/- ff, and state that to the best of my knowledge and lief, the cwner has performed examinauons and taken corrective measures desenbed in this Owner's Report in accordance the requirements of the BME Code. Secuon XI.

r signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective msures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or verty damage or a loss of any kiix! arising from or connected with this inspection.

/I s Comnussions fM j

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FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Secticn XI QCAP 0307-20 Revision 6 CGE Program # 98-014 WR# 980028387-01

1. Owner:

Comnxxiwealth Edison Date: 02/08/99 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Umt:

1 EPlant-Quad Cities Nuclear Power Station Comed 22710206th Ave. North,Cordova,IL 61242 kepaa ursanamuon P.O. No., Job No., etc.

Type Code Symbol Stamp:

N/A

5. Work Performed by-Quad Cities Nuclear Station Authorization No.:

E 22710 206th Ave. North, Cordova,IL 61242 Expiration Dae:

IL/A

l. Identification of System Control Rod Drive, Class 1

5. (a) Applicable Construction Code: ASME Section IIL 1%5 Editicx1, W-65 Addenda, 1361 Code Case (b) Applicable Editicx1 of Section XI Utilized fcr Repairs or Replacements: 1989 Edition,.th Addenda, N/A Code Case

6. Identificaticx1 of Compczients Repaired cr Replaced, and Replacement Components:

N.ame of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificaticx1 Built Replaced, er Code No.

Replacement Stamped (Yes or No)

Contrci Rod Dnve GE 534A N/A 1-0300-G-7 1%8 Replaced Yes Control Rod Dnve GE 618 N/A l-0300-G-7 1%8 Replacement Yes

7. Description of Woric Removal and replacement of Control Rod Dnve and associated bolting as reauired by the WR.

Tests Ccriducted: Hydrostatic O Pneumatic O Nominal Operaung Pressure Other @

Pressure 1005 psi Test Temp. 2.1._0 *F

. Remarks: Performed VT-1 insoection on boltine.

Performed VT-2 dunne the Class 1 System I **are Test.

l CERTIFICATE OF COMPLIANCE ke certify that the statements made in this report are correct and this reDlacement conforms to the rules of ASME Code Section XI repair orsepa cement p of Code Symbol Stamp N/A - Comed 10CFR50 Ano B. O A Program lertificate of Authorization No.

N/A Expiration Date N/A gned b ld et 16f (s4svP 444D Date fdAs.M6cf /f 19 4 4 y

towner cr owner's peasmee, noe if I

CERTIFICATE OF INSERVICE INSPECTION

, the indersigned, holding a valid commission issued by the National Board of Boiler and Pressure L,sel inspectors the: State of minnic. and employed by Hartford Steam Boiler Innection & Insurane Co.

of Hartfor i CT have inspected the aents desenbed in this Owner's Report during the period 4/2 #/0 P to M / d 9t?

, and state that to the best of my knowledge and

. ef, the owner has performed exarranations and taken corrective rneasures described in this Owner's Report in accordance the requzrerrents of the EME Code,Section XI.

sig2ing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied. concerning the examinations and corrective uses described in this Owner's Report. Fwhism, neither the inspector nor his employer shall be liable in any manner for any personal injury or roperty damage or a loss of any kind arising from cr connected with this inspecticn.

I-Corrrnissions fM Eu

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FORM NIS-2 0WNERS REPORT OF REPAIR OR REPLACEMENT j

As Required by the Provisions of ASME Code Section XI j

QCAP 0307-20 Revision 6 CGE Program # 98-017 WR# 980021522-01 &-03

l. Owner:

Commonwealth Edison Date:

I/29/99 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1 LPlant:

Quad Cities Nuclear Power Statim Comed 22710 206th Ave. North, Cordova, IL 61242 RePur Orgarauon P.O. No., Job No., etc.

Type Code Symbol Stamp:

F.fA

l. Work Perforrned by-Quad Cities Nuclear Station Authortzation No.:

NL6 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

l. Identification of System Reactor Water Cleanup, Class 1

5. (a) Applicable Construction Code: USAS B31.1.0 1%7 Edition, None Addenda, N/A Code Case (b) Applicable Editim of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N-416-1 Code Case

5. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Se.

Nat'l Other Year

Repatred, ASME Component Mfr.

No.

Bd.

Identificaticri Built Replaced, or Code Nc.

Replacement Stamped (Yes or No)

RPV Bottom Head GE N/A N/A 1-1265-2" N/A Replacement No Drain Pipe

. Desenption of Work Replaced txrtion of drain line with weldine as reouired by the WR.

. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other O Pressure 1005 psi Test Temp. 2.1._0 *F i. Remarks: Performed FT surface examinations on new welds.

Performed VT-2 durine Class 1 System ixakare Test.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code.Section XI npaar orreplacenent Type of Code Symbol Stamp N/A -Comed 10CFR50 App B. O A Program

ertificate of Authorization No.

N/A Expiration Date N/A signed k $ Y. sb l.

Z4% Mw t u r~.

Date d MvArt.N 71 19 %, -

y ownerorowner socesnee Tale s

I CERTIFICATE OF INSERVICE INSPECTION the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors ad the State of Illinois. and employed by Hartford Steam Boiler Insoettion & Insumnce Co.

of Hartford. CT have inspected the anponents described in this Owner's Report during the period 3* M-? T to # - 4 M

, and state that to the best of my knowledge and lief, the owner has performed exammations and taken corrective measures described in this Owner's Report in accordance the requirements of the SME Ccxle.Section XI.

, y signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the exammations and corrective neasures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or petty damage or a loss of any kind arisin from or connected with this inspection.

Commissions M U/

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,19 4

FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by th) Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-018 & 98-035 WR# 980026249-01 & 02 Owner:

Commmwealth Edism Date: 01/11/1999 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1 flant:

Quad Cities Nuclear Power Stattan Comed 22710 206th Ave. Ncrth, Cadova,IL 61242 Reimar Orsanarauon P.O. No., Job No., etc.

Type Code Symbol Stamp:

N/6 Work Performed by-Quad Cities Nuclear Station Authorizaticn No.:

N/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A Identification of System Main Steam, Class 1 (a) Applicable Construction Code: USAS B31.11%7 Editim, None Addenda, N/A Code Case (b) Applicable Editim of Section XI Utihzed fa Repairs or Replacements: 1989 Edition, N/A Addenda, N/A CodeCase Identificatial of Compments Repaired or Replaced, and Replacement Compments:

l Name of Name of Mfrs. Ser.

Natl Other Year Repaired.

ASME Component Mfr.

No.

Bd.

Identificaticn Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Pipe Flance N/A N/A N/A 1-3026-F N/A Repatred No Desalption of Work: Repaired defects in flance face and replaced boltine as reautred by the WR.

Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other D Pressure 1013 psi Test Temp. 2.1.; 'F Remarks: Performed a VT-3-1 m flance face after repairs. Performed a VT-2-1 dunne the Class I System leakare Test..

Performed a VT-1-1 on replacement boltine.

CERTIFICATE OF COMPLIANCE e certify that the statements made in this report are correct and this Rena!r conforms to the rules of ASME Code,Section XI repeir orreplacement me of Code Symbol Stamp N/A -Comed 10CFR50 Ann B. O A Procram ptificate of Authwizatico No.

N/A Expiration Date _,,

N/A gned sht f4s &c.ow= IAca Date dAuod.Y 1*>

19 H y

Otacr or Owner's Desgnee. Tai.le

'3 CERTIFICATE OF INSERVICE INSPECTION he undersigned, holding a valid conxnission issued by the National Board of Boiler and Pressure VesselInspectors i the State of IHinois. and employed by Hartford Steam Boiler Inscection & Insurance Co.

of Hartford CT have inspected the npanents described in this Owner's Report during the period 3 -M-9 P to 4' / F-fi, and state that to the best of my knowledge and ici. the owner has performed exammations and taken corrective measures described in this Owner's Report in accordance the requirements of the ME Ccde Section XI.

signing this certificate, neither the inspector nor his employer rmies any warranty, expressed or impheu concerning the examinations and corrective asures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liabic in any rmaner for any personal injury or perty damage or a loss of any kind arising from or connected with this inspection.

__ Commissions N N !

ww.

- =-s mn.un-m.

te 2- /P -

1999

FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307 20 R: vision 6 CGE Program # 98-019 &98-034 WR# 980026254-01 &O2

1. Owner: Commonwealth Edison Date: 01/11/1999 P.O. Box 767, Chicago,IL 60690 Sheet: 1 of 1 Unit:

I

!. Plant-Quad Cities Nuclear Power Statim Comed 22710 206th Ave. North, Cordova, IL 61242 Repur organnauon P.O. No., Job No., ac.

Type Code Symbol Stamp:

M6 J. Work Performed by:

Quad Cities Nuclear Station Authonzabcn No.:

M/6.

22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

M6

. Identification of System: Main Steam Class !

. (a) Applicable Construction Code: USAS B31.1 Editim, Nme Addenda, N/A CodeCase (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Editicn, N/A Addenda N/A Code Case

. Identification of Compments Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Pipe Plange N/A N/A N/A 1-3026-E -

N/A Pmaared No

. Description of Work: Reosired defects in flanze face and replace botting as reouired by the WR.

. Tests Cmducted-Hydrostatic Pneumatic 0 Nominal Operating Pressure Other Q Pressure 1013 psi Test Temp. 2J12 'F Remarks: Performed a VT-3-1 on flance face after repairs. Performed a VT-2 1 during the Class i System Leakare Test Performed VT-1 1 on the replaced bolting.

CERTIFICATE OF COMPLIANCE Ve certify that the statements made in this report are correct and this repair conforms to the rules of ASME Ccde.Section XI repair orsepiacemeat

'ype of Code Symbol Stamp N/A - Comed 10CFR50 At,o B. O A Procram ertificate of Authorization No.

N/A Expiration Date N/A gned r10!llN6 **.

for Move % Date M wvaeV 1%

1944 y

pwner or Owner's Desgaec, Tide 4i CERTIFICATE OF INSERVICE INSPECTION the undersigned, holditg a valid commissim issued by the National Board of Boiler and Pressure Vessel Inspectors d the State of mimis. and errplopd by Hartford Steam Boiler Insoection & Insurance Co of Hartford. CT have inspected the rgonents described in this Owner's Report during the period J M* 7 F to A N-99

, and state that to the best of my knowledge and di;f. the owner has performed exammations and taken corrective measures described in this Owner's Report in accordance the requirenents of the iME Code.Section XI.

' signing this certificate, neither the inspector nor his emplopr makes any wammty. expressed or implied conceming the enminations and corrective msures described in this Owner's Report. Furthermore, neither the laspector not his employer shall be liable in any manner for any personal injury or perty damage or a loss of any kind arising from or connected with this inspection.

. f. 8 Commissions 9d a-e m w am s.o, - ne te,,

Ae N 19 79

/

FORM NIS.2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-025 WR# 980020099-01

1. Owner: Commonwealth Edison Date:

11/18/98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710206th Ave. North, Cordova, IL 61242 Repar orsamzauon P o. Na. Job Na. etc.

Type Code Symbol Stamp:

EB

3. Work Performed by-Quad Cities Nuclear Station Authorization No.:

N/6 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

4. Identification of Systent Core Spray, Class 2

5. (a) Applicable Constructicx1 Code: USAS B31.1 1967 Edition None Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A CodeCase

6. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Pipmg N/A N/A N/A 1-1412-3/4"-A N/A Repaired No

7. Description of Work: Cut and reroute ninmr by weldine as reouired by WR.

Tests Conducted: Hydrostatic 0 Pneumatic Nominal Operatmg Pressure C Other O Pressure NB psi Test Temp. N% 'F P. Remarks: Repair is exempt from ASME Section XI pressure test reauirements based on size.

CERTIFICATE OF COMPL1ANCE We certify that the staternents made in this report are correct and this repair conforms to the rules of ASME Code.Section XI repair or replacement Type of Code Symbol Stamp N/A - Comed 10CFR50 Ann B. O A Procram

ertificate of Authorization No.

N/A Expiration Dote N/A

igned $1)

M, 1% WMPtrdo Date

&tmMt 18 19 46

{ owner or owner. ocusnee. Inie CERTIFICATE OF INSERVICE INSPECTION

. the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors nd the State of Illinois. and employed by Hartford Steam Boiler Insnection fjbyrance Co of Hartford. CT have inspected the xnponents described in this Owner's Report during the period 9#f

• I'd to J' WI, and state that to the best of my knowledge and plief the owner has perfonned examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the

,SME Code.Section XI.

y signing this certificate. neither the inspector nor his emplopt makes any warranty, exprersed or implied. concerning the examinations and xtective umsures described in this Owner's Report. Furthennore, neither the Inspector Lor his employer shall be liable in any manner for any isonal injury or property darnage or a loss of any kind arising from or connected with this inspection.

II' _77/

Commissions v

8-E ft ute i9

FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT l

As Required by the Provisions of ASME Code Section XI l

QCAP 0307-20 Revision 6 CGE l

Program # 98-045 WR# 980044515-01 l

1. Owner: Commonwealth Edison Date: 2/1/99 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova,IL 61242 R=rau orss= muon P.O. Na. sob ba. cic.

Type Code Symbol Stamp:

B

3. Work Performed by-Quad Cities Nuclear Station Authorization No.:

E 22710 206th Ave. North, Cordova,IL 61242 Expiration Date:

E

4. Identification of System: High Pressure Coolent Injection, Class 2

5. (a) Applicable Construction Code: USAS B31.11%7 Edition, None Addenda, N/A CodeCase (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N-416-1 Code Case

6. Identifiention of Compments Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacerr.ent Stamped (Yes or No)

Check Valve Hancock Ht# YJ11YSE N/A 1-2301-34 N/A Replacement No Pipe

[

N/A Ht# A30005 N/A 1-2309-2NLX N/A Replacement No

7. Description of Waric Rentsced the nine and check valve by welding as reauired by the WR.

Tests Cmducted: Hydrostatic Pneumatic Nominal Operating Pressure O Other @ Pressure JO, psi Test Temp.186 'F P. Remarks: Used Code Case N-416-1 for pressure testmr.

Performed a VT-2 on the replacement parts.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are ccurect and this replacement conforms to the rules of ASME Code,Section XI repan orrept comes Type of Code Symbol Stamp N/A - Comed 10CFR50 Ann B. O A Program Mficate of Authorizatim No.

N/A Expiration Date N/A iigned /hdlli,3d fat.

-f%f de/P #Ad Date 14me d I 1949

{ " lowner or ower's t=aisme. T*

CERTIFICATE OF INSERVICE INSPECTION

, the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors ad the State of minnic. and employed by Hartford Steam Boiler Insnection & Insurance Co.

of Hartford. CT have inspected the amponents described in this Owner's Report during the period S'/M /ff to M1,./ FIF

, and state that to the best of my knowledge and picf. the owner has performed exarranations and taken corrective measures described in this Owner's Repcrt in wdouc.e the requirements of the SME Code,Section XI.

y signing this certificate, neither the inspectcr nor his employer makes any wananty, expressed or implied. concernmg the examinations and wrective measures described in this Owner's Repcxt. Purthermore, neither the inspec".or nor his employer shall be liable in any manner for any trsonal injury or property damage or a loss of any kind arising from or ccamected with this inspection.

[

U Comnissicsis N

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7 b

2 19 99 ate

FORM NIS-2 OWNERS REPORT CF REPAIR OR REPLACEMENT As Required by the Provisions cf ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-05i WR# 980051285-01

1. Owner:

Commonwealth Edison Date: 10/30/98 P.O. Box 767. Chicago, IL 60690 Sheet: I of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North,Cordova,IL 61242 Repw Orgamamon F.O. No Job No., m Type Code Symbol Stamp:

N/A

3. Work Perfonned by:

Quad Cities Nuclear Station Authorization No.:

N%

22710206th Ave.Nonh,Cordova,IL 61242 Expiration Date:

N/A

4. Identification of System: Reactor Vessel Water Level Instrumentation Piping, Class I

5. (a) Applicable Construction Code: UJ y 331.1 1967 Edition, N/A Addenda, N/A Code Case (b) Applicable Edition of Section XI Utiuzed for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A CodeCase

6. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year Repaired.

ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Excess Flow Check Chemiquip Products H; < 32319 N/A l-0263 2-42B UNK Replacemmt No Valve Co.

Pipe N/A l Ht # 3992H N/A 1-0294-1"-RX N/A Replacement No

7. Description of Work: Reclared check valve. eine. and union by weldine as reauired by the WR.

8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure O Other Pressure psi Test Temp._ 'F

?. Remarks: Replaced components are exemot from ASME Section XI reolacement/oressure tests reauirements.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code,Section XI ap= or aphas===

Type cf Code Symbol Stamp N/A -Comed 10CFR50 Ann B. O A Procram Certificate cf Authorization No.

N/A Expiration Date N/A

. signed

/~d ) 1 h d sro t str a= = r e Date Corow bl 19 'f 6

[ ' Q or Owner's Des gnet, Tale CERTIFICATE OF INSERVICE INSPECTION i

. the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors nd the State of Illinois. and employed by Hartford Ste.gp Boiler Insocction & Insurance Co of Hartford. CT have inspected the omponents described in this Owner's Report during the period C / W l 4 P to 1/1/M, and state that to the best of my knowledge ar.d Niicf. the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the req LSME Code.Section XI.

ly signing this certificate, neither the inspector nor his employer makes any warranty, expened or implied, concerning the examinations and corrective peasures described in this Owner's Report. Ficthermore, neither the inspector nor his empmyer call be liable in any manner for any personal injury or vperty damage or a loss of any kind arising from or connected with this inspection.

[*

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Commissions Nf 2-19 N late I

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FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI

)

QCAP 0307-20 Revision 6 CGE Program # 98-076 WR# 980063567-02 & 03

' Jwner:

Cammnnwealth Edison Date:

12-23-98 P.O. Box /67, Chicago,IL 60690 Sheet: I of 1 Unit:

1

, Plant:

Quad Cities Nuclear Power Statim Comed l

22710 206th Ave. North, Cordova, IL 61242 hpar ursasurauon P.O. Na, Job Na, ac.

1 Type Code Symbol Stamp:

N/A Work Performed by:

Quad Cities Nuclear Station Authorization No.:

E!.6 22710 206th Ave. North,Cordova,IL 61242 Expiradon Date:

H/6 Identification of System Standby Liquid Control System, Class 2

(:) Applicable Constructim Code: USAS B31.1 1%7 Edition, Egpe Addenda, N/A Code Case (b) Applicable Editicn of Section XI Utihzed for Repairs or Replacements: 1989. Editica, N/A, Addenda, N/A Code Case j

Identificadon of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repatred, ASME Component Mfr.

No.

Bd.

Identificatim Built Replaced, or Code j

No.

Replacement Stamped (Yes or No)

Valve in11 Plug Canax C/N 19466 N/A 1 1106-A N/A Replacement No l

Trigger Assembly Canar S/N 81 N/A 1 1106-A N/A Replacement No Description of Waric Replaced the tnerer assembly and plus after the surveillance as reautred by the WR.

Tests Conducted: Hydrostatic Pneumatic Nominal Operatmg Pressure Other G Pressure 1295 psi Test Temp. Ambient 'F Remarks Performed a VT-2 durme the system functional test.

CERTIFICATE OF COMPLIANCE le certify that the statements made in this report are correct and this reolacement cmforms to the rules of ASME Code, Sectim XI repair or repiecemens l

me of Code Symbol Stamp N/A - Comed 10CFR50 Ano B. O A Program rtificate of Authcrtzation No.

N/A Expiration Date N/A ped M' Fef

'rV f "" ' ~

Date N~-^^--'

da 19 4 S y

Dwner or Owaar s Densmes, Taoe CERTIFICATE OF INSERVICE INSPECTION be undersigned. holding a valid commissian issued by the National Board of Iloiler and Pressure Vessel Inspctors d the State of minnie. and employed by Hartford Steam Boiler Inenection & Insurance Co of Hartfoni CT have inspected the riponents described in this Owner's Report during the period //- #-fF to /-// "f(

. and state that to the best of my knowledge and belief.

i owner has performed exananations and taken corrective measures described in this Owner's Report in accordance the requirements of the ASME de.Section XI.

signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied. concerning the exarranations and corrective i

wwes described in this Owner's Report. Funbermore. neither the Inspector nor his employer shall be liable in any manner for any personal irdury or perty damage or a loss of any kind arising fmrn or connected with this inspection.

5" b Y

' Commissions N

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FORM NIS-2 OWNER 3 REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Secuan XI OCAP 0307 20 Revision 6 CGE Program # 98-079 WR# 980027855-01

)

Owner:

Commonwealth Edison Date:

12-10-98 P.O. Box 767, Chicago, IL 60690 Sheet: I of 1 Unit:

1 Plant:

Quad Oties Nuclear Power Statian Comed i

22710 206th Ave. North, Cordova, IL 61242 kcPau Orguuuuon P.O. 50., Job No., ac.

Type Code Symbol Stamp:

N_/A

Work Performed try-Quad Ques Nuclear Station Authortzatim No.:

N_/A 22710 206th Ave. North, Cordova, IL 61242 Expirauon Date:

_N_/6

identificauan of System Control Rod Dnve. Class 1 (a) Apphcable Construction Code

ASME Section III 19'5 Edition, W-65 Addenda, 1361 Code Case (b) Applicable Editim of Sectim XI Utihzed for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A CodeCase

' identificatim of Compments Repaired or Replaced, and Replacement Compments:

-Name of Name of Mfrs. Scr.

Nat'l Other Ycar

Repaired, ASME Component Mfr.

No.

Bd.

' Identification Built Replaced, or Code.

No.

Replacement StaN.ed (Yes or 1

No)

Control Rod Dnve GE 6517 N/A 54-47

'1992 Replaced Yes gntrol Rod Dnve GE A8955 N/A 54-47 UNK Replacement Yes l

Desenpuan of Work: Rer> laced Control Rod Dnve and associated boltine as recurred bv WR.

Vests Conducted: Hydrostatic Pneumatic 0 Nominal Operaung Pressure C Other @

Pressure 1014 psi Test Tetap. 2.12 'F Remarks: Performed VT-1 visual inspection on all boltine.

Performed VT-2 dunne Class I System Leakare Test.

CERTIFICATE OF COMPLIANCE fe certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code Section XI repas urseplacement ype of Code Symbol Str.mp N/A - Comed 10CFR50 Ann B O A Procram

rtificate of Authortzation No.

N/A Expirauon Date N//

yed W Y fot.

1'1 M%r> ww Date DewnvNtd Io I9 AB p

Onner or Owner s Desasnce Tade 4

i CERTIFICATE OF INSERVICE INSPECTION h undersigned, holding a valid correnission issued by the National Board of Boiler and Pressure Vessel Inspectors p the State of minois. and employed by Hartford Steam Boiler Insrection & Insurance Co of Hartford. CT have inspected the to //f//f9, and state that to the best of my knowledge and mponents described in this Owner's Report during the period

@'/> O/# F

, c. the owner has performed exammations and taken corrective measures descnbed in this Owner's Report in accordance the requirements of the ME Code.Section XI.

, signing this cenificate, neither the inspector nor his employer rmkes any warranty, expressed or implied. concerning the examinations and corrective asures described in this Owner's Report. Furthennore. neither the inspector nor his employer shall be liable in any manner for any personal ir4 jury or yny damaFe or a loss of any kind arising from or connected with this inspection.

[

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I FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI l

QCAP 0307-20 Revision 6 CGE E

Program # 98-0%Ythru 98-103 WR# 980019145-01 thru 24

1. Owner:

Commcriwealth Edison Date: 01/27/1999 4 sdM P.O. Box 767, Chicago, IL 60690 Sheet: I of 3 I

Unit:

1

2. Plant:

Quad Cines Nuclear Power Stattm Comed 22710206th Ave. North Cordova,IL 61242 b =w orsmuun to. Na, Job 3a, ac.

l Type Code Symbol Stamp:

Ff,A

3. Work Performed by Quad Cities Nuclear Station Authorizaticri No.:

U!A 22710 206th Ave. North, Cadova, IL 61242 Expirauon Date:

_N.!A

. Identification of System: Control Rod Dnve, Class 1

)5,(:) Apphcable Constmcuan Code: ASME Section III 1%5 Edition, W-1965 Addenda, 1361 Code Case l (b) Applicable Edition of Secticri XI Utilized for Repairs a Replacements: 1989 Edition, N/A Addenda, N/A Code Case

. Identification of Compcnents Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificaticri Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Control Rod Dnve GE 8762 N/A 1 300-50-27 1980 Replaced Yes Control Rod Dnve GE 48 N/A 1-300-50-27 1%7 Replacement Yes

, Descnption of Work: Reolaced Control Rod Dnves and associated boltine as reouired by the WR.

. Tests Ccnducted: Hydrostatic Pneumatic O Nominal Operating Pressure Other @

Pressure 1014 psi Test Temp. 212 'F Remarks: Performed a VT-1 on all boltine Performed VT-2 dunne Class i System Leakare Test.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this repcut are conect and this replacement confonns to the rules of ASME Code,Section XI repsu orrepancearn ype of Code Symbol Stamp N/A -Comed 10CFR50 Are B. O A Procram ficate of Authcrtzation No.

N/A Expiration Dat:

N/A i

'1lfiAIn l gned M.

At Arsup e ao Date

1. 1. eAw'

'S 19 Pi y

Dwaar or Owner's Demgnee, Uuc d

• 8 CERTIFICATE OF INSERVICE INSPECTION the undersigned. holding a valid ccrnmission issued by the National Board of Boiler and Pressure Vessel Inspectors nd the State of Mnnk. and employed by Hartford Stearn Boiler inmeetion & Insurance Co of Hanford CT have inspected the

nnpanents described in this Owner's Report during the period 3r'.20 9I to d ~J - W, and state that to the best of my knowledge and helief, the owner has performed examistions and taken conective rneasures described in this Owner's Report in accordance the requirements of the SME Code,Section XI.

y signing this cenificate. neither the inspector nor his employer makes any warranty, expressed or implied, concerning the exarrunations and conective pures desuibed in this Owner's Report. Purthermore. neither the laspector nor his employer shall be liable in any manner for any personal irdury or Fy damage or a loss of any kind arising from or connected with this inspection.

-[

Commissions

1. 3

_.,_ _. ~

hte M2 19 97 I

FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT (Supplemnt) l As Required by the Provisions cf ASME Code Section XI

{

thru 98-103 WR# 980019145-01 thr3u Program # 98-08{P5M

1. Owner:

Commonwealth Edison Date:

01/27/1999 P.O. Box 767, Chicago,IL 60690 Sheet: 2 of 3 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710206th Ave. North,Cordova,IL 61242 xepau vrgannuon r.u r,o., suo rvo cw Type Code Symbol Stamp:

N/A

3. Work Performed by:

Quad Cities Nuclear Station Authorization No.:

N/A 22710206th Ave. North,Cordova,IL 61242 Expiration Date:

N!&

. Identification of System: Control Rod Drive, Class 1

5. (a) Applicable Construction Code: ASME Section III 1965 Edition, W-1965 Addenda, 1365 CodeCase (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A Code Case

. Identification of Components Repaired or Replaced, and Replacement Components: Continued Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No) l Control Rod Drive GE 0546 N/A l-300-06-27 1%8 Replaced Yes Control Rod Drive GE 9176 N/A 1 300-06-27 1992 Replacement Yes E ControlRod Drive GE 774 N/A 1 300-10-23 1968 Replaced Yes l Control Rod Drive GE 828" N/A 1 300 10-23 1978 Replacement Yes Control Rod Drive GE A3t ???

N/A 1-300-10-35 UNK Replaced Yes E ControlRod Drive GE A8237 N/A 1 300-10-35 1989 Replacement Yes Control Rod Drive GE I100 N/A 1 300-10-47 UNK Replaced Yes Control Rod Drive GE A9119 N/A 1 300-10-47 1992 Replacement Yes E Control Rod Drive GE

$05 N/A 1-300-14 43 UNK Replaced Yes

} Control Rod Drive Control Rod Drive GE A8074 N/A 1 300-14-43 1986 Replacement Yes d

GE 6591 N/A l 300 18 23 1984 Replaced Yes E Control Rod Drive GE 6285 N/A 1 300-18-23 1974 Replacement Yes fl Controll'od Drive Control Rod Drive GE 408 N/A 1 300-18 55 1980 Replaced Yes

[

GE 6602 N/A 1 300-18-55 1978 Replacement Yes l ControlRod Drive GE 7839 N/A 1 300-22 27 1991 Replaced Yes 5 Control Rod Drive GE 1056 N/A 1 300-22 27 1969 Replacement Yes ll ControlRod Dnve GE 1534 N/A 1 300-22 31 1982 Replaced Yes l Control Rod Drive GE A8541 N/A 1 300-22-31 1987 Replacement Yes 4

l Control Rod Drive GE 1885 N/A 1 300-22-35 UNK Replaced Yes

] Control Rod Drive GE 997 N/A 1 300-22-35 1969 Replacement Yes k Control Rod Drive GE 9341 N/A 1 300-26-23 1978 Replaced Yes l Control Rod Drive GE A8129 N/A 1 300-26-23 1986 Replacement Yes

] Control Rod Drive GE A5482 N/A 1-300-26-59 UNK Replaced Yes b Control Rod Drive GE 65 N/A 1 300-26-59 1%8 Replacement Yes l Control Rod Dnve GE 1669 N/A 1 300-34-31 1988 Replaced Yes T Control Rod Drive GE A9463 N/A 1 300-34-31 1994 Replacement Yes L Control Rod Drive GE A3343 N/A l-300-38-11 1980 Ret. laced Yes l Control Rod Drive GE 9440 N/A 1 300-38-11 1978 Replacement Yes l' Control Rod Drive GE 391 N/A l-300-42-35 1994 Replaced Yes

[ Contro: Rod Drive GE A9459 N/A 1 300-42-35 1994 Replacement Yes l Control Rod Drive GE A6676 N/A 1 300-42-39 1992 Replaced Yes P Control Rod Drive GE A9465 N/A 1-300-42 39 1994 Replacement Yes d/0

$l-3, /!W

FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT (Supplement)

As Required by the Provisions of ASME Code Secuan XI Program # 98-087thru 98-103 WR# 980019145-01 thru 24

1. Owner:

Commonwealth Edison Date:

01/27/1999 bt" tai P.O. Box 767 Chicago,IL 60690 Sheet: 3 of 3 Unit:

1

2. Plant' Quad Cides Nuclear Power Statim Comed 22710 206th Ave. North, Cordova, IL 61242 kepar urranamuon P.a ba, Job Na, etc.

Type Code Symbol Stamp:

N/A D. Work Performed by-Quad Cibes Nuclear Station Authonzation No.:

E/A 22710 206th Ave. North, Cordova, IL 61242 Expirauon Date:

E!/6

h. Identificadon of System Control Rod Dnve, Class 1 I

5. ( ) Applicable Cmstruchon Code: ASME Section III 1965 Editim, W-1965 Addenda, 1365 Code Case (b) Applicable Editim of Secdon XI Utihted for Repairs or Replacements: 1989 Edinon, N/A Addenda. N/A Code Case

s. Identificadon of Components Repaired or Replaced, and Replacement Compments: Contmued Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificatim Built Replaced, or Code No.

Replacement Stamped (Yes or f

No) l Control Rod Dnve GE 8355 N/A 1 300-42-47 19 %

Replaced Yes j Control Rod Dnve GE A8510 N/A 1-300-42-47 1988 Replacement Yes l Control Rod Dnve GE 674 N/A 1 300-46-23 1968 Replaced Yes l Control Rod Dnve GE A8511 N/A 1-300-46-23 1988 Replacement Yes l Control Rod Dnve GE A9013 N/A 1 300-50-23 1992 Replaced Yes I Control Rod Dnve GE A9042 N/A 1 300-50-23 1992 Replacement Yes Control Rod Dnve GE 3581 N/A 1-300-50-35 1988 Replaced Yes Control Rod Dnve GE 8692 N/A 1-300-50-35 1978 Replacement Yes Control Rod Dnve GE 189 N/A 1-300-54-23 1968 Replaced Yes Control Rod %ve GE 299 N/A 1-300-54-23 1967 Replacement Yes Coni ol Rod unve GE D1496 N/A 1-300-54-27 1970 Replaced Yes Control Rod Dnve GE 7930 N/A 1 300-54-27 1970 Replacement Yes Control Rod Dnve GE 571A N/A 1 300-58-27 1968 Replaced Yes Control Rod Dnve GE 6540 N/A 1 300-58-27 1974 Replacerrent Yes W /.

N 7,/TVT

FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by th3 Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98105 WR# 980016263-01 7wner:

Commonwealth Edison Date:

12-09-98 P.O. Box 767, Cnicago, IL 60690 Sheet: 1 of 1 Unit:

I

'lant:

Quad Cities Nucle.v Power Station Comed 22710 206th Ave. Nodt, Cordova, IL 61242 Repan orsamauan P.O. NoJob No., ac.

Type Code Symbol Stamp:

N/A Work Performed by-Quad Cities Nucl:ar Statim Authorizatim No.:

E/6 22710 206th Ave. North,Cordova IL 61242 Expiration Date:

U,/6

Identification of Systent Main Steam, Class I (a) Applicable Construction Code

ASME Section III 1965 Edition, S-66 Addenda, N/A Code Case (b) Applicable Editicn of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A Code Case i

l dentification of Components Repaired or Replaced, and Replacement Compcments:

Name of Name of Mfrs. Ser.

Nat'l Other Year Repaired.

ASME Component Mfr.

No.

Bd.

Identificaticn Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Safiy Valve Dresser BK7060 N/A 1-0203-3E UNK Replaced Yes l Saf 'y Valve Dresser BK7062 N/A 1-0203-3E UNK Replacement Yes Description of Work: Replaced the Electromatic Relief Valve in accordance with the W R.

I Tests Conducted: Hydrostatic Pneumatic Nommal Operatmg Pressure Other 5 Pressure 1014 psi Test Temp. 212 *F Remarks: Performed VT-1 inst ection on itilet bottine.

Performed VT-2 dunne Class 1 System leakare Test.

CERTIFICATE OF COMPLIANCE e certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code.Section XI repair ornplacement rpe of Code Symbol Stamp N/A -Comed 10CFR50 Are B O A Procram rtificate of Authmzation No.

N/A Expirauon Date N/A gned edlAjd M.

M 4M fE4p Date BeicempEc_ 4 1946 a

{ ownegorowner sowpee. Tide CERTIFICATE OF INSERVICE INSPECTION be undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors

l the State of Il!inois. and employed by Hanford Steam Bniler Insnection & Insumnce Co.

of Hartford. CT have mspected the mponents desenbed in this Owner's Report during the period W D-V8 to /-G-M

, and state that to the best of my knowledge and lief, the owner has performed exammations and taken corrective measures described in this Owner's Report in accordance the requirerrents of the

ME Code. Secuan XI.

' signing this certificate. neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective asures described in this Owner's Report. Purthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or peny damage or a loss of any Lind ansing from or connected with this inspection.

/

Commissions

[O y

M M. 0,

19 W ite

7 FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE 1

Program # 98-020 & 98-033 WR# 980026256-01 & 02 I. Owner:

Commonwealth Edison Date: 01/11/1999 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710206th Ave. North,Cordova,IL 61242 Remar orsanimuon P.O. Na, Job Na, ac.

Type Code Symbol Stamp:

N/A

3. Work Performed by-Quad Cities Nuclear Station Authertzatim No.:

N/6 22710 206'h Ave. North, Cordova, IL 61242 Expiraticn Date:

N_/.6

6. Dentification of System Main Steam, Class 1

5. (a) Applicable Construction Code: USAS B31.1 1%7 Editim, Nme Addenda, N/A CodeCase (b) Applicable Edition of Section XI Utihzed fa Repairs or Replacements: 1989 Edition, N/A Addenda, E2L Code Case E. Identificatim of Compments Repaired or Replaced, and Replacement Compments:

Name of Name of Mfrs. Sct, Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificaticn Built Replamd, or Code No.

Replammmt Stamped (Yes or No)

Pipe Flange N/A N/A N/A 1 3026-B N/A Ranaired No

' Description of Work: Repaired defects in flance face and replaced bolting as rectured by the WR.

Tests Conducted-Hydrostatic Pneumatic NominalOperatmg Pressure Other Q Pressure 1012 psi Test Temp. 212 'F 0

l. Remarks: Performed a VT-3 m flange face after repairs Performed a VT-2 durine Class 1 System Leakare Test.

Nfuiumi VT-1 on the repla~ ment boltinr.

CERTIFICNIE OF COMPLIANCE

% certify that the statements made in this report a e correct and this repair conforms to the rules of ASME Code Section XI sepair orsopiecement Type of Code Symbol Stamp N/A - Comed 10CFR50 Ano B. O A Program

.crtificate of Authorization No.

N/A Expiration Date N/A iigned Mll ant.

fat (.ete N a Date dAvaJudbM fh 19 44 8

l y

downer or Owner a pessmee,Taus 8*

l CERTIFLCATE OF INSERVICE INSPECTION the undersigned. holding a valid corranission issued by the National Board of Boiler and Pressure Vessel Inspectors h the State of minnie. and enployed by Hartford Steam Boiler 6-C.- & Inswan~ Co of Hartfwd. CT have iaspected the amponents described in this Owner s Report during the period lla * '/ 6 to 1-37-'#f

, and state that to the best of my knowledge and clief, the owner has pr '

4 exanunations and taken corrective rneasmus described in this Owner's Report in accordance the reqturements of the SME Code,Section XI.

f signing this certi5 case, neither the inspectcr nor his employer makes any warranty, expressed cr implied, conceming the exammations and car r.aswes described in this Owner's Report. Purthermwe, neither the inspector nor his employer shall be liable in any manner for any personal irsury or hperty damage or a Iws of any kind arising from or connected with this inspection.

/ O Y-Corrunissions D

47,

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19 d ute e

FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by th? Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE l

Program # 98-021 WR# 980026266-01

!. Owner: Commonwealth Edison Date:

11/18/98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1 LPlant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova. IL 61242 a,., ors.munaa r.o. sa. aob sa..ic.

Type Code Symbol Stamp:

M L Work Performed by-Quad Cities Nuclear Station Authorization No.:

E!/6 22710 206th Ave. North, Cordova IL 61242 Expirauon Date:

E!&

L Identificatim of System: Neutron Monitarmg, Class I l ( ) Applicable Construction Code: 2}]{pection III 1%5 Edition,.Nggg., Addenda,,,M/,, Code Case A

l (b) Applicable Edition of Section XI UtiL2d for Repairs or Replacements: 1989 Editicri, N/A Addenda, F_/6. Code Case l Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfts. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code 3

No.

Replacement Stamped (Yes or No) i

> LPRM Flange GE N/A N/A 1-0756 3217, N/A Replacement No l-0756-3233

)

l Description of Waric Replaced boltine as reouired by WR.

l Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure F/6 Psi Test Temp. E!A 'F l Remarks: VT-1 performed on replacement boltine.

CERTIFICATE OF COMPLIANCE e certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code,Section XI

1. of Code Symbol Stamp N/A - Comed 10CFR50 Ann B. O A Procram Rificate of Authorization No.

N/A Expiration Date N/A NIAAd w, rw c,ein re.4a Date Lunev I4 1949 gned

}

Okt er Ownst :Deassume. Title 8l l

CERTIFICATE OF INSERVICE INSPECTION the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors p the State of niin and errployed by Hartford Steam Boiler Inmection & Insurance Co of Hartford. CT have inspected the mponents described in this Owner's Report during the period Ah te,/n y to //4/ /f4, and state that to the best of my knowledge and lief, the owner has performed examinations and taken ccsTective measures desenbed in this Owner's Report in accordance the requtrements of the fME Code.Section XI.

[ signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied concerning the examinations and rrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any anal injury or property damage or a loss of any kind arising fmm or connected with this inspection.

-[ O Commissions

1. 3 l

f ste

~ S/

19 6 _

/

l

FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by th3 Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-022 WR# 980021123-01

1. Owner: Commonwealth Edison Date:

11/07/98 P.O. Box 767, Chicago IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 nepar ursamz.um ro. Na, Job Na, ac.

Type Code Symbol Stamp:

N/A

3. Work Performed by:

Quad Cities Nuclear Station Authonzation No.:

N. /A_

22710 206th Ave. North, Cardova. IL 61242 Expiration Date:

N_/A

4. Identification of System Main Steam. Class 1

5. (a) Applicable Construction Code: ASME Sect 11I1965 Edition, S-1966 Addenda. N/A Code Case (b) Applicable Edttian of Section XI Utilized for Repairs or Replacements: 1989 Edition. N/A Addenda, N/A Code Case S. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year Repaired.

ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Safr.y Valve Consolidated BL 1120 N/A 1-0203-4A N/A Replacement Yes Safety Valve Consolidated BK 7176 N/A l-0203-4 A N/A Replaced Yes i'. Description of Work: Removed / replaced the Main Steam Safety Valve and bottine as per the WR.

L Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other D Pressure 1013 psi Test Temp.112 *F

). Remarks: Performed a VT-2 on the replaced valve and renaired flance durine pressure test.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair conforms to the rules of ASME Code.Section XI rep, a replacemes Type of Code Symbol Stamp N/A - Comed 10CFp50 Ann B. O A Procram krtificit of Authanzation No.

N/A Expiration Date N/A NY]0AY tw

$1 &cn ' trAn Date Yomier 9

194b igned y opa a m t>

s uu.-

i CERTIFICATE OF INSERVICE INSPECTION

, the undersigned holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors nd the State of minois. and employed byllartford Steam Boiler inmeetion & Insurance Co of Hartford CT have inspected the unponents described in this Owner's Report during the period 3 /W/f B to //A '/99

. and state that to the best of my knowledge and clief, the owner has perfumed examinations and taken corrective measures described in this Owner's Report in accordance the requirerrents of the SME Code.Section XI.

ly signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and arrective rneasures described in this Owner's Report. Furthermre. neither the inspector nor his employer shall be liable in any ianner for any rsonal injury or property damare or a loss of any kind arising from or connected with this inspection.

[

Commissions Mf b

N 19 M pate

/

I FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT j

As Required by th: Provisions of ASME Code Section XI i

QCAP 0307-20 Revision 6 CGE Program # 98-036 WR# 980021123-03 I, Owner: Commonwealth Edison Date:

11/07/98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1 LPlant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova,IL 61242 kwear orsamzat=a r.o. ba. Job wa..ic.

Type Code Symbol Stamp:

H/6

l. Work Performed by-Quad Cities Nuclear Station Authorization No.:

N/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/6 L. Identification of System Main Steam. Class 1

i. (a) Apphcable Construction Code: USAS B3'.1 1967 Edition, None Addenda, N/A CodeCase (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A CodeCase

i. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfts. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Pipe Flange N/A N/A N/A l-3026-A UKN Repaired No

' Description of Work: Renaired nine flance by machininc as ter the WR.

. Tests Conducted: Hydrostatic O Pneumatic Nominal Operating Pressure O Other @ Pressure 1013 psi Test Temp. J.J2 'F

. Remarks: Performed MT and VT-3/4 on machined areas. performed a VT-2 durine pressure test.

CERTIFICATE OF COMPLIANCE We cenify that the statements made in this report are correct and this repair confonns to the rules of ASME Code,Section XI repen errepwemes type of Code Symbol Stamp N/A - Comed 10CFR50 Ann B O A Procram

eruficate of Authorization No.

N/A Expiration Date N/A

.igned MM #ctL fu Mevr t. san Date MwegmM 8) 194 6 V

obner er Owner s Desagnet, Istis CERTIFICATE OF INSERVICE INSPECTION the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors tid the State of Illinois and etrpoyed by Hartford Steam Boiler ins wetion & Insurance Co of Hartford CT have inspected the xnpanents described in this Owner's Report during the period 4 l4 ' 4e to I/f>lf9

. and state that to the best of my knowledge and clief. the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the SME Code.Section XI.

y signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied. conceming the examinations and wrective measun:s described in this Owner's Report. Furthermore, neither the inspector nor h. t employer shall be liable in any manner for any ersonal irtiury cr property damage or a loss of any kind arising from or connected with this inst ection.

Ibw Commissions 96 3

m. n r.

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.2 e 19 T'I tate l

FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307 20 Revision 6 CGE Pro' gram # 98-037 WR# 980022ti93-01

1. Owner: Commonwealth Ediscri Date:

11/07/98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 R=rar ors===u== P o baja 6 No ac.

Type Code Symbol Stamp:

Fi/6

3. Work Performed by:

Quad Cities Nuclear Station Authorization No.:

F./A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

4. Identification of System: Core Spray, Class 1

5. (a) Applicable Construction Code: USAS B31.11%7 Edition, None Addenda, N/A CodeCase (b) Applicable Editical of Section XI Utihzed for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A CochCase

6. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repatred, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Piping N/A N/A N/A 1 1402-35B N/A Replacement No

7. Description of Work: Replaced valve. pine and oice fittines by weldine as reouired by WR.

'. Tests Conducted: Hydrostatic Pneumatic NominalOperatingPressure O Other Pressure N/& psi Test Temp. H/A *F

7. Remarks: Replaced components are exempt from ASME Section XI replacement / pressure tests recuirements.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement confcrms to the rules of AShG Code,Section XI pur erreplacemen Type of Code Symbol Stamp N/A - Comed 10CFR50 Ann B. O A Program Certificate of Authcrization No.

N/A Expiration Date N/A signed MN LL fer G*n t %

Date hb#wim.c#

1l 19 at 6 F

Owns er Owur s Deegasc. Tals I

f CERTIFICATE OF INSERVICE INSPECTION L the undersigned. holding a valid ccuranission issued by the National Board of Boiler and Pressure VesselInspectors the State of minnie. and employed by Hartford Steam Boner Inmection & Insurance Co.

of Hartford CT have inspected the ts described in this Owner's Report during the period J/2 Aff to 2//IM

, and state that to the best of my knowledge and belief, the owner has performed exannnations and taken corrective measures described in this Owner's Report in accordance the requirements of tbc LSME Code,Section XI.

By signing this certi6cste, neither the inspector nor his enployer makes any warranty, expressed or implied, conceming the exammations and xrrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any wrsonal injury or property damage or a loss of any kind arising frorn or connected with this inspection.

M 6.

U Commissicais Pate I a B/,

19 ft/

I

F3RM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Secti::n XI QCAP 0307-20 Revision 6 CGE Program # 98-039 WR# 980033792-01

1. Owner:

Commonwealth Edison Date: 07/29/98 P.O. Box 767, Chicago,IL 60690 Sheet: 1 of I Unit:

1

2. Plant:'

Quad Cities Nuclear Power Statien Comed i

22710 206th Ave. North, Cordova, IL 61242.

RCPair Organizauon P.O. No., Job ho.. etc j

Type Code Symbol Stamp:

H%

3. Work Performed by:

Quad Cities Nuclear S ation Authorization No.:

H%

22710 206th Ave. North, Cordova. I' 61242 Expiration Date:

Fl%

1 1

8. Identific-lion of System: Standby Liquid Control System, Class 2

)

i. (n) Applicable Construction Code: USAS B31.1 1%7 Edition. _HODe. Addenda, N!%. Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition,.Fl%. Addenda, N/A Code Case j

i. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year Repaired.

ASME C:mponent Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or l

No)

Vdve Inlet Plug Conax Control #

N/A N-38139-01 N/A Replacement No l

20046 Trigger Assembly Conax S/N 82 N/A N-27022-02 N/A Replacement No I

. Description of Work: Replaced the trierer assembly and olue after the surveillance as reauired by the WR.

. Tests Conducted: Hydrostatic Pneumatic Nominal Operr. ting Pressure 5 Other Pressure D.QQ psi Test Temp. 21 'F

. R: marks: Performed a VT-2-1 durine the system functional test.

CERTIFICATE OF COMPLIANCE Ve c;rtify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code Section XI repair or replacement rype of Code Symbol Stamp N/A - Comed 10CFR50 Ann B. O A Procram lertificate of Authorization No.

N/A Expiration Date N/A igned Ml M

1. 4f 66wr> Lm:> Date MLY 9

1940

]

twner or owner s Designee. Title CERTIFICATE OF INSERVICE INSPECTION the undersigned holding a valid commission issued by the National Board d Boiler and Pressure Vessel Inspectors id the State af Illinois. and employed t)y Hanford Steam Boiler Insnection & Insurance Co of Hanford. Cr haveinspected the imponents desenbed in this Owner's Report during the period 4 - T* TSP to 2?2-T4, and state that to the best of my knowledge and tlief, the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the SME Code,Section XI.

y signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied conceming the exammations and corrective casures described in this Dwner's Repon. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or perty damage or a loss of any kind arising from or connected with this inspection.

I ['

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FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions cf ASME Code Section XI OCAP 0307-20 Revision 5 CGE j

Program #.96-040 WR# 980022479-01

1. Owner: Commonwealth Edison Date: 06/08/98-

'l&p ag9 P.O. Box 767 Chicago,IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova,IL 61242 Repair Organizauon P.O. No., Job No., cic.

Type Code Symbol Stamp:

N/A

3. Work Performed by:

Quad Cities Nuclear Station Authorization No.:

N/A 22710 206th Ave. North, Cordova,IL 61242 Expiration Date:

N/A

4. Identification of System: High Pressure Coolant Injection Cooling Water, Class 2

5. (a) Applicable Construction Code: USAS B31.11%7 Edidon, None Addenda,.HlA. Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: E32. Edition, l!/A. Addenda,.E/6. Code Case

6. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Check Valve C & S Valve N/A N/A 30SMF-402 N/A Replaced No Check Valve C & S Valve 94-2641-N/A 30SMF-402 N/A Replacement No 01001

7. Description of Work: Reolaced the Check Valve inaccordance with the work reauest.

Tests Conducted: Hydrostatic Pneumatic NominalOperatingPressure @

Other Pressure 232 psi Test Temp.11 'F

9. Remarks: Performed a VT-2-1 oost reolacement.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this ReolacemenL conforms to the rules of ASME Code,Section XI repair or - p-r - -

Type cf Code SymbolStamp N/A - ComM 10CFR50 Ano B. O A Pronram Certificate of Authorization No.

N/A Expiration Date N/A 2igned M w.

M '

- IJAb Date dutV ld 19 4 6 7 ~ ' Gwnir 6r Owner's Designac. Tatic CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors ed the State of 111 %

. and employed by Hartford Steam Boiler Insnection & Inmrance Co.

of Hartford. CT have inspected the components described in this Owner's Report during the penod to

, and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures desenbed in this Owner's Report in accordance the requirements of the MME Code,Section XI.

By signing this certificate, neither the inspector not his employer makes any warranty, expressed or implied. conceming the examinations and corrcctive measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury perty da ge or a loss of any kind arising from or connected with this inspection.

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FORM NIS 2 OWNERS REPORTOF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307 20 Revision 6 CGE

1. Owner: Commonwealth Edison Program # 98-115 WR# 980088960-01 Date:

1/30/99 P.O. Box 767, Chicago,IL 60690 Sheet: I of 1 Unit:

1

2. Plant Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova. IL 61242 kepau Orsanunuon Eo. Na. Job No etc.

Type Code Symbol Stamp:

N/A

3. Work Performed by.

Quad Cines Nuclear Station Authorizatim No.:

N/A 22710206th Ave. North,Cordova,IL 61242 Expirabon Date:

N/A

4. Identification of System Recirculanon, Class 1

5. ( ) Applicable Construction Code: ASME Section I 965 Edition, Ems Addenda, Ef/A CodeCase (b) Apphcable Edition of Secticai XI Utilized for Repairs or Replacements:.1989 Edition. N/A Addenda, N/A Co

6. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificatim Built Replaced, or Code No.

Replacement Stanped (Yes or No)

Pipmg GE N/A N/A 1-0202A(B)-28" N/A Replacement No

7. Desenption of Work Replaced boltine mr.terial associated with decontammation flanted connections as reo

' Tests Conducted-Hydrostatic Pneumatic 0 NommalOperatmg Pressure Other O Pressure psi Test Temp.

'F

). Remarks: Performed VT-1 on replacement boltine.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacemen_t_ conforms to the rules of AS repeu orreplaement Type of Code Symbol Stamp N/A - Comed 10CFR50 Arv B. O A Prcwam

~crtificate of Authorization No.

N/A Expiration Date N/A Ligned MOri

For_,

54 4&c.P wp Date s }MJ vu_Y '66 19 44 y

owner ar owner s pessnee.nue i

es CERTIFICATE OF INSERVICE INSPECTION

, the undersigned, holding a valid commission issued by the National Board of Boiler and P. essure Vessel Inspector td the State of t h is

. and employed by Hartford Steam Boiler b.-% & 's m Co.

of Hanford. CT have inspected the u m caponents described in this Owner's Report during the period 4/a//ff' to M//ff

lief, the owner has N.us4 examinations and taken corrective measures described in this Owner's Re SME Code,Section XI.

y signing this czruficate, neither the instector nor his emplopt makes any warranty, expressed or implied casures described in this Owner's Report. FwGoum neither the Inspector nor his emplogr shall be liab e

tipeny damage cr a loss of any kind arising from or connected with this inspection.

[

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\\9 99

FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Secuan XI i

QCAP 0307-20 Revision 6 CGE Program # 98117,98-124 WR# %0038277-01,03

1. Owner: C.mionwealth Edison Date: 01/04/99 P.O. Box 767, Chicago, IL 6%90 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Cides Nuclear Power Statim Comed 22710 206th Ave. North, Cordova, IL 61242 Kerir Orsammuon P.O. 6o.. Job No.. ac.

Type Code Symbol Stamp:

N/A

3. Work Performed by-Quad Cities Nuclear Station Authorization No.:

N/.6 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

F_/A

4. Identific-tica of System: Reactor Core Isolation Cooling, Class 1

5. (I) Apphcable Construction Code: USAS B31.1 1%7 Edition, None Addcmda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replamments: 1989 Editicn. Fl6_ Addenda,,and N/A Code Case

5. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other.

Year Repaired.

ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Gate Valve Crane 783U N/A I-1301-17 N/A Replacement No I

'. Desenption of Work: Overhaul valve. replaced valve disc and tack weld valve body to voke as reouired by WR.

Tests Cmducted: Hydrostatic Pneumauc 0 Nominal Operatmg Pressure Other G Pressure 1014 psi Test Temp.2]7 'F

' Remarks: Performed a VT-2 and a LLRT on the replaced disc.

Performed MT on tack weld.

CERTIFICATE OF COMPLIANCE We certify tut the statements made in this report are correct and this replacement conforms to the rules of ASME Code.Section XI repair or reptacement Type of Code Symbol Stamp N/A -Comed 10CFR50 Ano B. O A Procram Mtificate of Authcrization No.

N/A Expirauon Date N/A igned II/li - (rc, fof AEaup lee Date dmoad 9

1944 af

{>wner or Owner a Penagnee. Tide I

I CERTIFICATE OF INSERVICE INSPECTION

[ the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors fid the State of111innis. and employed by Hartford Steam Boiler inmection & Insurance Co of Hartford. CT have inspected the pmponents described in this Owner's Report during the period to/r/( F to il2 5' M. and state that to the best of my knowledge and belief, he owner has performed crammations and taken corrective measures desenbed in this Owner's Report in accordance the requirements of the ASME

' ode.Section XI.

y signing this certificate. neither the inspector nor his employer makes any warranty, expressed or implied. conceming the exanunations and corrective

..easures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or anperty damage or a loss of anykind arising from or connected with this inspection.

-[b Commissions

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FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by th: Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE

1. Owner:

Commonwealth Edison Program # 98-121 WR# 980061950-01 Date:

1/29/99 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of I bit:

1

2. Plant-Quad Cities Nuclear Power Statim ComFA 22710206th Ave. North, Cordovt. IL 61242 acpur orsamzauon P.o. No.. Job No.. ac.

Type Code Symbol Stamp:

N/6

3. Work Performed by-Quad Cities Nuclear J'ation Authortzattm No.:

N/6 22710 206th Ave. North, Cordova, IL O242 Expiratim Date:

N/A

4. Identification of System Neutrm Mmitering, Class 1

5. (r.) Applicable Cmstmetion Code:

i

_ASME Section III 1%5 Edition, _ Nane Addenda, N/A Code Case

- (b) Applicable Editim of Section XI Utihzed for Repairs or Replacements: 1989 Edition, N/A Addenda. N

6. Identification of Components Repaired or Replaond, and Replacement Compments:

Name of Name of Mfrs. Scr.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or LPRM Flange GE 35-55878-1 N/A 1-0756-4809 N/A Replacement No No)

7. Desenption of Work: Replaced LPRM flance and associated boltine as reouired by the WR B. Tests Cmducted: Hydrostatic Pneumatic 0 Nominal Operaung Pressure Other @

Pressure 1014 psi Test Temp.2.12 *F

7. Remarks: Performed VT-1 on replacement bo! tine.

Performed VT-2 dunne Class 1 Swtem Leakare Test.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to the rules of repar orreplacement Type of Code Symbol Stamp N/A - Comed 10CFR50 Ann B. O A Firemu htificate of Authorization No.

N/A Expiratim Date N/A igned(Y/d ve c f6% /,s2WP M4 b Date dwtAc_V M 1999 y

I OwnerorOwner sDengnac.Due CERTIFICATE OF INSERVICE INSPECTION

.the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors 4 the State of hrs and employed by Hartford Steam Boiler kwcGoa & Insu=.e Co of Hartford cr _ haveinspected the rnpcments described in this Owner's Report during the period A///ff to 24 /#4 ilief, the owner has performed exammations and taken corrective measures described in this Ow EME Code,Section XI.

r signing this certificate. neither the inspector nor his employer makes any warranty. expressed or implied insures described in this Owner's Report. F=G-m, neither the laspector nor his employer shall be n corrective gerty damage or a loss of anykind arising from or connected with this inspection.

/

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FORM NIS.2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Sectim XI OCAP 0307 20 Revision 6 CGE k

Program # 98123 WR# 960083129-01

1. Owner:

cnmmnnwealth Edison Date: 02/05/1999 P.O. Box 767, Chicago, IL 60690 Sheet: I of 1 Unit:

I

t. Plant-QuadCities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 xepaa ursam.uon to. so.. Job so...c.

Type Code Symbol Stamp:

N/A

l. Work Performed by-Quad Cities Nuclear Station Authertzatim No.:

N/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N//6

l. Identificatim of System Core Spray, Class I

i. (a) Applicable Construction Code USAS B31.1 1%7 Edition,.Hgle, Addenda, N/A Code Case e

(b) ApplicLble Editicn of Section XI Utilized for Repairs or Replacements: 1989 Edition N/A Addenda, N/A CodeCase

i. Identification of Components Repaired or Replaced, and Replacement Compments:

Name of Name of Mfrs. Ser.

Nat1 Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificatim Built Replaced, or Code No.

Replacerrat Stamped (Yes or No)

Piping / Valves Various N/A N/A 1 1423A-3/4"-A unknown Replamment No Desenptim of Waric Replaced pipine and valves associated with coualizine drain line as reautred by the WR.

Tests Conducted: Hydrostatic Pneumatic Nominal Operatmg Pressure Other Pressure psi Test Temp.

'F Remarks: No pressure testine recurred.

CERTIFICATE OF COMPLIANCE Ve certify that the statements trade in this report are correct and this replacement cmforms to the rules of ASME Code,Section XI mpaa orap 6acemem rype of Code Symbol Stamp N/A - Comed 10CFR50 Ann B. O A Procram lertificate of Authortzation No.

N/A Expiration Date N/A gned W4, 14r Mine LaAb Date Ms,aww&cP 9 19 D y

owner a-owner ~s peesnee Tius CERTIFICATE OF INSERVICE INSPECTION the undersigned, holding a valid canmission issued by the National Board of Boiler and Pressure Vessel Inspectors us the State of 111ind<. and enployed by Hartford Steam BMier inenennn & Insurance Co of Hartford cr have inspected the unpoents described in this Owner's Report during the period

/o/f/M to A/EIM

, and state that to the best of my knowledge and ilief, the owner has performed exammations and taken corrective measures described in this Owner's Report in accordance the requirements of the SME Code.Section XI.

r signing this cestificate, neither the inspector nor his enployer makes any wammty, expressed or irrplied, concerning the exannnations and corrective ensures described in this Owner's Report. Purthermore, neither the inspector nor his employer shall be liable in any manner for any personal irdury or operty damage or a loss of any kind arising from or connected v ith this inspection.

d

• Commissions YV03 fb 7

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Secuan XI j

QCAP 0307-20 Revision 6 CGE Program # 98-138 WR# 980107392-01 Omter: Commonwealth Edison Date:

12-15-98 P.O. Box 767, Chicago,IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant-Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 Reimar orsaniauon P.O. Na, Job No., ac.

Type Code Symbol Stamp:

E

3. Work Performed by:

Quad Cities Nuclear Stauan Authonzation No.:

E!A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

E!A

4. Identification of System Main Steam Class 1

5. (a) Applicable Construction Code ASME Section III 1965 Edition, S-1966 Addenda, N/A Code Case (b) Applicable Editicn of Section XI Utilized for Repairs or Replacements: 1989,Editicut, N/A Addenda, and N/A. Code Case

5. Identificaticxi of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Staroped (Yes or No)

Reh~f Valve Dresser Industnes BX00290 N/A 1-0203-3B UNK Replaced Yes Reliif Valve Dresser Industnes BK7063 N/A 1-0203-3B UNK Replacement Yes

' Desenpuan of Waric Replaced the relief valve as reomred by the WR.

. Tests Conducted: Hydrostatic Pneumauc Nommal Operatmg Pressure Other 5 Pressure 1014 psi Test Temp. 217 'P

. Remarks: Performed VT-2 on valve replacement.

Performed VT-1 on replaced boltine.

CERTIFICATE OF COMPLIANCE Ve certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code,Section XI repair or replacement fype of Code Symbol Stamp N!A -Comed 10CFR$0 Ann B. O A Procram

eruficate of Authonzation No.

N/A Expiranon Date N/A igned M rtd. T& r;,rwo 1-rh Date 13ru m e s L, 19 ah y ~ O$cr or Owner s Desgnee.TalIc '

CERTIFICATE OF INSERVICE INSPECTION the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors id the State of minnis. and employed by Hartford Stearn '4 oiler Insnection & Insurance Co.

of Hartfoni CT have inspected the unpanents described in this Owner's Report during the period V2tk('

to

, and state that to the best of my knowledge and lief the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the SME Code,Section XI.

v signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied. concerning the examinations and corrective asures desc:ibed in this Owner's Report. Furthermore. neither the Inspector nor his employer sball be liable in any manner for any personal iriury or eny danage or a loss of any kind arising from or connected with this inspection.

/

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' Commissions M3

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-139 WR# 980024210-01

, Owner:

Commonwealth Edison Date: 01/26/99 P.O. Box 767, Q1icago, IL 60690 Sheet: 1 of 1 Unit:

1

..Aant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 Repur Orsamzauon P.O. No.. Job ho., etc.

Type Code Symbol Stamp:

NM

. Work Perfcrmed by:

Quad Cities Nuclear Station Authartzetim No.:

NB 22710 206th Ave. North, Cordova, IL 61242 Expiranon Date:

N%

, Identificadon of System Residual Heat Removal, Class 1 L (3) Applicable Constmcuan Code: USAS B31.11%7 Ediucn, None Addenda, N/A CodeCase (b) Applicable Editim of Sectica XI Utihzed for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A CodeCase L Identificauon of Components Repaired or Replaced, and Replacement Compments:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Mecharucal PSA 30694 N/A 1 1025-122 UNK Replamd UNK Snubber Mechanical PSA 8806 N/A 1 1025-122 UNK Replacement Yes Snubber Descriptien of Work Reolaced the mechanical snubber as reautred by the WR.

Tests Ccuducted: Hydrostatic Pneumatic NominalOperatmg Pressure O Other Pressure psi Test Temp.

'F Remarks: Performed a VT-3 insoection on the reolaced snubber.

pio cressure testine reouired.

CERTIFICATE OF COMPLIANCE Fe certify that the statements made in & report are correct and this reolacement conforms to the rules of ASME Code,Section XI repaar cruspiacemen

ype of Code Symbol Stamp N/A - Comed 10CFR50 Ato B. O A Program eruficate of Authertzation No.

N/A Expiratica Date N/A igned -

Nt ' *L MT map fAbDate M w oartV f/a 19 44 J OwdurnrOwaar'sDestgaet,Tiue i

/8 l

CERTIFICATE OF INSERVICE INSPECTION the undersigned, holding a valid cr==rmasion issued by the National Board of Boiler and Pressure VesselInspectors

$ the State of miaak. and employed by Hartford Steam Boiler ! n +a & Insurmaer Co of Hartford CT have inspected the wriponents desmbed in this Owner's Repwt during the period I/efe/ft to / -17 M _, and state that to the best of my knowledge and Llief, the owner has performed exammations and taken corrective measures described in this Owner's Report in acccrdance the requirements of the EME Code,Section XI.

k signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied. -% the exammations and corrective basures described in this Owner's Report. Furthermse, neither the Inspector act his employer shall be liable in any manner far any personal injury or l party damage or a luss of any kind ansing from or connected with this inspection.

Commissions fA7 d w n,-.-r b

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FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307 20 Revision 6 CGE Program # 98-141 WR# 980023968-01

, Owner:

Cnmmnnwealth Edason Date: 02/13/99 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit: 1

.. Plant:

Quad Cities Nuclear Power Statien Comed 22710 206th Ave. North, Cordova, ~L 61242 Rapa r Organizauan P.O. No., Job No., eac, Type Code Symbol Stamp:

E/&

. Work Peformed by-Quad Cities Nuclear Station Authorizatim No.:

N/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

. Identification of System Residual Heat Removal, Class I

r. (1) Applicable Constructica Code: USAS B31.1 1%7 Edition Mg}.t_ Addenda, N/A Code Case (b) Applicable Editim of Section XI Utilized for Repairs or Replacements: 1989 Editien, N/A Addenda, N/A Code Case

5. Identification of Components Repaired or Replaced, and Replacement Compments:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificatim Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Mechanical PSA 9481 N/A 1 1025-123 unknown Replaced Yes Snubber Mechanical PSA 8808 N/A 1 1025-123 unknown Replacement Yes Snubber Desenption of Waric Replaced the mechanical snubber as reautred by the WR.

. Tests Cmducted: Hydrostatic Pneumatic NominalOperating Pressure Other Pressure psi Test Temp.

'F L Remarks: Performed a VT-3 inspection on the replaced snubber.

No pressure testme reautred.

CERTIFICATE OF COMPLIANCE Ve certify that the statements made in this report are correct and this replacement cefams to the rules of ASME Code,Section XI repair arrepdacement Type of Code Symbol Stamp N/A - Comed 10CFR50 Ann B. O A Program ertificate of Authorizatim No.

N/A Expiration Date N/A gned Ib's' #co 16E dErMP (4aa Date k h oecf 185 1999 g

gwmer or owner.Dessaee, nue s

a -

m CERTIFICATE OF INSERVICE INSPEC'I1ON the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors the State of minnie and employed by Hartford swam Bailer = S-, & Insur== Co.

of Hartfani Cr have inspected the nts described in this Owner's Report during the period

//-20-ff to 2"/2" ??, and state that to the best of my knowledge and lief. the owner has performed examinations and taken arrective measures described in this Owner's Report in accordance the requirenants of the ME Code, Sectica XI.

hy signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied. conceming the examinations and c asures described in this Owner's Report. Furthermore. neither the Inspector nor his employer shall be liable in any manner for any personal irsury or y damage or a loss of any kind arising from or connected with this inspection.

[h Corrrnissions 843

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACFJdENT As Required by ths Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-146 WR# 980113021-01 Owner:

Commonwealth Edison Date:

12-23-98 P.O. Box 767, Chicago, IL 60690 Sheet: I of I Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 Repan orsaruauon P.o. No.. Job bo.. eic.

Type Code Symbol Stamp:

N/A

3. Work Performed by-Quad Cities Nuclear Station Authortzatim No.:

N/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N14

6. Identification of System Main Steam, Class 1

5. (a) Applicable Construction Code: ASME Section III 1%5 Edition, S-66 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utihzed for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A Code Case

s. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Safny Valve Consolidated Valve BK6295 N/A 1-0203-4D UNK Replaced Yes Saf ty Valve Consolidated Valve BK6266 N/A 1-0203-4D UNK Replacement Yes

7. Desenption of Work The Safety Valve was replaced as reouired by the WR.

i. Tests Conducted: Hydrostatic Pneumatic O Nominal Operating Pressure Other @

Pressure 1014 psi Test Temp. 217 *F P. Remarks: Performed VT-2 durtne the Class 1 Leakare Test.

CERTIFICATE OF COMPLIANCE We cenify that the statements made in this report are correct and this replacement confctms to the rules of ASME Code.Section XI sepna orrepiscemera Type of Code Symbol Stamp N/A - Comed 10CFR50 Are B. O A Procram ertificate of Authcrization No.

N/A Expiration Date N/A iigned odll mut.

f!nr dance unap Date Ms -W 10 1948

/ ' ~ Obser or owder~s Desagnes.Taus i

CERTIFICATE OF INSERVICE INSPECTION

. the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors ad the State of Illinait and employed by Hartford Steam Boiler Insnection & Insurance Co.

of Hartford. CT have inspected the omponents described in this Owner's Report during the period r/- S-9 ff to t-F-99

, and state that to the best of my knowledge and

1ief. the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the SME Code.Section XI.

ly signing this certificate. neither the inspector nor his employer makes any warranty, expressed or implied, conceming the examinations and corrective

.aswes described in this Ovmer's Report. Furthermore. neither the inspector nor his employer shall be liable in any manner for any personal injury or gerty damage or a loss of any kind arising from or connected with this inspection.

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FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307 20 Revision 6 CGE Program # 98-147 WR# 980113020-01 Owner: Commonwealth Edison Date:

12 23-98 P.O. Box 767, Chicago,IL 6%90 Sheet: 1 of 1 Unit:

1

. Plat:

Quad Cities Nuclear Power S:ation Comed 22710 2%th Ave. North, Cordova, IL 61242 R*Pau Organuauon P.O. bo., Job No. etc.

Type Code Symbol Stamp:

N/6-

. Work Performed by-Quad Cities Nuclear Station Authorizaticn No.:

FL/A 22710206th Ave. North,Cordova,IL 61242 Expiration Date:

N/A

. Identification of Systent Main Steam, Class 1

. (a) Apphcable Construction Code: ASME Section III 1965 Edition. S-66 Addenda, N/A CodeCase (b) Applicable Editim of Section XI Utilized for Repairs or Replacements: 1989 Editicn, N/A Addenda, N/A Code Case

. IdentifiWicn of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year Repaired.

ASME Component Mfr.

No.

Bd.

Identificaticn Built Replaced, or Code No.

Replacement Stamped (Yes or No) k Saf ty Valve Consolidated Valve BK6531 N/A 1-0203-4C UNK Replaced Yes Safety Valve Ccmsolidated Valve BK6264 N/A 1-0203-4C UNK Replacement Yes

. Dc:scnption of Work The Safety Valve was replaced as reouired by the WR.

. Tats Conducted: Hydrostatic Pneumatic Nominal Operatmg Pressure Other @

Pressure 1014 psi Test Temp. 2J,2 'F

. Remarks: Performed VT-2 durins the Class 1 Leakare Test.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code.Section XI repar ersepacement ype of Code Symbol Stamp N/A -Comed 10CFR50 Am B. O A Program

'ficste of Authorization No.

N/A Expiraticn Date N/A igned rihl she.

nr ^^* m

• Date Dumus 2A 1976

[

O*ner er Owner s Designec. Tsuc E

f CERTIFICATE OF INSERVICE INSPECTION the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors the State of Illinois and employd by Hartford Steam Boiler Inspection & Insurance Co.

of Hartford CT have inspected the nt. described in this Owner's Report during the period i/-f4P to /-&*ff, and state that to the best of my knowledge and hlief. the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requirenents of the SME Code.Section XI.

y signing this certificate. neither the inspector nor his employer makes any warranty. expressed or implied. concerning the exammations and corrective asures described in this Owner's Report. Purthermxe, neither the Inspector nor his emplopt shall be liable in any manner for any personal injury or perty darrage or a loss of any kind arising from or connected with this inspection.

M f. d e -,

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1999 g

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT j

As Required by ths Provisions of ASME Code Section XI QCAP 0307 20 Revisicn 6 CGE Program # 98148 WR# 980065960-0I

. Owner: Commonwealth Edison Date:

12-11-98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

. Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 Repair Organnauon P.O. No., Job No., etc.

Type Code Symbol Stamp:

N_/,A

. Work Performed by-Quad Cities Nuclear Station Authorization No.:

N/A 22710206th Ave. North, Cordova,IL 61242 Expiration Date:

N!.A

. Identification of System: Main Steam Class 1

- (a) Applicable Cmstruction Code: ASME Section IH 1%8 Edition, W-1968 Addenda, N/&. Code Case (b) Applicable Editim of Section XI Utihzed for Repairs or Replacements' 1989 Edition, N/A,, Addenda, M//L Code Case Identificatim of Compcxients Repaired or Replaced, and Replacement Components:

Name of Name of Mfts. Ser.

Nat'l Other._

Year Repatred.

ASME Component Mfr.

No.

Bd.

Identificaticn Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Reli-f Valve Target Rock 120 N/A 1-0203-3A UNK Replaced Yes Relief Valve Target Rock 171 N/A 10203 3A UNK Replacement Yes Descnption of Work The relief valve was replaced as reouired by the WR.

Tests Cmducted: Hydrostatic Pneumatic Nominal Operating Pressure Other @

Pressure 1014 psi Test Temp.2]7 'F Remarks: Performed VT-2 dunne the Class 1 Leakare Test.

CERTIFICATE OF COMPLIANCE

/c certify that the statements made in & report are correct and this replacement cmforms to the rules of ASME Code.Section XI repair ornpascemenu Ype of Code Symbol Stamp N/A -Comed 10CFR50 Are B. O A Program artificate of Authanzation No.

N/A Expiration Date N/A gned en8H k d e n# t maur / em Date ibJua, arf 19 1949 p 3 owntsorownersuessnee.me CERTIFICATE OF INSERVICE INSPECTION be undersigned, holding a valid commissim issued by the Natimal Board of Boiler and Pressure Vessel Inspectors

'd the State of minn;<. and employed by Hartford Steam Boiler Insnection & Insurance Co.

of Hartford _ CT have inspected the mponents described in 6 Owner's Report during the period Ii/r/ay to //.7 s-/cc, and state that to the best of my knowledge and lief the owner has gifu.d exammations and taken corrective measures described in this Owner's Report in accordance the requiremenu of the BMECode SectionXI.

' signing this certificate. neither the inspector nor his employer trakes any warranty, expressed or implied. concerning the examinations and corrective asures described in this Owner's Report. Purthermore, neither the inspector nor his employer shall be liable in any manner for any personal iqjury or bperty damage or a loss of any kind arising from or connected with this inspecticn.

1' b A/

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FORM N1%2 0WNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-151 WR# 980027857-01

1. Owner:

Comrronwealth Edison Date: 02/05/99 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Statim Comed 22710 206th Ave. North, Cordova. IL 61242 Rel= O's'airanon m Na, Je Na. ac.

Type Code Symbol Stamp:

N/6

3. Work Performed by-Quad Cities Nuclear Station Authorization No.:

E/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

4. Identification of System: Control Rod Drive, Class 1

5. (r) Applicable Construction Code: ASME Section III.1965 Edition, W-65 Addenda, 1361 Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced, and Replacement Compments:

Name of Name of Mfrs. Ser, Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificatim Built Replaced, or Code No.

Replacement Stamped (Yes or No)

CRD GE N/A N/A 1-0300-1827 N/A Replacement Yes

7. Desenption of Work: Replaced bottine associated with CRD 18-27 as reauired by the WR.

Tests Cmducted: Hydrostatic Pneumatic 0 Nominal Operstmg Pressure O Other C Pressure 1014 psi Test Temp.212 "F

?. Remarks: Performed a VT-1 inspection of boltine when disassemNed and a VT-2 inspection durine the Class 1 System Leakare Test.

CERTIFICATE OF COMPLIANCE We cenify that the statements made in this report are correct and this replacement conforms to the ndes of ASME Code.Section XI repast orreplacement Type of Code Symbol Stamp N/A -Comed 10CFR50 Aro B. O A Procram Certificate of Authcrization No.

N/A Expiration Date N/A Signed Md roc,

_nr t.doup r_W Date AmaEvatV 5 1944 y

04ncr ct Owner a Demgnec, Tide CERTIFICATE OF INSERVICE INSPECTION

[. the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Illinois. and employed by Hartford Steam Boiler Insnection & Insurance Co of Hartford. CT have inspected the

/

f i/4 Y to J' hl*f'T

, and state that to the best of my knowledge and omponents described in this Owner's Report during the period

%1ief, the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the GME Code Section XI.

3y signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied concerning the exammations and corrective neasures described in this Owner's Report. Purthermore. neither the Inspector nor his employer shall be liable in any manner for any personal injury or woperty damage or a loss of any kind arising from or connected with this inspection.

i7I Commissions a

3 ate bM~

19 I

FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-154 WR# 980023966-01

1. Owner: Commonwealth Edison Date: 01/26/99 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

. 'lant:

Quad Cities Nuclear Power Statim Comed 22710 206th Ave. North, Cordova, IL 61242 ne=r ursamuuon P.a da. Job ba. cie.

Type Code Symbol Stamp:

N/6

. Work Performed by-Quad Cities Nuclear Station Authorizatim No.:

N//6 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

. Identification of Systerre Rectreulatim. Class !

5. (!) Applicable Construction Code: - ASME Section 1 1%5 Edition, Nme Addenda, N/A Code Case (b) Applicable Editim of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced, and Replacement Compments:

Name of Name of Mfrs. Se.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Mechanical PSA 16917 N/A 1-0201 M45 UNK Replaced' No Snubber Mechanical PSA 13893 N/A 1-0201-M45 UNK Replacement Yes Snubber

. Description of Work: Replaced the mechanical snubber as reoutred by the WR.

. Tests Cmducted: Hydrostatic Pneumatic 0 NominalOperatingPressure O Other Pressure psi Test Temp.

'F

. Remarks: Performed a VT-3 inspection on the replaced snubber.

No pressure testme reouired.

CERTIFICATE OF COMPLIANCE e certify that the statements inade in this report are correct and this replacement conforms to the rules of ASME Code. Sectica XI repast arreplacement Type of Code Symbol Stamp N/A - Comed 10CFR50 Ano B. O A Procram ertificate of Authcrization No.

N/A Expiration Date N/A ligned /Wki..G/f..

dANvACf. fle 167 ti/IAP LEAP Date 1944 g

o.

. o.

m.

I CERTIFICATE OF INSERVICE INSPECTION lthe undersigned. holding a valid commission issued by the National Board of Boiler and Pmssure Vessel Inspectors Ed the State of minnis and employed by Hartford Steam Boiler Insnection & Insurance Co of Hartford. CT have inspected the components described in this Owner's Report during the pedod a/f4f to /-#7'fi

. and state that to the best of my knowledge and lief, the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the ME Code.Section XI.

py signing this cer6ficate. neither the inspector nor his employer makes any warranty, expressed or implied. concerning the exammations and corrective

.asures described in this Owner's Repcrt. Furthermore. neither the inspector nor his employer shall be liable in any manna.r for any personal injury erty damage or a loss of any kind arising from or connected with this inspection.

t_/ / -[

Commissions

1. 3 m

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l FORM NIS 2 OWNERS REPORT GF REPAIR OR REPLACEMENT I

As Required by the Provisions of ASME Code Section XI QCAP 0307 20 Revision 6 CGE ProFram # 98-155 WR# 980116146-02 1 Owner: Commonwealth Edison Date: 01/30/1999 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of I Unit:

1

2. Plant-Quad Cities Nuclear Power Statwn Comed 22710206th Ave. North,Cordova,IL 61242 Repaar Organizauon P.O. Na, Job No., cae.

Type Code Symbol Stamp:

U/6

3. Work Performed by:

Quad Cities Nuclear Station Authorizaum No.:

N/6 22710 206th Ave. Notth, Cordova, IL 61242 Expiradon Date:

N/A

6. Identificaticri of System High Pressure Coolant injection, Class 2

i. (a) Applicable Construction Code: USAS B31.11%7 Editicn, None Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition,.U/A, Addenda, N-416-1 Code Case

i. Identificauon of Components Repaired or Replaced, and Replacement Compments:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificatim Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Stop Check Valve Edwards Valve Inc.

A868YT3 N/A 1 2301-71 N/A Replacement No Pipe Various HT# A41538 N/A l 2301-71 N/A Replacement No

. Desenption of Work: Replace valve and nice as reouired by the WR.

. Tests Cmducted: Hydrostatic Pneumatic NominalOperatingPressure Q Other Pressure 22 psi Test Temp. L@ *F Remarks: Performed VT-2 on replacement parts durine pressure test.

Test conducted by Code Case N-416-1.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code,Section XI repair orreplacement Type of Code Symbol Stamp N/A - Comed 10CFR50 Arv B. O A Procram

'ertificate of Authorization No.

N/A Expiration Date N/A igned ccL M 6,rtNt-MADDate h/'AJAM 19 %

y' Outici or Owndr s Desagnee. Title CERTIFICATE OF INSERVICE INSPECTION the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors d the State of minois and employed by Hartford Steam Bniler insacio- & Insurance Co.

of Hartford. CT have inspected the temponents described in this Owner's Report dunng the period

//49h to 2-3 -M

, and state that to the best of my knowledge and Elief, the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the regturem fME Code.Section XI.

p signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the exammations and corrective reasures described in this Owner's Report. Purthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or operty damage or a loss of any kind arising from or connected with this inspection.

- b od Commissions

[63 ke 4 J,7 m.~ e--

19 19 i

FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Regtred by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98138 WR# 970124981-04 Owner: Commonwealth Edison Date:

12-17-98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Ciues Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 Repau Organuauon P.O..No., Job bo., etc.

Type Code Symbol Starnp:

N1/6

3. Work Performed by-Quad Cities Nuclear Station Authorization No.:

Ji/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

1. 14 L. Identification of System Reactor Head Vent, Class 1

i. (a) Applicable Construction Code: USAS B31.1 1%7 Edition, None Adderida, ji/6 Code Case (b) Applicable Editical of Section XI Utilized for Repairs or Replacements: 1989.,Edtticut, NL4. Addenda, and N/A. Code Case

i. Identification of Components Repatred or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME

+

Component Mfr.

No.

Bd.

Identificaticn Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Boltmg N/A Vanous N/A 1-0201-1 N/A Replacement No

' Desenpuan of Work: Replaced the flange bolting as reouired by the WR.

. Tests Ccnducted: Hydrostatic Pneumatic Nominal Operatmg Pressure Other Pressure ps:

Test Temp.

'F

. Remarks: VT-1 was performed on all renlacements.

- No pressure testing reouired.

CERTIFICATE OF COMPLIANCE W2 certify that the statements made in this report are correct and this rerilacement conforms to the rules of ASME Code.Section XI repaar orreplacernra Type of Code Symbol Stamp N/A - Comed 10CFR50 Ato B. O A Program

eruficate of Authcrtzation No.

N/A Expiration Date N/A

,igned re8M mat fer geop i ns Date

_h - - "

28 19 fg Gf Lkner or Owner's Designee, Tide

. CERTIFICATE OF INSERVICE INSPECTION the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors md the State of minnis. and employed by Hartford Steam Boiler indou & Insurance Co.

of Hartford. CT have inspected the xnpanents described in this Owner's Report during the period if /s1/GC to / - 2 h ff, and state that to the best of my knowledge and clief, the owner has performed exammations and taken corrective rneusures described in this Owner's Report in accordance the requircrrents of the SME Code.Section XI.

y signing this certificate. neither the inspector nor his employer makes ar v wa:Tanty, expressed or implied, conceming the exarranations and orrective asures described in this Owner's Report. Purthermore. neither the Inspe.

7.. Y his employer shall be liable in any manner for any personal injury or

,operty damage or a loss of any kind arising from or connected with this inspection.

I Commissions fe 3

__a rate

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19 EI

/

FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI

~

QCAP 0307 20 Revision 6 CGE Prograrn # 98-160 WR# 960033587-02

1. Owner: Cornmanwealth Edison Date:

12/07//98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Corned 22710 206th Ave. North, Cordova, IL 61242 Man orsammuo= I".o. No.. Job No..==.

Type Code Symbol Stamp:

E

3. Work Performed by:

Quad Cities Nuclear Station Authorization No.:

E 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

FyA

4. Identification of System Reactor Recirculatsoin System, Class 1

5. (a) Applicable Construction Code:,6FME Section I IM5. USAS B31 1 1%7 Editica Egile_, Addenda, E/6 Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N-504 Code Case

6. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year Repaired.

ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacerrent Stamped (Yes or No)

Pipe Weld GE N/A N/A 1-0202B-28"-A N/A Repaired No 02BS-F14 7, Desenption of Wcrk: Renaired nine weld 02BS-F14 on line 1-0202B-28" by performine weld overlay as recuired by the WR. Repair tformed in accordance with Code Case N-504.

B. Tests Conducted: Hydrostatic Pneumatic 0 Nominal Operating Pressure Other D Pressure 1Q14 psi Test Temp. 217 *F

9. Remarks: Performed FT. UT and VT-2 inspections on the weld overlav as recuired by the WR.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair conforms to the rides of ASME Code,Section XI

,, g Type of Code Symbol Stamp N/A - Comed 10CFR50 Aon B. O A Program hificate of Authorization No.

N/A Expiraticri Date N/A signed r%In M.

fE dAuP LAAh Date De aWf 1.8 1948

{ ovan or owns sI% Tioe CERTIFICATE OF INSERVICE INSPECTION

. the undersigned. holding e valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors

'md the State of tms.. and ca.iployed by Hanford Steam Boiler Insmetion & Insurance Co of Hartford CT have inspected the ornpanents described in this Owner's Report during the period

////_r /ff to d//89, and state that to the best of my knowledge and clief, the owner has performed exammations and taken corrective measures described in this Owner's Report in accordance the requirements of the GME Code,Section XI.

4y signing this certificate. raither the inspector nor his employer'makes any warranty, expressed or implied concerning the exammations and rective measures described in this Owner's Report. Funbermore. neither the inspector nor his employer shall be liable in any manner for any ersonal irsury cr propeny damage or a loss of any kinh arhing from or connected with this inspection.

M I-d Commissions M

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19 #

FORM NIS 2 OWNERS REPORT OF REPAIR OR REP!ACEMENT As Required by the Provisions of ASME Code Section XI

~

QCAP 0307-20 Revision 6 CGE Program # 98-162 WR# 980120826-02 L Owner: cnmrmnwealth Edison Date:

12/08//98 P.O. Box 767, Chicago, IL 60690 Sheet: I of 1 Unit-1 LPlant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova,IL 61242 hepar Orgammuon P.O. Na, M Na, etc.

Type Code Symbol Stamp:

N/6

i. Work Performed by:

Quad Cities Nuclear Station Authorization No.:

N/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A L. Identification of System Reactor Recirculatioin Syst:m, Class 1

5. (:) Applicable Construction Code: ASME Section i 1965. USAS B31.1 1%7 Edition, None Addenda, N/A Ccr'e Case (b) Applicable Edition of Section XI Utilized fcr Repairs or Replacements: 1989 Edition, N/A Addenda, N-504 Code Case

5. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Pipe Weld GE N/A N/A 1-02028-28*-A N/A Repaired No 02BS-F7

. Description of Work: Repaired nine weld 02BS-F7 on line 10202B-28"-A bv performine weld overlay as reouired by the WR. Repair nfamed in accordance with Code Case N-504.

. Tests Conducted: Hydrostatic Pneumatic Nominal Operatmg Pressure Other G Pressure 1014 psi Test Temp. 2Jll *F

' Remarks: Performed IT. UT and VT-2 inspections on the weld overlay as reouired by the WR.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this. repair conforms to the rules of ASME Code Section XI repar errepiscement Type of Code Symbol Stamp N/A - Comed 10CFR50 App B. O A Procram Tertificate of Authorization No.

N/A Expiration Date N/A

igned M b (er

.fts deus e Date D m m.a. 16 1946 y

O&ner or Owner a Demgnee, htle r

CERTIFICATE OF INSERVICE INSPECTION the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors ed the State of minois. and employed by Hartford Steam Boiler Insnection & Insurance Co of Hartford. CT have inspected the xnponents described in this Owner's Report during the period

//' / 7 - f F to J-M-f 7, and state that to the best of my knowledge and clief, the owner has performed examinations and taken corrective measures described in this Owner's Repcrt in accordance the requirements of the

,SME Code.Section XI.

ly signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and erective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any ersonalinjury or property dama or a loss of any kin 21 arising from or connected with this inspection.

M_

Commissions A'I47 I t p.== me==.

V./

woonamoma erm, no sa.

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l FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-163 WR# 980120638-02

1. Owner: Cornmonwealth Edison Date:

12/07//98 P.O. Box 767. Chicago, IL 60690 Sheet: I of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Corned 22710 206th Ave. North, Cordova,IL 61242 ker== ors==zauan to. Na. a tm. ac.

Type Code Symbol Stamp:

N/6.

3. Work Performed by-Quad Cities Nuclear Station Authertzation No.:

N!%

22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

US

4. Identification of System Reactor Recirculation System, Class 1

5. (a) Applicable Construction Code: ASME Section I 1%5. USAS B31.1 1%7 Edition, _Ngge. Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repatrs or Replacements: 1989 Edition, N/A Addenda, N-504 Code Case

6. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year Repatred.

ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes cr No)

Pipe Weld GE N/A N/A 1-0202A-28"-A N/A Repatred No 02AS F9

'. Description of Work: Repaired eine weld 02AS-F9 on line 1-0202A 28"-A by nerformine weld overlav in accordance with the WR.

Veld overlsv repair iw% med in accordance wtth Code Case N-504.

. Tests Conducted: Hydrostatic O Pneumatic O Nominal Operatmg Pressure Other D Pressure 1014 psi Test Temp. 2R 'F

i. Remarks: fgformed P'r. UT and VT-2 inspections as reouired by the WR.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this repair conforms to the rules of ASME Code.Section XI repar erreplacemens Type of Code Symbol Stamp N/A -Comed 10CFR50 App B. O A Procram

ertificate of Authorization No.

N/A Expiration Date N/A

.igned Midd roO fGf d e vr-m a Date CEt4arnM /C 1945

{ owner or owner a peasnes. Inle CERTIFICATE OF INSERVICE INSPECTION the unde'rsigned, holding a valid commission issued by the Naticmal Bmrd of Boiler and Pressure Vessel Inspectors xi the State of Illinois and employed by Hartford Steam Boiler Insnection & Insurance Co.

of Hartford CT have inspected the niponents desenbed in this Owner's Report during the period ti-lO 9 F to 2 * /f, '99

. and state that to the best of my knowledge and 51ief, the owner has performed examinations and taken corrective rneasures described in this Owner's Report in accordance SME Code.Section XI.

y signing this certificate. neither the inspector nor his employer makes any warranty, expressed or implied. conceming the examinations and nrrective measuns described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any trsonalinjury or property or a lost of any kind arising from or connected with this inspection.

D _97/

Commissions v

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19 N nte

FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by th? Provisions of ASME Code Section XI

~'

QCAP 0307-20 Revision 6 CGE Program # 98-164 WR# 980120637-02 i Owner: Commonwealth Edison Date:

12/09//98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1 J. Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 Karar orsa==uanl'.o.E. Job tm. eu:.

Type Code Symbol Stamp:

L4/6

. Work Performed by-Quad Cities Nuclear Station Authorization No.:

I!M 22710 206th Ave. North, Ccrdova, IL 61242 Expiration Date:

14/A

. Identification of System Reactor Recirculation System Class 1

. (a) Applicabe Construction Code: ASME Section I 1%5. USAS B31.1 1%7 Edition, None Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N-504 Code Case

. Identification of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacemen:

Stamped (Yes or No)

Pipe Weld GE N/A N/A 1-0201A 28" A N/A Repaired No 02AD-F8

. Descripticx1 of Work: Repaired nine weld 02AD-F8 on line 1-0201 A-28"-A by performine weld overlav in accordance with the WR.

pair performed in accordance with Code Case N-504.

Tests conducted: Hydrostatic Pneumatic Nominal Operating Pressure O Other D Pressure 1014 psi Test Temp. 212 *F Remarks: Performed IT. UT and VT-2 inspecticris as reouired by the WR.

CERTIFICATE GF COMPLIANCE Ve certify that the statements rnade in this report are correct and this. repair. conforms to the rules of ASME Code,Section XI arar erapa.ames rype of Code Symbol Stamp N/A - Comed 10CFR50 App B. O A Procram ertificate of Authartr.ation No.

N/A Expiration Date N/A igned (9 sa' L

1. 1C h8=n Date rwms SA 19 eA

/

ok er owner s Densmic. Tads t

l CERTIFICATE OF INSERVICE INSPECTION the undertigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors d the State of Imnnk. and er@loyed by Hartford Steam Boiler Insnection & Inmrance Cc nf Hartford CT have inspected the anponents described in this Owner's Report during the period n /n-/4 c to.N &

• M, and state that to the best of my knowledge and lief, the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the sME Code.Section XI.

y signing this certificate. neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and rrective measures described in this Owner's Report. Furthermde, neither the Inspector nor tis employer shall be liable in any manner for any rsonal iqjury or property damage or a loss of any kindsarising from or connected with this inspection.

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FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT i

As Required by the Provisions of ASME Code Section XI l

QCAP 0307-20 Revision 6 CGE Program # 98-165 WR# 980113022-01 Owner: Commonwealth Edison Date:

12 23-98 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant-Quad Cities Nuclear Power Statim Comed 22710 206th Ave. North, Cordova, IL 61242 Repar Organnauon P.O. No., Job No., etc.

Type Code Symbol Stamp:

F_/6

3. Work Performed by:

Quad Cities Nuclear Station Authorization No.:

F_/&

22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

4. Identification of System Main Steam, Class 1

5. (:) Applicable Construction Code: ASME Section !!! 1%5 Edition, S-66 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replamments: 1989 Editimt. N/A Addenda, y/,,6, Code Case S. Identification of Components Repaired or Replaced, and Replacement Ccmpcsients:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificaticri Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Saf Oy Valve Consolidated Valve BK6529 N/A 1-0203-4G UNK Replaced Yes Safety Valve Consolidated Valve BK7165 N/A 1-0203-4G UNK Replacement Yes P. Desenption of Wak: The Safety Valve was reclamd as recuired by the WR.

.~ests Carducted: Hydrostatic Pneumatic Nominal Operatmg Pressure Other @

Prentre 1014 psi Test Temp. 212 'F

' Remarks: Performed VT-2 dunne the Class 11 akare Test.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code,Section XI spar orreplacenem Type of Code Symbol Stamp N/A - Comed 10CFR50 Ario B. O A Procram Mficate of Authcrization No.

N/A Erpiration Date N/A

igned f dM saa -

nr h>#'=*

Date

_ h_

2B 19 46

/

I vwner or owna s Deasnee, Due CERTIFICATE OF INSERVICE INSPECTION

, the undersigned, holding a valid cornmission issued by the Natimal Board of Boiler and Pressun: Vesselinspectors ad the State of minnie. and employed by Hanford Ste.am Boiler Insnection & Insurance Co.

of Hartford CT have inspected the amponents described in this Owner's Report during the period v-1 1 - 9P to / - Jr-9 4, and state that to the best of my knowledge and clief. the owner has performed examinations and taken conective measures described in this Owner's Report in accordance the requirements of the SME Code,Section XI.

y signing this certificate, neither the inspector nor his employer makes any warranty, expressed cr implied. concerning the examinations and corrective

• atures descibed in this Owner's Report. Furthermare. neither the Inspector nor his employer shall be liable in any manner for any personal irdury or petty damage or a loss of any kind arising from or connected with this inspection.

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-166 WR# 980113023 01 Owtier:

Commonwealth Edison Date:

12-23 98 P.O. Box 767, Chicago. IL 60690 Sheet: I of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Station Comed 22710206th Ave. North, Cordova, IL 61242 Repau Orsaniunon P.O. No.. Job No.. ac.

Type Code Symbol Stamp:

N/A

3. Work Performed by' Quad Cities Nuclear Station Authanzaticri No.:

E!A 22710206th Ave. North, Cordova, IL 61242 Expiration Date:

E/A

4. Identification of System Mam Steam. Class 1

5. (I) Applicable Constniction Code: ASME Section III 1965 Edition,.}.-Q6. Addalda, N/A Code Case (b) Applicable Editicx of Section XI Utihzed for Repairs or Replacements: 1989 Edition, & Addenda, N/A CodeCase

6. Identificauen of Components Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificaticn Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Saf2y Valve Consolidated Valve

'BK6251 N/A 1-0203-4H UNK Replaced Yes Saf:y Valve Consolidated Valve BK6278 N/A 1-0203-4H UNK Replacement Yes

7. Desenption of Work: The Safety Valve was replaced as reauired by the WR.

Tests Conducted: Hydrostatic Pneumatic Nominal Operatmg Pressure Other D Pressure 1014 psi TestTemp.212 'F

i. Remarks: Performed VT-2 dunne the Class 1 trakare Test.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacerrent conforms to the rules of ASME Code.Section XI repau wrepsacemear Type of Code Symbol Stamp N/A - Comed 10CFR50 Ano B. O.A Procram htificate of Authanzation No.

N/A Expiraticri Date N/A

igned Amt.

far ' - e e Date A-"

lb 1948 y

Odher w Owner s Demgnee. Tale CERTIFICATE OF INSERVICE INSPECTION

, the undersigned, holding a valid conunission issued by the National Board of Boiler and Pressure VesselInspectors ud the State of minnis. and enployed by Hartford Steam Boiler Insnection & Insurance Co.

of Hartfoni CT have inspected the anyonents described in this Owner's Report during the period

//- /7-/f to /- F'99, and state that to the best of my knowledge and

, lief, the owner has performed exammations and taken corrective rneasures described in this Owner's Report in accordance the requirements of the SME Code,Section XI.

y signing this certificate, neither the inspector nor his enployer rnakes any wammty expressed or implied. concerning the exammations and corrective easures described in this Owner's Report. Purthermare. neither the Inspector nor his employer shall be liable in any manner for any personal iqjury or

.perty damage or a loss of any kirx' arising from or connected with this inspection.

/'

Commissions M84I b

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FORM N:S-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provtsics of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-167 WR# 98002451641 Owner:

Commonwealth Edison Date: 01/26/1999 P.O. Box 767 Chicago,IL 60690 Sheet: I of I Unit:

1

. Plant:

Quad Cities Nuclear Power Statico Comed 22710 206th Ave. North. Cordova, IL 61242 RePatt Organazauon P.O. No., Job ho.. etc Type Code Symbol Stamp:

F{/A Work Performed by-Quad Cities Nuclear Station Authonzation No.:

Ff_A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

. Identification of System High Perssure Coolant injection, Classi (a) Apphcable Construction Code: USAS B31.1 1967 Editim, None Addenda, N/A Code Case (b) Applic:ble Editicn of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A Code Case Identification of Components Repaired or Replaced, and Replacement Compcnents:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificatico Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Mecharsical PSA 16919 N/A 1-2305-67 UNK Replaced No Snubber Mechanical PSA 4793 N/A 1-2305-67 UNK Replacement Yes Snubber Desenption of Work: Replaced the mechanical snubber as reouired by the WR.

Tests Ccmducted: Hydrostatic Pneumatic Nonunal Operating Pressure Other Pressure psi Test Temp.

'F Remarks: Performed a VT-3 on the replaced snubber.

No pressure testme reautred.

CERTIFICATE OF COMPLIANCE Te certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code,Section XI repair or replacement ype of Code Symbol Starnp N/A - Comed 10CFR50 Ann B. O A Procram

rttficate of Authcnzauan No.

N/A Expiration Date N/A gned r dI.Ct (td.

T*d" MwP (Mr> Date

. Lv ArzV U 19 49 7

q.ncr or o.w. Dessnee, noe jg CERTIFICATE OF INSERVICE INSPECTION Lbe undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors d the State of IHinois. and employed by Hartford Steam Boiler inmeetion & Insumnce Co.

of Hartford CT have inspected the mponents described in this Owner's Report during the period

<> / n /ry to M//H

, and state that to the best of my knowledge and lief, the owner has performed examinations and taken corrective measures described in this Owner's Report in accordance the requircrrents of the

ME Code,Section XI.

4igning this certificate. neither the inspector nor his employer makes any warranty, expressed or implied. concerning the examinations and corrective insures described in this Owner's Report. Furthermarq. neither the Inspector nor his employer shall be liable in any manner for any personal injury or prty damage or a loss of any kind arising from or connected with this inspection.

Commissions b

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19 'I'T ite

I FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307 20 Revision 6 CGE ProFrara # 98-168 WR# 980120950-05

1. Owner: Commonwealth Edison Date: 02/01/1999 P.O. Box 767, Chicago, IL 60690 Sheet: I of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Statim Comed 22710 206th Ave. North, Cordova, IL 61242 kepen Orgamzauon EU. No.. Job No.. ca.

Type Code Symbol Stamp:

N/A,,

3. Work Performed by Quad Ciues Nuclear Station Authorization No.:

N//A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

4. Identificauan of System Rwitculation, Class 1

5. (a) Apphcable Construction Code: USAS B31.1 1%7 Edition, None Addenda, N/A Code Case (b) Apphcable Editicri of Section XI Utilized for Repairs or Replacements: 1989 Edition N/A Addenda, N/A Code Case

6. Identification of Components Repaired or Replar:ed, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd Identificaticn Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Pipmg Vanous N/A N/A 1-02106A-1/2" unknown Replacement No

7. Descnption of Work: Replaced 1/2" pipine with 3/4" eining by welding to ungrade numn seal as reoutred by the WR.

Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp.

'F

). Remarks: No pressure testine reouired.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this nport are correct and this replacement conforms to the rules of ASME Code.Section XI sepan weeplacement Type of Code Symbol Stamp N/A - Comed 10CFR50 App B O A Program htificate of Authcrization No.

N/A Expiration Date N/A Bigned.$ALb fat fst 6tw t.asb Date fica n AA W

/

1944 y

Owner or Owner's Demgnee, Tade

/

( /

CERTIFICATE OF INSERVICE INSPECTION

. the undersigned, holding a va:id commission issued by the National Board of Boiler and Pressure Vessel Inspectors ad the State of minois. and employed by Hartford Steam Boiler Insocction & Insurance Co.

of Hartfoni CT have inspected the omponents described in this Owner's Report during the period n/sq/W to Al*Jl0 d

, and state that to the best of my knowledge and Clief, the owner has performed exammations and taken corrective measures described in this Owne(s Repon in accordana: the reqdrements of the LSME Code.Section XI.

ly signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied. concerning the exammations and corrective re.asures described in this Owner's Report. Purthermore, neither the Inspector nor his employer shall be liable in any rmaner for any personal injury or repeny damage or a loss of any kind arising frtrn or connected with this inspection.

[-

Commissions 86

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1

FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI OCAP 0307-20 Revisica 6 CGE Program # 98-169 W'R# 980010827-01

1. Owner:

Commmwealth Edison Date: 02/12/1999 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant.

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 Repur orsammuon P.O. No.. Job ho. ac.

Type Code Symbol Stamp:

E/A

3. Work Performed by:

Quad Cities Nuclent Station Authorizatim No.:

F_/6 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N_la

t. Identification of System High Pressure injection Coolant, Class 2.

5. (a) Applicable Construction Code: USAS B311 1%7 Edition, None Addenda, N/A Code Case (b) Applicable Edition of Sectim XI Utilized for Repairs or Replacements: _]989 Edition, N/A Addenda N/A CodeCasc

6. Identification of Components Repaired or Replaced, and Replacement Compments:

Name of Name of Mfrs. Ser Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identificatim Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Reli:f Valve Dresser TC 46115 N/A 1-2301-53 unknown Replaced Yes Consolidated Relitf Valve Dresser 2799501-N/A 1-2301 53 1997 Replacement Yes Cmsolidated FP

' Desenption of Waric Replaced relief valve and associated botting as reauired by the WR.

. Tests Cmducted: Hydrostatic Pneumatic NomtnalOperatingPressure O Other @

Pressure.46 psi Test Temp. 2_8 'F P. Remarks: Performed a VT-2 on the replaced relief valve.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement confonns to the rules of ASME Code,Section XI sepair orseplacement Type of Code Symbol Stamp N/A - Comed 10CFR50 Arv B. O A Program irtificate of Authanzation No.

N/A Expiration Date N/A

'igned (~'98 mac.

fat derA F t m p Date I'wutf /6 19 99 y Olwner or Uwaar's Deangnee Inle

//

CERTIFICATE OF INSERVICE INSPECTION the undersigned, ho'. ling a valid commission issued by the National Board of Boiler and Piessure VesselInspectors xi the State of,,,,jhang_,,, and employed by Hartford Steam Boiler Imnection & Insumnce Co.

of Hartford CT have inspected the ornponents described in this Owner's Report during the period

//-J V-FP to h/3-ff, and state that to the best of my knowledge and

lief, the owner has puforrned exammations and taken corrective tru.asures described in this Owner's Report in accordance the requirements of the SMECode SectionXI.

ly si ping this certificate, neither the inspector'nor his employer <nakes any warranty, expressed or implied. concerning the exammations and corrective E

iswes described in this Owner's Report. Fuchm, neither the Inspector nor his employer shall be liable in any manner for any personal izqury or

.perty damage or a loss of any kind arising from or connected'uith this inspection.

Carunissims

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE l

Program # 98-170 WR# 960091915-01

1. Owner:

Commonweahh Edison Date: 02/08/99 P.O. Box 767, Chicago,IL 60690 Sheet: I of 1 Unit:

1

2. Plant:

Quad Cities Nuclear Power Statim Comed 22710 206th Ave. North, Cordova,IL 61242 Repaa orsuuzauon P.o. No, Job No., ac.

Type Code Symbol Stamp:

N/A

3. Work Performed by Quad Cides Nuclear Station Authorizatim No.:

N/A 22710206th Ave. North, Cordova, IL 61242 Expiration Date:

N/6

4. Identification of System Recirculatim, Class 1

5. (:) Applicable Constmetion Code: ASME Section I 1%8 / USAS B31.1 1965 Edition, Nme Addenda N/A CodeCase (b) Applicable Edition of Section XI Utihzed for Repairs or Replacements: 1989 Editim, E!6. Addenda, N-416-1 Code Case

6. Identification of Components Repaired or Replaced, and Replacement Compments:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repatred, ASME Component Mfr.

No.

Bd.

Identificatim Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Pipmg GE N/A N/A 1-0204B-2" Unknown Replacement No

7. Description of Work Temnorarily remove and reinstall drain linelo surmort adiacent weld overlav as reouired by WR.

' Tests Conducted-Hydrostatic Pneumatic NominalOperatmgPressure @

Other O Pressure.[0.14 psi Test Temp.117 'F

). Remarks: Performed VT-2 exanunation durine Class 1 System Leakare Test.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code,Section XI repaa orreplacemem Type of Code Symbol Stamp N/A - Comed 10CFR50 Are B. O A Proeram

'ertificate of Authcrtzation No.

N/A Expiration Date N/A I

signed M.

sec 4 0 W t. n o Date h ur4%cY S

19 i 1 J OwterorOwner'sDeegmee,Tiue CERTIFICATE OF INSERVICE INSPECTION p the undersigned, holding a valid commission issued by the Natimal Board of Doller and Pn:ssure Vessel Inspectors ad the State of 11Hndt and employed by Hartford Steam Boiler itswdoi, & Insurance Co.

of Hartford CT have inspected the xnponents desaibed in this Owner's Report during the period

///2 dff' to 1/4 /M

, and state that to the best of my knowledge and elief, the owner has performed exarranations and taken corrective measures described in this Owner's Report in accordance the requirements of the LSME Code,Section XI.

y signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the exammations and correctiv e.asures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal inj roperty damage or a loss of any kind arising from or connected with this inspection.

I d

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Prograrn # 98171 WR# 980120951-05 I

1. Owner: Commonwealth Edison Date: 02/01/1999 I

P.O. Box 767, Chicago, IL 60690 Sheet: I of 1 i

Unit:

1

2. Plant:

Quad Cities Nuclear Power Staticxi Comed 22710206th Ave. Nonh,Cordova,IL 61242 Kes=r orsanuauon P.o..w. Job tu, etc.

Type Code Symbol Stamp:

N/A

3. Work Performed by Quad Cities Nuclear Station Authonzauan No.:

NL6 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A

4. IdV'1 cation of System Recirculation, Class 1

5. (a) Apphcable Construction Code: USAS B31.1 1%7 Edition, h Addenda, N/A Code Case (b) Apphcable Editicn of Section XI Utilized for Repairs or Replacements: 1989 Edition. N/A Addenda N/A Code Case

6. Identification of Compc.ients Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year Repaired.

ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Piping Vanous N/A N/A 102106B-1/2" unknown Replacement No

7. Desenpuan of Work: Replaced 1/2" pining with 3/4" ninme by weldine to upgrade pumo seal as recuired by the WR.

Tests Ccnducted-11ydrostatic Pneumauc 0 Nominal Operaung Pressure Other Pressure psi Test Temp.

'F

). Remarks: No pressure testine reautred.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code Section XI repair orseplacement Type of Code Symbol Stamp N/A -Comed 10CIG50 Ann B O A Program Certificati of Authorization No.

N/A' Expiration Date N/A signed M 1 (d,

J'kT 6.&ve tab Date Iss'voe V /

19 44 7 ' qwner or owner s acusnee. nue is CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the Naticnal Board of soiler sad Pressure Vessel Inspectors ad the State of mimir and employed by Hartford Steam Boiler inmeetion & Insurance Co.

of Hartford CT have inspected the omponents described in this Owner's Report during the period II.14/. @ to,3f,$/fL, and state that to the best of my knowledge and belief. the owner has performed exammations and taken corrective measures described in this Ovier's Report in accordance the requirements of the LSME Code.Section XI.

ly signing this certificate, neither the inspector nor his employer trates any warranty, expressed or Nnplied. concerning the examinations and corrective ricasures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any perscnal injury or Leoperty damage or a loss of any kind arising from or connected with this inspection.

[

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FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI l

QCAP 0307-20 Revision 6 CGE I

Program # 98172 WR# 970054567-01

1. Owns:

Commonwealth Edison Date: 01/30/1999 P.O. Box 767, Chicago, IL 60690 Sheet: 1 of 1 Unit:

1

2. Plant:

Quad Ciues Nuclear Power Statim Comed 22710 206th Ave. North, Cordova, IL 61242 kepur vrranamuon P.O. No.. Job No.. cac.

Type Code Symbol Stamp:

N_%

3. Work Performed by-Quad Cities Nuclear Station Authonzatim No.:

Uf%

22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

U!%

4. Identificadon of System. High Pressure Coolant Injection. Class 2

5. (a) Applicable Cmstruction Code: USAS B31.11%7 Editim, None Addenda, N/A CodeCase (b) Applicable Editim of Section XI Utilized for Repairs or Replacements: 1989 Edition, N/A Addenda, N/A CodeCase

6. Identification of Components Repaired or Replaced, and Replacement Compments:

Name of Name of Mfts. Ser.

Nat'l Other Year

Repaired, ASME Component Mfr.

No.

Bd.

Identification Built Replaced, or Code No.

Replacement Stamped (Yes or No)

Bollmg Vanous ifT. Code N/A 1-2310 N/A Replacement No JNC/LFN

f. Desenption of Work: Replaced boltine at heat exchancer/pirnne flance as reoutred by the WR.

B. Tests Cmducted: Hydrostatic 0 Pneumatic NommalOperstmg Pressure Other Pressure psi Test Temp.

'F J. Remarks: No pressure testme reautred.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code. Sectim XI mpir ornplacement Type of Code Symbol Stamp N/A - Comed 10CFR50 Ann B. O A Program Tertificate of Authcrization No.

N/A Expiration Date N/A signed /

m#.

M dho 6m Date hoevAer

/

1941

/

Dwner or Owner sDemgaes, lade CERTIFICATE OF INSERVICE INSPECTION the undersigned. holding a valid commission issued by the National Bcard of Boiler and Pressure Vessel lospectors xithe State of minnis. and ernployed by Hartford Steam Boiler Insocction & Insurance Co.

of Hartford. Er have inspected the xnponents descnbed in this Owner's Report during the period

/>3*ff to 7-3-99

. and state that to the best of my knowleage and miief, the owner hu performed examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the ME Code,Section XI.

signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the exammations and corrective Mures desenbed in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for an y damage ce a loss of any kind arising from or connected with this inspection.

M- [ N C

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FORM NIS 2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI QCAP 0307-20 Revision 6 CGE Program # 98-173 WR# 980126319-01 Owner:

Conunonwealth Edison Date:

12 15-98 P.O. Box 767, Oricago,IL 60690 Sheet: 1 of 1 Unit:

1 LPlant:

Quad Cities Nuclear Power Station Comed 22710206th Ave. North, Cordova, IL 61242 Res=r orsaan.uon e.o. Na, Job No.c.

Type Code Symbol Stamp:

N/A

l. Work Performed by:. Quad Cities Nuclew itation Authonzatim No.:

N/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

E!6

6. Identification of System: Reactor Vessel Water Level Instrument Piping, Class 1

i. (A) Applicable Constructim Code' USAS B31. I 1967 Edition, Hoge_ Addenda, E/A Code Case (b) Applicable Editim of Section XI Utilized for Repairs or Replacements: 1989_Editicn, N/A_Addeda, and N/A. Code Case

i. Identification of Cornpanents Repaired or Replaced, and Replacement Components:

Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME l

Component Mfr.

No.

Bd.

Identificatim Built Replaced, or Code No.

Replacement Stamped (Yes or No)

' Excess Flow Check Jobet Valves Inc.

50FM-N/A 1-0263-2-42B N/A Replacement No Valve 920704 Desenption of Wcrk: Check Valve was replaced in accordance with the WR.

L Tests Cmducted: Hydrostatic O Pneumatic Nominal Operating Pressure i

Other Pressure psi Test Temp.

• F

, Remarks: Exempt from pressure testine (ie 1" diameter)in accordance with IWA-7400.

CERTIFICATE OF COMPLIANCE e cenify that the statements made in this report are correct and this replacement conforms to the rules of ASME Code.Section XI repair or replacemem of Code Symbol Stamp N/A -Comed 10CFR50 Are B. O A Program

ertificate of Authanzation No.

N/A Expiration Date N/A Jgned M d rar, 18 r 6dw /E&b Date DEcenips>L /(p 1948 a

y OWer or Owner s Demgnee.Taue I

CERTIFICATE OF INSERVICE INSPECTION the undenigned. holding a valid conunission issued by the National Board of Boiler and Pressure Vessel inspectors ad the State of mimit and errployed by Hartford Steam Boiler inmeetion & Insurance Co.

of Hartford CT have inspected the xnpanents described in this Owner's Report during the period /3 -A.- GI to /- //- 9 T

, and state that to the best of my knowledge and

licf. the owner has performed examinations and taken corrective measures described in this Owner's Report in acconiance the requirenunts of the SME Code. Sution XI.

~ signing this certificate, neither the inspectctner his employer rmkes any warranty expressed or implied, cmcerning the examinations and corrective sures described in this Owner's Repon. Punbermare. neither the inspector ncr his errployer shall be liable in any manner for any personal injury or operty damage or a loss of any kind arising from or cormecteq with this inspection.

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W Commissions Ift'3

/

-- r - n ate dA 19 ff I

FORM NIS-2 OWNERS REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Secuan XI QCAP 0307 20 Revision 6 CGE Program # 98-174 WR# 980126593-01 Owner:

Commonwealth Edison Date:

12-10-98 P.O. Box 767, Chicago. IL 60690 Sheet: I of 1 Unit:

1 Plant:

Quad Cities Nuclear Power Station Comed 22710 206th Ave. North, Cordova, IL 61242 kep=>r orsaruauon P.O. No, Job No.. etc.

Type Code Symbol Stamp:

N/A Work Performed by-Quad Cities Nuclear Station Authorization No.:

N/A 22710 206th Ave. North, Cordova, IL 61242 Expiration Date:

N/A identification of System Control Rod Drive, Class 1 C) Apphcable Construction Code: USAS B31.1 1967 Edition, None Addenda, N/A Code Case (b) Applicable Edittai of Section XI Utihzed for Repairs or Replacements: 1989 Editicut, N/.A. Addenda, and N/A_ Code Case A

l

, Identification of Components Repaired or Replaced, and Replacement Compcnents-l Name of Name of Mfrs. Ser.

Nat'l Other Year

Repaired, ASME j

Component Mfr.

No.

Bd.

Identification Built Replaced, or Code i

No.

Replacement Stamped (Yes or 1

No) 3CU 18-47 Piping GE N/A N/A 1-0338B-1-A N/A Repaired No l

I Desenption of Work Pine socket weld was repaired in accordance with the WR.

.:sts Ccaducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp.

'F Remarks: Exempt from pressure testine de 1" diameter) m accordance with IWA-4700 (b) (5).

CERTIFICATE OF COMPLIANCE e certify that the statements made in this report are cortect and this remr conforms to the rules of ASME Code.Section XI repair or tepiaceman pe of Code Symbol Stamp N/A -Comed 10CFR50 Are B. O A Procram dificate of Authcrization No.

N/A Expiration Date N/A sted samL nf ^w im n Date her -acs f6 1948

/

IOwner or Ow act's Deaagnee. Tide'

~~

E CERTIFICATE OF INSERVICE INSPECTION se undenigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel laspectors the State of Illinois. and employed by Hartford Steam Boiler Inspection & Insumnce Co.

of Hartford CT have inspected the 1ponents desenbed in this Owner's Report during the penod

/2 *3 *iE to /J 'M-Y, and state that to the best of my knowledge and ef, the owner has perfcrmed examinations and taken corrective measures described in this Owner's Report in accordance the requirements of the 4E Code.Section XI.

signing this certificate, neither the inspector not his employer makes any warranty, expressed or implied, concerning the exarrunaticus and corrective tsures described in this Owner's Report. Furtlarmore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or rty dama or a loss of any kind arising frtan or connected with this inspection.

Comdiissions NN u

/A 2 P 19 N e

l IVI Evaluations

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l IVI Evaluations

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Calculation Title Pcgo CALCULATION TITLE PAGE Calculation No: ODC-0200-M-0768 DESCRIPTION CODE: M07

[

DISCIPLINE CODE:

M i

SYSTEM CODE:

0200 RX).1400 (CS)

TITLE:

Ouad Cities Unit 1 Core Soray Flaw Evalnation XX Safety Related Augmented Quality Non-Safety Related REFERENCE NUMBERS Type Number Type Number Socc 21A3319 Rot TR-106740 Soce AS 3-16 Rot NP-2347 Rot NP-4690-SR

[

COMPONENT EPN:

DOCUMENT NUMBERS:

EPN Compt Type Doc Type / Subtype Document Number 1-D200 V35 DWGV E861. Sheet 1

[

DWGV E861. Sheet 2 DWGV 161F312

[

CALC /ENG OC-NPD-0038 i

CALC /ENG ODC-0200-M-0769 CORR /NDIT SO40-OH-0572 REMARKS:

(

REV.

REVISING APPROVED DATE ORGANIZATION PRINT /SIG,)j f i

O Em.%

dwkW /ddff' n/ao/98 v

v O

{

(

r ControNed Electronic Fonn Page 1 of 2 File: 12-02c. doc L

See NEP Table of Contents issued: 6/08/98 NEP-12-02C

Rivizian Summarico CALCULATION NO. QDC-0200-M-0768 PAGE NO.: 2 REVISION SUMMARIES REV: 0 REVISION

SUMMARY

InitialIssue

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Electronic Calculation Data Files:

(Program Name, Version, File name ext / size /date/ hour /: min)

Prepared by:

LU /

d

//~[f~(($

~

[

Print /Sp Date

~

l Reviewed by: Ou y //. 3elley/XJ un r0O#l),,-

n/27/98 Pr'in't/ Sign "

bate '

Type of Resiew

[$ Detailed

[ ] Alternate

[ ] Test Supplemental Review Required

[ ] Yes (NEP-12-05 docummtation attached)

[ ] No Supenisor

/

(

DOANY ASSUMPIlONS NTHIS CA!IULA110NREQUEELATERVERIFICATION [ ] YES [X]NO Tracked by:

{

REV:

REVISION

SUMMARY

Electronic Calculation Data Files:

(Program Name, Version, File name ext / size /date/ hour /: min) f Print / Sign Date Reviewed by:

Print / Sign Date Type of Review

[ ] Detailed

[ ] Alternate

[ ] Test Supplemental Review Required

[ ] Yes (NEP-12-05 6-tation attached)

[ ] No Supervisor

/

DOANYASSUMr110NSNTHISCAlilRA110NRBQUIRELATERVERIFICA110N [ ] YES [ ] NO Tracked by:

Controlled Electronic Form Page 2 of 2 File: 12-02c. doc r

See NEP Table of Contents NEP-12-02C issued: 6/08/98

re p u s ii in C;lcul;ticn Tcbla Of Centents CALCULATION NO. ODC-0200-M-0768 REV. NO. O PAGE NO. 3 SECTION PAGE NO.

SUB-PAGE NO.

TITLE PAGE 1

REVISION

SUMMARY

2 TABLE OF CONTENTS 3-PURPOSE / OBJECTIVE 4

l METHODOLOGY AND ACCEPTANCE 4

CRITERIA ASSUMPTIONS 4

DESIGN INPUT 5

REFERENCES 8

CALCULATIONS g

SUMMARY

AND CONCLUSIONS 33 ATTACHMENTS Attachment A 7 Total Ccntralled Electronic Form Page 1 of 1 File: 12-02d. doc f

See NEP Table of Contents issued: 9/23/97 NEP-12-020 f

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l CORAAONWEALTH EDISON CORFANY cas ru n aTION NO. QDC-0200-M 0768 l PAGE NO.4 REVISIONNO. 0 l

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1.0 Purpose

The purpose of this enladmeiart is to evoluoto the structural integrity of the flaws found in the core spray line of Quad Cities Unit 1 per the requirements of BWRVIP-18. The evaluation wil determine the structural integrity for a 48 month, hot operating Penod and the calculabon wel also propect the remarung life of those flowed locatens. The entusbon is bened on the visual and UT eneminston results descrbed in Attachment A. The detaled flaw dimenmon is provided in Attachment A. Core spray line flows were found in the HAZ of the circumferental weld of the elbow to the thermal sleeve

.l (P4d) of the 290s downcomer of the upper sparger, and the 110s and 200e downcomer of the lower

- shroud -

2.0 anothodology and Acceptance cetterte:

2.1 RAsthodology

Por BWRVIP-18 these fisws are swelusted using the limit load methodology of ASME B&PV Code Secten XI, Appendet C, Reference 1. This methodology assumes a plaste collapse falure mode of the fiswed cross-secten. Plaste milapse failure occurs when the romaning uncracked ligament reaches a plastic flow stress level of og and behaves as a hinge at faRure (Reference 8). This failure mechanism is appropriate based on the inherent fracture toughness and ducWity of type 304 austenitic stomises steels

' As defined in ASME Sechon XI, Appendoc C, the flow strees, og is defined as 3Smat operetng temperature. For these sweluatens, S, is 16950.0 pai at a temperature of 550'F(Reference 13).

2.2 Acceptance Cetterte:

Por BWRVIP-18 the flaw evaluebons performed in the ceaa da% emotion are base on the ASME B&VP Code Secten XI, Appendbc C fisw acceptance critorie which requres a load safety factor (SF) of 2.77 for j

the normallupset conditens and 1.3g for the emergency /foulted conditions. The load margin reported in this naindahnry jg dgllngd gg the ratio of the acceptabit Code strees for the end of twelualDn penod flew length to the actual applied strees. In additon to the load marges, the prodched remaimng months of cperation are determined by calculatng the onbeel flaw sies which would meet the acceptable Code stress t-requrements, and then calculatng the months of operston at 5 x 104 inch / hour for the measured flaw to.

grow to the cribcelflowlength f

3.0 Amoumptione

Although the UT eneminaten was capable of determining the exletence of intomal and extemal

{-

surface fisws, it was not able to determine whether or not they were connected through wall. For conservellem, these eweluelens assume the flaws to be through wall.

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coaA00NWEALTH EDWON COMPANY CALCULATION NO. QDC4200444768 l PAGE NO. 5 REVENONNO. 0 l

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l 4 o ossioninput:

4.1 Flaw Characteritahon During the Q1R15 in-weesel mapecelons, fisws were found at the P4d weids on the 290=

downoomer (upper operger), and the 110s and 200s downcorner (lower operger) elbow to thermal miseve couer weids.. Tne new in each albow is in the some general location as presented in Figure 1. Ultrasonic Examinagons (UT) and Enhanced Visual Examinston (EVT-1) were performed dunng this outage Attachments A provides a descrpton of the flaws idondned by the UT and EVT-1 inspechons. Bened on the demonphon provided in attachment 1, the following fisw charactedstics are used for those sweluetons Core Sorav 8 laa., nn.,oer Thermal Sleeve CAlae and 8w-Wald (A"d) at 290s:

WNH 0* being the 12:00 o' clock poetion, the flaw is a through well, orcumferential flaw 3.7"long starting from 140* to 204* (identNied as too indications because of he obstruodon of me seem weld at 6:00 o' clock poeltlan). The fisw is in the elbow HAZ of me butt weld. The UT examinston covered 100% of the weld aucept for the longitudinal seem wold at the emirados of the elbow where the transducer lost contact.

This flaw was determined to be 7" long dunne the Q1R14 examinston. More accurate saing by automated UT and EVT-1 resulted in the new flaw eine length of 3.7".

Core Sorav Lower Aa='oer Thermal Sleeve CA8-and Fahe== Wald (CP4d) at 110*.

Wuh 0* being the 12:00 o' clock posibon, the flaw is a through well, cucumferenhet flaws 2.9" long starths from 130* to 180a. The flaw was indentlRed by UT to extend from 130= to 16>

including crack tips. The UT inspecton experienced liR-off at the 180s elbow long seem; howower the remainder of the weld was covered by the UT exam. EVT-1 was used to confirm the crack and the end points. The addibonel 0.7" from the EVT-1 inspecton s,,

cf.4 bounds the BWRVIP-18 requeenwnt to include 2x% of uninspected UT regens The flaw is in me elbow HAZ of the butt weld.

Core Sorav Lower amener Thermal Sleeve Can-and M = 7.W (C"O) at 260s:

c WNh 0+ being me 12:00 o' clock poolbon, the flew is a through wall, circumferennel flaw 3.5" long sterling from 120* to 170s. The flow was indetNied by UT to autend from 120s to 170o including crack tips. The UT inopochon empenanced till.cff at the 180* elbow long seem; however the remainder of the weld was covered by the UT exam. EVT 1 was used to conhrm the crack and the end pomis. The addeional 0.61" from the EVF-1 inspecton bounds the BWRVIP-18 regurement to include 2x% of unmepected UT regens The flaw is in the elbow HAZ of the butt weld. This flaw was determined to be 4.6"long dunne the

[r Q1R14 eneminellon. More accurole sinng by automated UT and EVT-1 reeuned in the new flow eine of 3.5".

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COREADNWEALTH EDISON COWANY CALCULATION NO. QDC-020H4-0768 lPAGENO.6 REVISION NO. 0 l

l-l l

Comportolon of the inopoetion Results From Q1R14 and Q1R15 Wold P4d Q1R14 Q1R15 2100o VT 5.5" 3.7" UT*

7.0"*

3.7" 110 VT No Flaw 2.g" UT N/A 2.7" 200=

VT 3.5" 3.5" UT*

4.6"*

2.g"

• UT inspaamans shsene Q1R14 used a alsk as eis desimy sputan for eis launual UT. For Q1R15 ein GE Fisy Aimamssed. compiser canoned, anssess uneasic scesune Hand C8L2000 syuten was used, wNah pnndeed mee aconses aimns.

The evolueton penod is deAnod as a 48 month hot operating penod The crack growth during this portod is bened on the conservelse IGSCC rate of 5 x 104 in/hr as deAned h Reference 11. The thermal transsent and spension loads assocated with the start-up/ shutdown and normal operabon of the vessel are inagnincent. During normal operston, the htsmal and odernal line pressure is aquel This eliminates any fabgue concoms amwth pipeline pressure Auctuebons Bened on the low now velocibes and the hormontal ngdity (high fundamental frequency) of the core spray lines, now induced vtratons will be neglighie Conesqueney, fehgue crack growth will not contribute seniReaney to eneck growth and is not conodored h the projected flaw length.

- The end of evolumbon penod Asw lengths used in those eweluetons are determhed by applying the IGSCC growth rate of 5.0 x 10 4 inthr to each of the Asws for 48 months 4.2 Metanol Proportes Based on istmcston drawings, References 2-4, the piping elbow and thornial sleeve were fabncated from ASTM A403, WP304 and A240, T304 material, respechwely. References 4 and 6 identWy the welding processes to be AS 3-16, a 100% Gas Tungsten Arc Wold (GTAW) for the to elbow to the thermal sleeve collerweid.

The metallurgecal evolueton of these fimws concluded that these Asws are the result of inter-granular otross corrosen crecidng, IGSCC. The metallurgical owelueton also concludes that these lines are not

=P to radiobon embrittlement because the neutron fluence level at this elevabon in the RPV is below the requesd redabon threshold level.

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CORARAONWEALTH EDISON CORFANY

+as naa aTION NO. QDC4200#4768 l PAGE NO. 7 namsIONNO. 0 l

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l 4.3 Load Defintions.

The core spray line is requred to prcmde core coolant under poet LOCA condibons when the veneel is at a reduced pressure, i.e. less then 325 peig. Dunne normal and upset operating condtions the spray line is not intended to funceon and is at the same pressure and temperature as the veneel ar.aulus. Por Ref.12, the maamum diNorential pressures of the core spray piping and the reecer preneure are:

Test condibon using Flow rate DiNorentual Prosaure condeneste storage tank 5350 gpm 64 paid injection Mode 4600 gpm 47 paid The mandmum core spray flow rate per the Quad Chios UFSAR is 5650 gpm. Therefore, the mammum design dlNorenbal pressure is 71 paid per the emirad=8-wi sechon 5 of Reference 5. The 71 paid will be used in the emergency and faulted condtion flow evolusion However, the pressures of 47 paid and 64 paid of the infechon mode wil be used in the leakage calculaton The loeds used for the elbow flaw evaluabon are taken from the piping analysis results reported in

- Reference 14 for the upper and lower core spray loops. These models generated the adel forces and bending moments actng on these flows for the following loads:

- Weight (W)

-Injection Force (i)

- Sommic (OBE/SSE)

- Operahng Drag (Dn)

-LOCA (Df)

The design basis load cominnebons were evalueled per BWRVIP-18 and the worst case normallupset aruf emergency /foulted condtion load comtunebons were used for these evolustons.

Receculebon Lhe Brook LOCA event produces loads which bound the MS Line Break LOCA loads for this pipmg 4

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-CALCULATION NO. QDC-0200.M.0768 l PAGE NO. 8 REVISION NO. 0 l

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8.8

References:

5.1 References

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1. AShE B&PV Secten XI 1989 Edition, Appendk C.

2. Wilamette iron & Steel Company, Shop Order No. 860510, Drawmg No. E861 sh.1, Rewmon J.

[

3. Wilamette iron & Steel Company, Shop Order No. 660510, Drawmg No. E861 sh.2, Rowson B.

4.

WNiamette iron & Steel Company, Shop Order No. 660510, Material Drawmg No. E861, Rowmon D.

5. Core Spray Line Ppng Analyses, N% No. OC-NPD 0038, Rev.1

6. Wilamette Iron & Steel Company, Welding Procedure Speci8cahon AS 3-16.

7. GENE Purchase Speci8caten 21A3319," Standard Requirements for Core Structure", Rev.1

8. "Evolustion of Flows in Austonibe Steel Piping", EPRI NP 4690 SR, July 1986.

9. " Instability Prodotenu for Circumferentially Cracked Type - 304 Stainless Steel Under Dynamic Load",

{

EPRI NP-2347, Apr81982.

10. " Degraded Piping Program Phase 11, Semi Annual Report, October 1964 - March 1985", Nureg / CR A082, BfAl-2120, Vol. 2 July 1985.

11.' "BWR Vessel and internals Project BWR Core Spray intamals triepaet wi and Flaw Evalualen Guideline," (BWRVIP-18), EPRI TR-108740, July 1996.

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12. GENE-161F312," Core Spray System Process Dis 9 ram", Quad Cibes 1&2.

13. ASME B&PV Code SocIlon lit,1989 Edibon, Appendet 1.

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14. NDIT SO40-QH-0572 " Loads on RPV Intomal Core Spray Ppng - Quad Cides 1"

5.2 Attachments

1. GENE Later fmm John Easton to T. Wojck regardmg the woual inspectons of the 110o,260s and 290s Core Spray Downcomers, dated 11/24/1998

5.3 Figure

1.

P4d Wold Configuraten

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F i,....

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COMMONWEALTH EDBON COMPANY

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CALCULATION NO. QDC-0200-M 0768 l PAGE NO. 9 REVISION NO. 0 l

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l s.o Calcuistions:

8.12Mk Upper Sperger Elbow Wold AP4d Flow Evaluation:

8.1.1 Piping Demonolone and Motorial Proporties Outside Diameter, DJ D,:=6.625 in Nominal Outside Diameter, DJ D, := 6.0 NominalWallThicimess, t; tn := 0.280 in Mean radius R D,-t, t

2 Flow Area, A,:

Ag:=*.(D -2t)

A " 28 89'I" f

o n

D,2- (D - 2.t )'

[

Axlal Area, A-A := s-A = 5.581 *in o

3' 2

4 D,#- (D - 2.t,[

o 3

Secten Modulus, Z.p:

Z p := x-Zp = 8.496 in 64-2 S,,,at Operahng Temperature:

S,:= 16950 psi

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COGSGONWEALTH EDISON COtrANY l

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CALCULATION NO QDC-020044-0768 l PAGE NO.10 ftEVISION NO. 0 l

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l S.1.2 Lead Dollnition for 20p Downcomer:

Loads are from PIPSYS analysm RUNID UPPERNEW, dated 11/25/98, NP 307. No system compliance was modeled Compressive axial forces were ce,a.-d.d/ set equal to 0.

Axial Forose (Ibe):

Proesure Force Normal and Upset Condibon Pressure, PJ P,:= 0.00 psi Emergency and Faulted Conditon Pressure, P,:

P g:=71 psi F p, :=P, A r F, = 0 4bf p

F pf:=P (A g Fpf = 2051.2 =lbf Weight Axial Force, W:

W :=0 Ibf Normal Drag Axial Force, D,;

D,:=0 lbf RLB Drag Axial Force, D,:

D :=0lbf f

infechon Axial Force, Fi F g :=0 lbf Sommicinerte Axial Force OBE Force, F,,,:

FOBE := Ill.0 lbf SSE Force, F., :

F SsE :=221.0 lbf Bending Momente (ircibs):

Weight, M,;

M,:=hl15'+ 5 12 in lbf 2

9,:=h28 2

Normal Drag, M,;

M I.12 in lbf a

Df:= 336'+(-31)'.12 in Ibf RLB Drag, M,:

M injechon Axial Force, M M :=h(-54)* +(-48)' 12 in Ibf i

i Seismic Momente:

OBE, M,e:

M OBE := 103' + 70'.12 in lbf a

M ssE :=J205 + 140 12 in ibf 2

2 SSE, M.,,:

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1-1 f-CORAADNWEALTH EDIBON CORFANY -

1 CALCULATION NO. QDC-020040768 l PAGE NO.11 1

RIMSION NO. 0 l

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i 4.1.3 Eltow RAemtwane Strees for 2008 Doumoomer:

Normal and Upest Condibons i

W+D, l

Pmal :=

Pmal 09si A

i W+ F g + F pr Pmn2

• Pmn2 = 367.511 9si A

f j

W+D,+FOBE p

Pmu4 :"

""4 " ' '

A l

l Emergency and Faulted Conditions:

I W+ D +FSSE n

Pmfl :=

Pmfl - 39.5%9si A

i i

W+Dr PmD "

mD = 0pi A

W+ F g t F pg "f4 A

Pmf4 = 367.51I = psi l

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l-f CORRIONWEALTH EDBON COMPANY CALCULATION NO. QDC6768 l PAGE NO.12 l

fumSION NO. 0 l

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6.1 A Ellow Bending Strees for 200* Downoemer:

Normaland Upest Condtons f

M wtM De Pbal :=

Pbal = 202.1629si P

M w+M i Pbn2:

Pbn2 = 264.638 ysi g

P M,+M 9,+ M OBE Pbd :=

Pbd = 378.064 9si

.f P

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Emergencyand FauHed Condibons M,+ M p,+ M SSE Pbfl "

Pbfl = $52.798 ys.

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1 P

M,+M Df PbD ~

Pb6 = 639.1929si Z p Mw+M i PbM ::

PbN = 264.6389si Z

P ASAE Safety Factors:

Normal and Upeet Condtons SF n :=2.77 Emergency and Fauhod Condsons.

. SF g:= 1.39 L

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CALCLEATI3N NO.0DC-020044768 l PAGE NO.13

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8.1.5 Appued Bending Stroos, P, for 200* Doumoomer:

Nonnaland UpsetCondbons PABel:=SF -(Pmal + Pba1)- P,3 PABal = 559.9889si and P,,g 50.5 S P,3=09si

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m PABn2 := SF -(Pmn2+Pbn2)- Pma2 n

p Bn2 = 1383J4 ysi A

.nd Pmn250.5 S,

Pan 2 = 367.5II 9si ABM :=SF -(P,,4+ Pbu4)- P

,4 PABu4 = 1082.4379si P

n and P,,450.5 S,

p

,39,gg,,p,,

Emergency and Faulted Conditions:

PABfl :=SF r(P,gg + Pbft)- Perg PABn " 783 832 " Psi and Parg 51,0.S.

Pmfl = 39.5%9si PABO :=SF r(PmD+PbDj - P,o PABD " 888 477 ' Psi and PmDS1.0 S,

PmD = 0= psi

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PABN ::SF p(P,g4 + Pbf4j - P,g4 PABN = 511.175 apsi

, and Pmf451.0 S,

Pmf4 = 367.511 apsi r

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commeONWEALTH EDBON COMPANY

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CALCULATION NO. QDC-0200 M-0788 l PAGE NO.14 REMBION NO. 0 l

l l

l s.1.s Load namgin at the End of Evaluation Portod,290* Downcomer:

As deocted in sechon 4.1, the crack is 3.7" long startng at 140= and sends to 204o Tne crack length at the end of evolumbon period of 48 month hot operakon is dadt :=510"Y hr crack _I g :=3.7 in+2 dadt 48 month crack _I g = 7.156ain dI-I Half crack angle:

0 :-

red 6 = 1.128 2R 8.1.E.1 For Design Basie Conditione. (Normal Test Condition is the Goveming Case)

(

For q+b < p and a:=t,

"_ = 1 i n

$(6):=1.z ". 0-s 3S,/

2(

t o 0 + p(0) = 2.123 0 + p s:

Allowable tAmding stress PBn2(8):=6 " 2 sin (p(6)) 1cin(0)

{

t, PBn2(6) = 25076.141 apsi Applied stress including the Code safety factor

(

PMn2 = 1383.54 apsi Load margin beyond the Code requerement PBn2(6) = 18.12 Pi M n21

~ ~ ~ ~

I CORAGONWEALTH EDISON CORFANY m n u aTION NO. QDC-0200444766 l PAGE NO.15 i

ftEVISION NO. 0 l

l l

l

~

l S.1.7 Projected ufe for 200* Downoomer:

1 S.1.7.1 For Design Basis Condloons. (Normal Test Condition is the Goveming Case) l For 0+p < z and a := 0.28 in

..=1 t n

$(9):=1.s 1 0- :

2 4

t, 3S m/

PBn2(6) := 6-S

,(2 sin ($(0)), sin (8)

)

psi (

i n j

an :=2.251989

)

Total Flaw i

9 := an,an +.01. an +.1 rad D

0180 6

o 0

$(0) 0 + $(0)

PBn2(6) 2.252 0,433 2.685 2045.422 258.059 14.919 2.262 0.428 2.69 1956.407 259.205 14.986 2.272 0.423 2.695 1869.213 260351 15.052 2.282 0.418 2.7 1783.828 261.497 15.118 2.292 0.413 2.705 1700.237 262.643 15.184 2302 0.408 2.71 1618.428 263.789 3.251 2312 0.403 2.715 1538385 264.934 15317 2322 0398 2.72 1460.095 266.08 15383 PMn2 = 1383.54 vsi 2332 0393 2.725 1383.547.

267.226 15.449

~

2342 0388 2.73 1303.*iT3 2683 72 15.516 2352 038?

2 755 1235.593 269.518 15.582 i

Critical := 15.449 in

)

i conAADNWEALTH EDWON COMPANY a

enLCULATION NO. QDC-020040768 l PAGE NO.16 l

MMMON NO. 0 l

l l

l 1

~

l The time for the crack b grow from 3.7" to the cribcal crack length is Time 2 := Critical-3.7 in 2.dadt l

Predicted life := Time 2

~

i j

Predicted _ life = 163 weath d

i l

l i

l

I CosasONWEALTH EDtBON COMPANY CinLCULATION NO. QDC4200 M-0768 l PAGE NO.17 f4MBION NO. 0 l

l l

l

~

4.2 110e Lower Sparger Eltow Wold CP4d Flow Evalentle t:

8.2.1 Piping Dimonolone and Motorial Proportise Outside Diameter, D; D,:=6.625 in Nominal Outsade Diameter, DJ D, := 6.0 NominalWall Theknees, t; t, := 0.280 in Mean radius R D

-t, o

2 A := -(D - 2 t,)2 A r= 28.89ain' FlowArea A,:

f o

2 Axial Area, A-A:::

A = 5.581 ain 4

do-(D -2t f D

o a

s Sechon Modulus, Z.p:

Zp := s-Zp = 8.496.in 64 - "

2 S,,,at Operahng Temperature Sm := 16950 psi 4

i

{

l ConA00NWEALTH EDBON COMPANY f

CALCUI.ATION NO. QDC-0200-M.0768 l PAGE NO.18 nEvielON NO. 0 l

l l

l

' W Dennition for110e Downcomer:

f a are envolloped from PIPSYS analysm RUNIDs LOWERNEW and RELNEW, dated 11/25/98, at 1 'l07. No system compliance was modeled Compresswe axial forces were cer.. ddi set equal 0:

.. /orces(lbs):

Pressure Force Normal and Upset Condition Pressure, PJ P,:= 0.00 psi Emergency and Faulted Condition Pressure, P,:

P :=71 psi f

F p, := P, A r F p, = 0 albf

{

F pg:=P A y F pr = 2051.212 =lbf p

Weight Axial Force, W:

W :=00 lbf Normal Drag Axial Force, DJ D,:= 00 lbf RLJ Drag Axial Force, D,:

D g:= 00 lbf injechon Force, Fe F g :=00 Ibf

{

Sommicinertin Axlel Force OBE Force, F.:

FOBE := 123.0 lbf SSE Force, F :

FSSE :=246.0 Ibf Bending Momente(in-Ibs):

2 M,:= 126 +(4)2.12 in lbf 9,:=h.12 in Ibf Nonnal Drag, M,4 M

M pr:=h352 +(-56)2.12 in lbf 2

RLB Drag, Mo/

injection Axial Force, M M g :=d(-49)'+(-48)212 in lbf i

{

Sommic Moments:

OBE,Mm:

M OBE := 125'+ 83.5 12 in lbf 2

(

SSE,M.:

M SSE := 250 167 12 in Ibf 2

2 I

L

(

CORRAONWEALTH EDSON COtrANY

(.

CALCULATION NO. QDC-0200444768 i PAGE NO.19 ftEVISION NO. O l

l I

I S.2.3 Ebow RAsmtwane Strees for 110* Downoomer:

Normaland UpsetCondihons:

P

,3:=

P,3 = M

(

W + F g + F pr pmn2,

Pmn2 = 367.511 9si A

W+ U +FOBE n

p pmM = 22.038 vsl

{

Emergency and Faulted Conditions:

W+D +FSSE n

p pmD = 44.0759si

+o<

,me = 0,si W + F g + F pr Pmf4

A Pmf4 = 367.511 Tsi 6.2A Elbow Bendin0 Strees for 110* Dommoomer:

Normaland Upset Condibons:

{

w.+==

,,n, = 2i,.022,si A P

[

• • I p

P g = 274.946 ysi P

M w+M Dn+M OBE p

.=

P

= 431.359si P

(

(

CORAGONWEALTH EDISON COtrANY CALCUULTION NO. QDC4200-M4768 l PAGE NO.20

[

RumsION NO. 0 l

l l

l Errorgency and Fauited Condtons M,+MDo + MSSE Pbfl :=

Pbfl = 643.678 ysi f.

M w+MDf Pb 6 :=

PbD = 681.5029si

(

P M,+Mg P

(

bf4" Z

Pbf4 = 274.9469si P

AttA! Safety Factors:

Normal and Upest Condtons

(

SF n :=2.77

(

Emergency and Fautted Conditions:

SF g:= 1.39

(

(

(

{

(

(

L

l l

I COMMONWEALTH ED50N COMPANY f

CALCULATION NO. QDC=0200-M 0768 l PAGE NO.21

[

REVISIONNO. 0 l

l l

l

[

s.2.s Applied sendine memos, P. for 110' Downcomer:

Normaland UpeetCondibons:

P ABal := SF -(P,,g + Pbn t ) - P,,g PABal = 606.692 apsi n

P,js0.5 S,

P,,g = 0 apsi PABn2 := SF,-(Pmn2 + Pbn2)- Pmn2 p Md = 1412.0959ai and P ma250.5 S,

Pmn2 = 367.511 apsi P ABu4 := SF -(P,,4 + Pbu4)- Pmu4 PABu4 = 1233.846apsi 3

and P,450.5.S,

P,,4 = 22.038 apsi Emergency and FauHed Conditions:

PABfl :=SF g-(Pmfl + Pbft )- Pmfl PABn = 911.901 apsi and P mflSt.0 S, P,rg = 44.075 apsi PABD :=SF r(PmG+PbO)- PmD PABO = 947.288 apsi and P mD$1.0 S, PmD = 0 apsi PABN "Si f(P,r4 + Pbf4)- Pmf4 PABf4 = 525.5049si and P ar4st.0 S,

P,r4 = 367.511 = psi c

l

.~

~

i COWOONWEALTH EDISON COWANY CALCULATION NO. QDC-0200444768 l PAGE NO.22 ftEVISION NO. 0 l

l l

l 8.2.4 Load Mergin at the End of Evaluation Period for 110e Downcomer:

As described bi sedan 4.1, the crack is 2.9"long. The crack length at the end of evaluaten penod of 48 month hot operalenis i

dadt :=510"8 br crack I ; :=2.9 in + 2 dedt 48 month crack _1 g = 6.356ain crack Ig Half exack angle:

0 :=

. rad 0 = 1.002

~

}

2R 8.2.4.1 For Deelen Basis Conditions (Normal Test Condition is the governing case) s For 0+$ < x and a :=t "I

n t,

p(0) :=1

• . 0- z ""

2(

t, 3S,/

0 + p(0) = 2.06 0+p5 Allowable bending stress PBn2(0):= 6 "/2 sin ($(0))

• sin (0)\\

8 t

/

(

n PBn2(0) = 29164.4039si Applied stress including the Code safety factor PABn2 = 1412.095 apsi Loed margin beyond the Code requirement PBt2(0) = 20.65 Pz g3,3) i

[

f.

ConSIONWEAl.TH EDBON COMPANY

['

cal.CULATION NO. QDC-0200-M 0768 l PAGE NO.23

[

ftEvielON NO. 0 l

l l

l

[

8.2.7 Projected LNe for110* Downcomer. ~

[

S.2.7.1 For Desien Basis Conditions (Normal Test Condition is the Goveming Case)

For 0+p < z and a :so.28 in

..=1 t n

$(0):=1 x-.

• O-n-2; i

3S n

m/

S,1

\\

PBn2(0) :=6-

,2 sin (p(0))

, sin (0)i psi t

g o

j an :=2.2482327 Total Flaw f

6 :=an,an+.01 an +.1 rad Le @

\\

D 20 180 9

f e

6 p(0) 0 + p(0)

PBn2(0) 7 2.248 0.435 2.684 2079J32 257.628 14.895 2.258 0.43 2.689 1989.629 258.774 14.961 f

2.268 0.425 2.694 1901.753 259.9?

15.027 2.278 0.42 2.699 1815.69 261.066 15.093 2.288 0.415 2.704 1731.427 262.212 15.16 f

2.298 0.41 2.709 1648.95 263358 15.226 2308 0.405 2.714 1568.245 264.504 15.292 2318 0.4 2.719 1489.298 265.65 15358 PABn2 = M12.M59si 2328 0395 2.724 1412.095 266.796 15.425 2.338 039 2.729 1336.62 267.942 15.491 2348 0385 2.734 1262.86 269.088 15.557 Critical := 15.425 in i

L e

[

[

COAMAONWEALTH EDISON COR5'ANY CALCULATION NO. QDC-0200-M 0768 l PAGE NO. 24 ftEVISION NO. 0 l

l l

l

[

T=

.er

- - 2.,e.,..

i.,,,,,.

The2 = Critical-2.9 in 2 dedt f

Predacted_ life := Time 2 i.,

or.. iu,..

[

[

{

{

(

(

(

(

(

L

CoaAAONWEALTH EDISON COMPANY CALCULATION NO. QDC-0200-M-0768 '

l PAGE NO.25 nEviseONNO. 0 l

l l

l 8.3 206 Lower Sperger Elbow Wald DPed Flow Evaluation:

8.3.1 Piping Dimenolons and RAstorial Proporties Outade Diameter, D,:

D,:=6.625 in Nominal Outade Diameter, D,;

D,:= 6.0

{

Nominal WallThicknees, t,;

t,:=0.280 in Mean radius R D - t, o

j 2

Flow Area, A,:

A g:= * -(D,- 2 t,)2 2

A = 28.89ain f

~

2 Amiel Arsa, A-A := x-A = 5.581 ein 4

- (D - 2 t ")*

D soebon Modulus, z.p:

z

=s-z = s.496 ain' p

p 6a 2

S,at Operahng Temperature:

(

S, := 16950 psi

(

I

(-

1 1

i

/

[

(

COMIAONWEALTH EDMON COMPMY f.

CALCULATION NO. QDC-0200-M 0768 l PAGE NO. 26 ftEvislON NO. 0 l

l l

l s.s.2 Load Dennmon ser the aso. Downoomer:

[

Loads are enveloped from PIPSYS analysm RUNIDs LOWER 2 and RELNEW, dated 11/25/98, NP 307.

No system compliance was modeled Compressurandel forces were os,a.f S set equel to 0.

i Axial Fomes (Ibs):

Pressure Force Normal and Upeet Condton Pressure, PJ P, = 0.00 psi Emergency and Faulted Condibon Pressure, P,:

P g:= 71. psi FPn :=P, A r F, = 0 4bf p

F pr:=P g A g Fpg = 2051.2124bf Weight Axial Force, W:

W :=00 lbf Normal Drag Axial Force, DJ D,:=00lbf RLB Drag Axial Force, D,:

D g:=00 Ibf injechon Force, Fe F g :=00 lbf Seemicinerte Axial Force OBE Force, F :

FOBE :=123.5 Ibf a

SSE Force, Fm:

F SSE :=247.0 Ibf f

Bending atoments(in-lbs):

Weight, M; M,:=hl26 +(-4)2.12 in Ibf 2

M p,:=h29 +(0).12 in Ibf Normal Drag, M ;

2 o

{

RLB Drag, M ;

MDr:= 352'+56 12 in ibf 2

o injechon Axial Force, M M :=d(-49)2,g4g)2.12 in Ibf i

i Sommic Moments:

2 2

OBE, M,:

MOBE := 125.5 g3,3 12 in Ibf o

2 2

SSE,M :

M SSE := 251 167 12 in lbf I

~

t t

i r

CORSAONWEALTH EDWON CONPANY d

d CALCULATION MO. QDC-0200444788 l PAGE NO.27 ftEVISION NO. 0 l

l l

l 1,

S.3.3 Elinow RAmmisrano Stress for the 200* Doumoomen 4

Normaland Upest Condibons 4

W+D n P,,,3 :=

P,,g = 0 vs-W + F ; + F pr 4

3 Pmn2 "

Pma2 = 367.511 9s:

A 4

W+ D,+ FOBE y,g :=

P,,4 = 22.127 vs-A i

Emergency and Faulted Condibons W + D,+ FSSE p,gg :=

Pmfl = 44.254 vs-A W+Dr Pm D :=

PmD=09s A

W+ F ; + F pr

, mf4 ;*

A P,g4 = 367.511 9si S.3A Eltsow SmW Stroes for the 200* Doumcomer:

Normal and Upwt Condibons M,+M 9, p h I:=

P g,,g = 219.0229si E P M,+M i pg :=

P g,n2 = 274.9469si E

P M,+M 9,+ M OBE

,pg :=

P,,4 = 431.9389si i

P i

1 COGAIONWEALTH EDIBON COWANY CALCULATION NO. QDC-020044-0768 l PAGE NO.28 ftEVISION NO. 0

[-

l l

l Emergencyand Faulted Comkhons

^

Mw+MDo + M SSE Pbn :=

Pbfl = 644.853 apsi A P Mw+M Df PbD :s Pb0 = 681.502 pi P

M,+Mg Pbf4 :=

Pbf4 = 274.946 apsi A P AstE! Safety Factors:

Normaland Upeet Condibons SF, := 2.71 Emergencyand Faulted Conditions:

SF g:=lJ9 i

)

{

C o O N o r.A tr s = = o N C o A,u tmLCULATION NO. QDC-020044 0768 l PAGE NO.29 L

ftEVWONNO. 0 l

l l

l 7

t s.s.s Appued sensing Stroes, P, for the 200* Downoomer:

Normaland UpsetCondtons PABal := SF,-(P,,g + Pbal)-P,,g PABal = 606.6929si P,g50.5 S,

P,,g = 09si PABn2 := SF,-(Pmn2+Pba2;- Pmn2 PABn2 = 1412.0959si and P g 0.5S, Pmn2 = 367.511 9si 5

PABM := SF,-(P,,4 + Pbu4)' - P,,4 PABu4 = 1235.6329si and P,,450.5 S P,,4 = 22.1279si m

Emergency and Faulted Conditions:

PABn ::SF r(Pan +Pbft )- P,gg PABn = 913.6059:1

{

and P,ggsl.0 S,

Pmfl = 44.2549si PABD :=SF r(PmD+PbD)- PmD PABD = 947.288 ysi and PmDSI.0 S, PmD=09si PABN :=SF g-(P,g4 + Pbf4)- Par 4 PABN = $25.5049si and Pmf4st.0 S, P,g4 = 367.511 ysi L

4 I

CohneDNWEM.TH EDWON COMPANY CALCULATION NO. QDC-0200-M-0768 l PAGE NO 30 ftEVISION NO. 0 l

l l

l 8.3.8 Lead RAergin at the End of Evaluation Period for the 200* Downoomer:

i As described irt secton 4.1, the crack is 3.5" !nng. The crack length at the end of emiustion permd of 48 month hot opershonis dadt :=510'd hr crack _I g :=3.5 in+2M 48 mondi crack _I g = 6.9564n crack I~3 i

Half crack angle 8 :=

rad 0 = 1.096 2R 8.3.8.1 For Design Beste Conditione. (Normal Test Conditon is the governing case)

For 0+p < z and a :=t

,=I n

t p(0):=1I P

I 0- s mn2 a

2(

t 3S o

m/

0 + p(0) = 2.108 0 + $ $s i

Allowable bending stress PBn2(0):=6 2 sin (p(0)) 1 sin (0)\\

t, j

l i

PBn2(0) = 26076.3559si Applied stress including the Code safety factor PABn2 = 1412.0959si Load margin beyond the Code requirement Bn2W, 3,,47 (P ABn2) i

i CORAGONWEALTH EDISON CO8FANY CALCULATION NO. QDC-020044-0768 l PAGE NO. 31 ftEVISION NO. 0 l

{

l l

6.3.7 Projected Life for the 200* Doumoomer.

i 6.3.7.1 For Design Basis Conditione.- (Normal Test Condition is the Goveming Case) l For 0+$ < x and a :=0.28 in

"=1 t,

p(0):=1 x

" O-2; t

3 5,j o

S, t PBn2(6) := 6-2 sin (p(8))

, sin (9)y E Psi t

z n

j i

an :=2.2482327 Total Flaw 0 :=an,an+.01 an +.1. red 9

p(0) 0 + p(9)

PBn2(0) 2.248 0.435 2.684 2079332 257.628 14.895 2.258 0.43 2.689 1989.629 258.774 14.961 2.268 0.425 2.694 1901.753 259.92 15.027 2.278 0.42 2.699 1815.69 261.066 15.093 2.288 0.415 2.704 1731.427 262.212 15.16 2.298 0.41 2.709 1648.95 263358 15.226 2J08 0.405 2.714 1568.245 264.504 15.292 2318 0.4 2.719 1489.298 265.65 15358 2328 0395 2.724 1412.095 ABn2 = 1412.095 = psi 266.7 %

15.425 2338 039 2.729 1336.62 267.942 15.491 2348 0385 2.734 1262.86 269.088 15.557 Critical := 15.425.in d

I

I I

CosM00NWEALTH EDSON COMPANY

{

CALCULATION NO. QDC-0200440768 l PAGE NO. 32

{

ftEVINON NO. 0 l

l l

l

{

The time for the crack to grow from 3.5" to the enbcal crack length is The2. Critical-3.5 in 2 ded:

Prodsted_ life := Time 2 Predicted _ life = 166wonth I

l i

COMMONWEALTH EDISON COMPANY CALCULATION NO. ODC-020040768 l PAGE NO. 33 REWSION NO. 0 l

l l

l 7.0 Conclusions Using the BWRVIP-18 Flaw Evaluston Gudelines, indcatens on three P4d Core Spray welds (290+,110. and 260. Sparger Downcomers Elbows) were evaluated for two 24 month cycles of hot operation. As shown below the the length of all three flaws at end of ovaluston cycle (EOC) were a frachon of the critcal flaw size and emhtxted siontricant load l

margin. In addition, using conserwtwo crack growth rates, the flaws are predited to be i

structurally sound for a minimum of 163 months of hot operaten which far exceeds the 48 month evaluaton time penod E.. ;y of Flow Evaluation Neoutes Wold Langth EOC Length Cettical Flow Stae Land Margin Predicted Life Ped 29 6 3.7" 7.16" 15.450" 18.12 163 Months 110a 2.9" 6.36" 15.425" 20.65 174 Months 280a 3.5" 6.96" 15.425" 18.47 166 Months

CORAAONWEALTH EDISON COWANY CilLCULATION NO. 00C-020044-0768 l PAGE NO.34 Final RIMlHON NO. 0 l

l l

l N

Figure 1 Flaw LM#ian For the P4d Welds y WELD 84C 58Roua L

{

l AFrE L d

\\

l SLEEVE

$1> vsr rr av/a p

(

,,, pg N WELD PBA i

COLLAR J

SHROUD i

F

~

ATT k N#)sMT A

)

O Qbc. - ozoo -M - o76 8 GENacieer Energy November 24,1998 JEE 4 m is414 Mr. Tom Wojcik Commonweeldi Fdienn Quad Cities Nuclear Station (Construction Dept.)

22710 206* AveNorth Conkwa,IL 61242 309.654.2241 Ext.2616

SUBJECT:

1996 vs.1998 Corseprey UT and IVVI Caenparises (Raference Attadied INR #QlR15-98-1)

Tom:

Attached are the com pensons of the Ultrasonic (UT) and Visual (VT) dets from QlRl4 and QlRIS for the following coresprey piping welds.

l.) AP4d Upper Sparger inlet Elbow to Thermal Sleeve Collar Weld loated (290*).

2.) CP4d 1.ower Sparser inlet Elbow to ThesmalSleeve Collar Weld located (110').

3.) DP4d Lower Sparger inlet Elbow to Thermal Sleeve Collar Weld located (260').

Ragards, Faman OE Projem Manager, QlRIS NDE Examinations Extension:3447 oc: w/o enct W. Bentley

.OE M. Baron Corned l

l l

i

(

Pace a t as A,

ArrAc.d roer4T A

p Q'D C.- 02co-F1 - C'76B

%)

GEInspection Services Ouad Cities 01R151998 Core Sprav UT/IVVI Results Core Spray 290 Upper Sparger Inlet Elbow to Thermal Sleeve Collar Weld Number AP4d:

1996 Results: The UT examination of this location Figure 1, confirmed the presence of the crack. The crack was identified by UT to extend from 110' to 230. The UT was able to identify both ends of the flaw. The flaw LTT length is the same as the visual length on the ID but slightly skewed with respect to the controidal axis. The UT examination did not cover the

(

area from 330' to 30 due to obstruction. However, no visualindication was found in this area.

1998 Results: The "non-qualified" UT exammation of this location, Figure 1, confimled the presence of the previously identified 1996 indications. The indications were identified by UT, Indication 1 extends from 140' to 166 and Indication 2 extends from 188' to 204. The UT exammation was able to identify both ends of the flaws but on indication information was obtained near 180* due to transducer liftoff from the outside radius longseam. Ahhough this cxammation is a "Non-Qualified" examination, due to the configuration, the technique proved to be able to detect flaws in this specific area of the elbow, even with the geometric interference. The Enhanced Visual Examination (EVT-1) confirmed the approximate position and lengths including the area with transducer liftoff from the 180 outside radius longseam.

See the attached IVVI INR # Q1R15-98-1 for photographs of the Visual indications.

i Page1 of6 FAc,2 A2.

o F A'l

CiTDC_ -0 ?_co - M- 07/o 6 GEInspection Services Ouad Cities 01R151998 Core Sprav UT/IVVI Results U or TDC

,l

.,/'

.y j

/

5. 5 - 7. 5"

.., _ ~ "

J90 Elbow to. Shroud Pepe A P-ID 1996 0 or TDC

\\

N, f;".>,=1 y.q ::

q Y9.gC1. 5

Ms

% g. ~"

290 Elbow to Shroud Ptpe AP4D 1998 Visual Flaw Length l

l UT riaw Length t

i Page 2 of 6 PAGE A3 oF A 1

J

. (m Qb c_ - O F_co - M - 6% 8 r

k.J1 GEInspection Services I

I Ouad Cities 01R151998 Core Sprav UT/IVVI Results l

Core Spray 110* Lower Sparger Inlet Elbow to Thermal Sleeve Collar Weld Number CP4d:

1996 Results: This weld was not scanned with the UT examination techniques durmg the 19% outage and, no visualindication was found in this area.

1998 Results: The "non-qualified" UT exammation of this location, Figure 2, identiSed a new indication that was not identified during the 1996 outage. The indication was identified by UT, Indication 3 extends from 130* to 168. The UT examination was able to identify both ends of the flaw but due to transducer liftoff from the outside radius long-m. cound not gain any indication information near the 180* longseam. Ahhough this examination is a "Non-Qualified" exanunation, due to the configuration, the tecimique proved to be able to detect flaws in this specific area of the elbow, even with the geometric interference. The Enh-*A Visual Examination (EVT-1) confirmed the approximate position and lengths including the area with transducer liftoff from the 180* outside radius longseam. See the attached IVVI INR

1. QIR15-98-1 for photographs of the Visual indications.

Page 3 of 6 PACE A tl oF A1

ATrAcA MGNT A

n ptc. -ozoo-M - o% 8 l

u 1

GEInspection Services Ouad Cities 01R151998 Core Sprav UT/IVVI Results O' or TDC

^

x ij N

- 1,,

\\

f\\

,/(

b.S

/'

+

7 c;"

~.s 110' Elbow to Shroud Pipe CP4D 1998 l'

l Visual Flaw Length

(

l'

.l UT Flaw Length

{

l I

L Page 4 of 6 PAC,E AF oF Al

A rmc#1a4T A

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GEInspection Services Ouad Cities 01R151998 Core Sprav UT/IVVI Results Core Spray 260* Lower Sparger Inlet Elbow to Thermal Sleeve Collar Weld Number DP4d:

1996 Results: The flaw UT length starts from i 10* and extends to 180* on the elbow side HAZ. The flaw length of 4.6" is longer than the visual length of 2.5" - 3.5". The 1" long visual length in the clockwise direction from the seam weld was not observed by the UT examination due to the search unit lift off at the seam weld crown. No flaws were observed clockwise from the 1" location to the 100 position during the UT exanunation. The upperbound lengths of UT and visual resuhs were selected for use in perfornung the flaw evaluations.

1998 Results: The "non-qualified" UT examination of this location, Figure 3, confirmed the presence of the previously identified 1996 indication. The indication was identified by UT, Indication 4 extends from 120* to 170*. The UT examination was able to identify both ends of the flaws but, due to transducer liftoff from the outside radius longseam, could not gain any indication information near the 180* longseam. Altho igh this examination is a "Non-Qualified" examination, due to the configuration, the technique proved to be able to detect flaws in this specific area of the elbow, even with the geometric interference. The Enhanced Visual E i-tion (EVT-1) confirmed the approximate position and lengths including the %"

area clockwise direction of the seam weld not identified by UT due to the transducer liftoff fmm the 180* outside radius longscam. The See the attached IVVI INR # QlR15-98-1 for photographs of the Visual indications.

t Page 5 of 6 pA s e~

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Qbc_ -02po - M-o 7(,8 U

GEInspection Services Ouad Cities 01R151998 Core Sprav UT/IVVI Results O' or TDC

.I iWl Wr l

l l

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'4. 6" R

3. o_,.

-l. a....

260 Elbow to Shroud Ptpe t

DP4D 1996 0' or TDC A

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9 3.0 260 Elbow to Shroud Pxpr DP4D 1998 Vsrual flow Length l

1 UT Flaw Length i

Page 6 of 6

(

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OV T

C:lculiti::n Titta Prgn CALCULATION TITLE PAGE Calculation No: ODC-0200-M-0769 DESCRIPTION CODE: M07 DISCIPLINE CODE:

M SYSTEM CODE:

0200 (RXL 1400 (CS)

TutE:

Ouad Cities Unit 1 Core Sprav Leakage Evaluation XX Safety Reir.ted Augmented Quality Non-Safety Related REFERENCE NUMBERS Type Number Type Number 2

Rot NP-3596-SR

'i i

4 L

COMPONENT EPN:

DOCUMENT NUMBERS:

EPN Compt Type Doc Type / Subtype Document Number 1-0200 V35 CALC /ENG OC-NPD-0038 CALC /ENG ODC-0200-M-0768 CORR /NDIT SO40-OH-0572 REMARKS:

REV.

REVISING APPROVED DATE ORGANIZATION PRINT /SIGyy O

Es. 4s d.-w. V'a dek A /d/d

1. /n/St u

u s

s a

C:ntrolled Electronic Form Page 1 of 2 File: 12-02c. doc See NEP Table of Contents NEP-12-020 issued: 6/08/98

R:vi:l:n Summaries 1

CALCULATION NO. QDC-0200-M-0769 PAGE NO.: 2 REVISION SUMMARIES REV: 0 f

REVISION

SUMMARY

InitialIssue Electronic Calculation Data Files:

(Program Name, Version, File name ext / size /date/ hour /: min)

Prepared by:

e2/M

/ -O-- 78 f

Reviewed by:6 e // /3r Na

• r rJbt2v/

_ l 7 9A

'Pnnt/ Sign Da'e t

l Type of Review pQ Detailed

[ ] Alternate

[ ] Test

{

Supplemental Review Required

[ ] Yes (NEP-12-05 documentation attached)

[ ] No Supenisor

/

l DO ANYASSUMr110NSIN THIS CALLLILA110N REQUIREIATERVERIFICA110N [ ] YES [X]NO 1

Tracked by:

REV:

REVISION

SUMMARY

Electronic Calculation Data Files:

(Program Name, Version, File name ext / size /date/ hour /: min)

Prepared by:

Print / Sign Date Reviewed by:

Print / Sign Date Type ofReview

[ ] Detailed

[ ] Alternate

[ ] Test Supplemental Review Required

[ ] Yes (NEP-12-05 documentation attached)

[ ] No Supervisor

/

DO ANY ASSUMr110NS INTHIS CALWIATION REQUIRE LATERVERIFICA110N [ ] YES [ ] NO Tracked by:

Centrolled Electronic Form Page 2 of 2 I

Soe NEP Table of Contents File: 12-02c. doc NEP "2-02C issued: 6/08/98

Cciculatien Tcbla Of Cont:nts CALCULATION NO. ODC-0200-M-0769 REV. NO. O PAGE NO. 3 SECTION PAGE NO.

SUB-PAGE NO.

TITLE PAGE 1

REVISION

SUMMARY

2 TABLE OF CONTENTS 3

PURPOSE / OBJECTIVE 4

METHODOLOGY AND ACCEPTANCE 4

CRITERIA ASSUMPTIONS 4

1 5

DESIGN INPUT I

REFERENCES 7

CALCULATIONS

{

SUMMARY

AND CONCLUSIONS

'4-ATTACHMENTS Attachment A 3 Total F

Attachment B 3 Total L

Attachment C 3 Total i

FL Controlled Electronic Form Page 1 of 1 File: 12-02d. doc See NEP Table of Contents NEP.12-02D issued: 9/23/97

4 4

J 11 j

- COMMONWEALTH EDISON COMPANY j

CALCOIATION NO. QDC-0200-M 0700 l PROJECT NO.

l PAGE NO. 4 1

i ftEVittON NO. 0 l

l l

l-i 1

1.0 PURPOSE Ale OBJECTWE I

j The purpose of this leekoge flow evaluation is to determine the rate of water lealdng from the elbow flows at the P4d wolds in the core spray loops A and B (at the 2tKk,1106 and I

j 200= operger downcomers) during core spray injection. The cors aprey system leekoge is calculated for elbow flow lengths at the end of the evoluston penod and at the end of prodcted Me.

2.0 METHODOLOGY & ACCEPTANCE CRITERIA As allowed for in BWRVIP-18, the elbow flew leek rate is calculated using the PICEP program developed by EPRI for Leek-Before 8 reek appbcatens, Reference 5.1.

This program uses elenec piente fracture mechanics to calculate the crack operung eres of a through well drcumferental flow. It *h the look rete based on 1

Henry s homogeneous nonequabnum critcal flow model, Reference 5.2. This ovoluellon is based on the combined tonelle membrane and bending stresses at the elbow during the core spray injeeson mode. Leskoge rate is ceiculated for several

}

crack eiess and at two bounding pressures for further essessment of different flew

. stres. No acceptance ceterin is required for this calculaton.

J

/

?

y 3.0 ASSUMPTION 1

i j

4 The evallahia motorial Ramberg-Oegood constants for stremostrain curve of a ty scal TP 304 l

material at 70 f and at 550 f from Reim 5.3 was used to obtain strees4 train curve at j.

195 f. The eveNeblo dets is the typical value ois.u-e ~ 04 material test speconen Therefore, it is ensumed that the date is acceptable for this evolueton i

't

l I

COMMONWEALTH EDRON COMPANY CALCULATION NO. QDC-020M-0700 l PROJECT NO.

l PAGE NO. 5

[

REVISION NO. 0 l

l l

l

~.0 DESIGN INPUT 4

4.1 APPLIED LOAD The leakage calculabons for all three P4d weld flaws (at the 200a,110o and 260= sporger downcomers) are conservatwely beood on the largest initial and end of cycle flew on the P4d wold at the 200* eperger downcomer. in additon the foliorig conservatwo assumptons have been apphed.

DOperahng Loads are Erweloped for all Three Flowed Elbows.

DMedmum Bendmg Moments and Mrumum Axial Teneen Used to Meomme COD DCv,T,,,-in Axial Forces were Conservatwely ignored DBending Moments Which Close the Crack Were Also Not included

[

The leakage calculation is bened on the loodmg conditons of the core spray popmg which occur during the core aprey injec6on mode (pressure, weight and theimal loads). The injechon water temperature after the inidoHon of the core spra*: flow is 120aF as defined in Reference 5.4 for the piping thermal modes. At the initebon of core sprey when the reactor vessel is et 90 peig, the maximum dWorontial pressure of the core oprey piping is 47 paid. This is the pressure at

=i-

. M;the same time that the core reaches its peak cladding temperature, PCT. As the reactor vessel pressure continues to reduce to the drywell pressure (~ 0 poig), the maximum differentiel line pressure would reach 64 pold at the core sprey pump runout flow rate of 5350 ppm. This maximum differenliel pressure does not occur until significanty after the PCT has been reached The leakege flow rate through the elbow d cumferential fisw was calculated for both the 47 paid and 84 paid differential pressure.

Dunne the core spray injection mode, the elbow fisw is subjected to a differential thermal sapension load which is conserva#wely bened on the core shroud and reactor vessel being at the normal operahng temperature while the core spray piping is cooled by the flow of 120f water, as described in Reference 5.4. This thermal loedmg is appled to the pipeg analyucal model which does not includes the flexibluty due to the flow (PIPSYS RUNID UPPERNEW,

(

Reference 5.5). Therefore, the apphed membrane and bending stresses are conservelwe for

- the crack eies aseodated with the end of Rio evolustion Piping dead weight. including water, Reference 5.5,is eleo considered in the following combined load on the elbow crecit

(

Axialtonelle force:

F A := 117 lb Bendmg moment-M B := (115 + 956)2 (5 + 996)2 12 in lb

('

~

M B = 17591.53342=in lb

(

L I

CORAMONWEALTH ED180N COMPANY CALCULATION NO. QDC 020044-0769 l PROJECT NO.

l PAGE NO. 6 ftEVISION NO. 0 l

l l

l.

4.2 MATERIAL PROPERTES Leekage rate calculation using PICEP computer program requires the matenal Ramberg-Oegood constants. The Ramborg-Oegood paramotors for a typical TP304 bene metal strose strain curve at temperature 550f and 709 given in Reference 5.3, the piping system toets database developed try Batolle, are used in this evaluehon. Data at 195f is not available. However, from the values of yield strees vs temperature given in the Appendk i of the ASME B&PV, Secton ill, a linear factor, d con be obtained for calculating stressetran data at 195 f from the data curve at temperature of 5509 and 709 as the follow.

195 "' 550 + d-(o 70- 85501 8

where-o 550 :Ylekistroes at 550 f a yo

Yleid strees at70 f a 95 :Yiekistrees at195 f For the purpose of caelulating the above linear factor d, these yield stresses at temperature can be obtained from Appendk I of the A84E B&PV, Section ill for TP 304 matenal.

Curve fliting of the generated data using the following Ramborg Oegood streso etrain i:' ~- 4 to obtain parameters a and n for leakage calculations

. '._ := ' + a -

E o

{o f O

O O

where e, and o,are the referenced y6 eld strain and strees i--;+ff;.

i

P h

[

{

COMMONWEALTH EDISON COMPANY CALCULATION NO. QDC-0200-M-0769 l PROJECT NO.

l PAGE NO. 7 REVIslON NO. 0 l

l l

l 5.0 REFERENCE-5.1

• PICEP: Pipe Crack Evaluston Program (Revision 1)," EPRI NP-3596-SR, Rowision 1, December 1987 5.2 "The Two-Phase Critical Ducharge ofinitially Saturated or Subcooled Liquid,"

Nuclear Science and Enaneering. 41,1970

'r 5.3

" Pipe Fracture Database," from Douglas A. Scarth, Task Group Chairman, ASIE

[

Secten XI Task Group on Pipe Flaw Evaluation, October 21,1992 5.4 Calculation Number QC-NPD-0038," Quad Clbes Core Spray Flaw Evalumbon". Rev.1.

5.5 NDIT SO40-QH-0572, Loads on RPV Intemals Core Spray Pipmg - Quad Caios Unit 1.

5.6 ASME B&PV, Secten lil, Appenda 1,1977 Edibon

[

L

(-

{-

COMMONWEALTH EDISON COMPANY CALCULATION NO. QDC-0200 M-0769 l PROJECT NO.

l PAGE NO. 8 REVISION NO 0 l

l l

l

~.0 CALCULATION 8

6.1 MATERIAL PROPERW Stremo strain curve for TP304 material at 70nf_(Reference 5.3) i Ultimate strees a 7 : 913 k83 u

Referenced yield strain e 7 :=0.00138 o

Referenced yield strees o 7 :=35.8 ksi o

Ramberg-Osgood Parameters:

a 7 := 2.556 n 7 :=5.5 Ramberg-Osgood stress strain equation c 7(o):=c 7-a7

+

o (807) i'o7),

1 Stress strain curve for TP304 material at SW(Reference 5.3) i Ultunate strees o 5 :=66.8 kol u

Referenced yield strain

o5 := 0.0009 Referenced yield strees o $ :=23.1 kal o

Ramberg-Osgood Parameters:

a5: 9533 1

Ram - - e,..n

<o r,, o,

c5(8) *8o5' ' 5':

l' 05/

+ { ' 05 i

/,

{

{

COMMONWEALTH EDe8ON COMPANY CALCULATION NO. QDC 020044-0789 l PROJECT NO.

l PAGE NO. 9 -

[

ftEVISION NO. 0 l

l l

l

~

[

O__ 24, curve for TP304 n^- -i : at 10.'C interpolaton factor f obtained from the Codo yield strees value vs. temperature:

(

o 550 :=(16.3 + 15.5). 5

Yield strees (ksi) at 550 f, interpoisted from Reference 5.6

{'

o 70 :=25

-Yield strees (kal) at 100 f from Reference 5.6 8195 :=21.3

- Yield strees at 200 f, interpoisted from Reference 5.6 550 + d-(o 70- 8550 0 195 #8 95 -

50 d :=

d = 0.59341 8 70 - ' 550 Interpoleton funcuon for data et 195 f lin(a,b) :=((b) + d (a-b))

Generated date

' u :=b(o S'8 u7) u o = 76.76154 kai o

o := h(c 5 07) o c

8 o=

6374 W

o =lin(s 5'807) 0 8o"I I

s

{

op(o):=lin(s 5(8)'87('))

E := o Elseec M h E = 25807.74634 kai 8 o c oto u

• f*

2 8 f = $2.51264 kal

(

l

~

t I

g i

(

(-

CORIR40NWEALTH EDtSON COMPANY

(

CALCULATION NO. QDC 020040760 l PROJECT NO.

l PAGE NO.10

[

REVISION NO. 0 -

l

.l l

l fitting for the generated data ep(o) at 1959 a := 1. 80 The values of a and n are obtained by a trial and error method such that the fitted curve matches the above

(

generstod data pomes as shown in the following fl ure.

0 u :=7.95 a :=3.7 c(o):=c - o !1 + f1.

o

\\* ol

\\,0o),

{

a y-;........-

/_g-

[

/

~

f...... -

(

sY g'

[~

J*

i 20 0

[,

0.1 0.2 c.3 o.4 o.5 06 saem Stress Strain at 70 deg F r

---

Stress Strain at $50 des F

(-

+++ Generated data for 195 deg F Fitted Cave for 195 degree F

(-

FIGURE 1 INTERPOLATION AND CURVE FITTING OF STRESS-STRAIN DATA b

L p

COMMONWEALTH EDISON COMPANY CALCULATION NO. QDC-020044-0769 l PROJECT NO.

l PAGE NO.11 REVISION NO. 0 l

l l

l 6.2 FLUID DATA 62.1 For 47 caid case:

Subcool water at 120 f at 151.7 pois. The ambient pressure is 104.7 pela 622 For64 omd case:

I Subcool water at 120 f at 78.7 poia. The ambient pressure is 14.7 psia.

I 6.3 PICEP ANALYSES 6.3.1 Comouter Proaram Verh"~1 Run i

Exemple 1 anahois given in Picep manuel (Reference 5.1) was rerun to verifled that the program was propeth inetmiled. The verificaten analysis output which matches the output for Example Problem 1 of Reference 5.1 is included in i

Attachment A. The crack lengths at the end of evaluation period and at the end of life are proudedin Reference 5.4 6.32 8 -' R=*= atwivais for 47 caid The anahois output for the case of 47 paid is included in Attachment 8. The leak I

rate as a functon of crack length is plotted in Figure 2. The leak rates at the end of a 48 month period and at the end of life are shown in this figure.

6.3.3 Laak Rate analveis for 64 neid The anahus output for the case of 64 paid is included in Attachment C. Tt.e leak rate as a function of crack length is plotted in Figure 3. The leak rates at the end of a 48 month period and at the end of life are shown in this figure, F

L

-- - ~ -

[

COMMONWEALTH EDISON COMPANY CALCULATION NO. QDC-020044-0700 l PftOJECT NO.

l PAGE NO.12

{

N NO. 0 l

l l

l 3

1810 f

s'

/

10

~

{'

\\

l

.r'

/

/I I

b 7'

,i

/

1 0.1 I

i r

Y 0.01

/

/

i

/

-3

. I.,0 0

1 2

3 4

5 6

7 8

9 10 11 12 13 CRACK SIZE On)

Leak Rate Curve Den End of48 Month Period (I amirage:2gpm)

-+ - End of48 Mondi Fisw Length: 7.16' FIGURE 2 LEAKAGE RATE AT DIFFERENTIAL PRESSURE OF 47 psid f

L I

COMMONWEALTH EDISON COMPANY CALCULATION NO. QDC-0200-M-0789 l PROJECT NO.

l PAGE NO.13 REvislONNO. 0 l

l l

l 3

l*80 2

l

[

/

100 s'

i

/

10 J

[

l 1

,t v

b d

/

0.1 I

/

\\

I/

I I

i 0 01 l

I

/

f

~

l g

I

/

i

..,0 >

0 1

2 3 4 5 6 7 8 9 10 11 12 13 14 CRACK SIZE (in)

I Leak Rate Curve uma End of 48 Month Perio/ (Leakage: 2.5 gpm)

-+ End of 48 Month Lengf a: 7.16" l

FIGURE 3 LEAKAGE RATE AT DIFFERENTIAL PRESSURE OF 64 psid l-

l l

COMMONWEALTH EDISON COMPANY

. CALCULATION NO. QDC-0200 M 0700 l PROJECT NO.

l PAGE NO.14

[

REVISION NO. 0 l

l l

l 7.0 SUIARRARY & CONCLUSION The leakage is calculated bened on the previously described loads, meterial proporties and

{

fluid properties. The leek rate curves are presented in Pieures 2 and 3 for en injection differential pressure of 47 paid and 64 paid, ie+rl;fi. At the end of evaluation period,i.e.

48 months with a crack length of 7.16 inches the leek rate is 2 gpm for 47 paid differental pressure and is 2.5 gpm for 64 paid differential pressure, it con be seen that the leakage rate et the end of evolustion period is insignificent when compared to the injecilon flow rate of 4600 gpm. These leek retos are less then or aquel to 2% of the injection flow rate.

I l-l-

9

Attachment A QCD-0200-M-0769

[

RESEARCH PROGRAMS

(

THE SUBJECT COMPUTER PROGRAM HAS BEEN CLASSIFIED BY EPRI AS A RESEARCH PROGRAM. AS SUCH, IT HAS NOT BEEN DEVELOPED AND TESTED TO THE EXTENT THAT A PRODUCTION PROGRAM WOULD BE, AND UNFORSEEN

[

RESULTS MAY OCCUR WHEN RUNNING THE PROGRAM.

EPRI DOES NOT MAKE ANY WARRANTY OR REPRESENTATION WHATSOEVER, EXPRESS OR IMPLIED, INCLUDING 'ANY WARRANTY OF MERCHANTABILITY OR FITNESS OF ANY PURPOSE WITH RESPECT TO THE PROGRAM; NOR DOES EPRI ASSUME ANY

(

LIABILITY WHATSOEVER WITH RESPECT TO ANY USE OF THE PROGRAM OR ANY PORTION THEREOF OR WITH RESPECT TO ANY DAMAGES WHICH MAY RESULT FROM SUCH USE.

PICEP VERSION 06/30/87 PIPE CRACK EVALUATION PROGRAM EPRI REPORT NP-3569-SR REV.1 BY D.M. NORRIS AND V.K. CHEXAL UNITS: BRITISH, LENGTH-INCHES, MASS-LBM, TEMP-DEGF NEW-STYLE PICEP INPUT AS PER EPRI REPORT NP-3569-REV.1 ECHO PRINT OF INPUT DATA PROB 1 4-IN PIPE.BWR. AXIAL IGSCC SUBCOOLED TYPE 304 MODE IPLAS ISOL 0

2 1

DO THICK 4.5000

.3370

[

IFDIR-IFAREA NDIV COD AF l'

1 10

.0000E+00

.4000E+01 YOUNG SO EO ALPHA FACN FSR Z

SF

.280D+08

.380D+05

.000D+00

.452D+01

.329D+01

.480D+05

.000D+00

.000D+00 IN

' PRES -

TO PB TRACT BMOM PMSTR PBSTR 3 1156.7 528.00 14.7 0.

O.

O.

EK AR N90 N45 CD FFRED.

.20000D-03 1.000 0

8

.000

.0000 END OF ECHO PRINT f-t Page Al OfA3

Attachm:nt A I

QCD-0200-M-0769 I

PIPE DATA l

PIPE OUTSIDE DIAMETER

.4500D+01

=

PIPE THICKNESS 1

.3370D+00

=

CRACK DATA I

CRACK SHAPE

= ELLIPTICAL CRACK ORIENTATION

= LONGITUDINAL CRACK SURFACE ROUGHNESS I

.2000D-03

=

HALF CRACK LENGTH INCREMENT

.2000D+00

=

NUMBER OF INCREMENTS 10

=

NUMBER OF 45 DEG TURNS 8

=

I NUMBER OF 90 DEG TURNS 0

=

EXIT TO INLET AREA RATIO 1.00

=

I

- " ^ =

YOUNG'S MODULUS

.280D+08

=

I YIELD STRESS

.380D+05

=

RAMBERG-OSGOOD EXPONENT

.329D+01

=

RAMBERG-OSGOOD CONSTANT

.452D+01

=

FLOW STRESS

.480D+05 i

=

YIELD STRAIN

.136D-02

=

REFERENCE STRESS

.380D+05

=

REFERENCE STRAIN

.136D-02

=

I LOAD DATA l

AXIAL (NON-PRESSURE) LOAD

.000D+00

=

TOTAL BENDING MOMENT

.000D+00

=

TOTAL AXIAL STRESS

.298D+04

=

TOTAL BENDING STRESS

.000D+00

=

FLUID DATA l

PRESSURE

.116D+04

=

TEMPERATURE

.528D+03

=

ENTRANCE LOSS COEFFICENT

.610D+00

=

FRICTION FACTOR

.376D-01

=

BACK PRESSURF

.147D+02

=

I I

Page A2 of A3 F

{

Attachment A QCD-0200-M-0769

[

OUTPUT DATA PROB 1 4-IN PIPE.BWR. AXIAL IGSCC SUBCOOLED TYPE 304 CRITICAL CRACK LENGTH (Z-1) 10.5536.

SUBCOOLING =-

34.3

['.

CRACK LENGTH COD FL/D LEAK FLOW RATE CHOKED INCHES INCHES GPM 9 200 F

[.

1

.4000

.000191 440.4

.0017 YES 2

.8000

.000419 152.7

.0129 YES 3

1.2000

.000688 76.7

.0445 YES

(

4 1.6000

.001133 43.1

.1287 YES 5

2.0000

.001966 25.7

.3546 YES 6

2.4000

.003269 17.5

.8372 YES

[

7 2.8000

.004979 13.4 1.6598 YES L

8 3.2000

.007142 11.1 2.9389 YES 9

'3.6000'

.009801 9.5 4.8066 YES 10 4.0000

.013001 8.5 7.4114 YES

[

[

[

[

[

[

[

[

fu Page A3 of A3 r

q

(

Attachment B ~

)

QDC-0200-M-0769 RESEARCH PROGRAMS

{

THE SUBJECT COMPUTER. PROGRAM HAS BEEN CLASSIFIED BY EPRI AS A RESEARCH PROGRAM. AS.SUCH, IT HAS NOT BEEN DEVELOPED AND TESTED TO THE EXTENT THAT A PRODUCTION PROGRAM WOULD BE, AND UNFORSEEN RESULTS MAY OCCUR WHEN RUNNING THE PROGRAM.

EPRI DOES NOT MAKE f

ANY WARRANTY OR REPRESENTATION. WHATSOEVER, EXPRESS OR IMPLIED, INCLUDING ANY WARRANTY OF MERCHANTABILITY OR FITNESS OF ANY PURPOSE WITH RESPECT TO THE ~ PROGRAMS NCR DOES EPRI ASSUME ANY LIALILITY WHATSOEVER WITH RESPECT TO AN) USE OF THE PROGRAM OR ANY PORTION THEREOF OR WITH RESPECT TO ANY DAMAGES WHICH MAY RESULT FROM SUCH USE.

PICEP VERSION 06/30/87 PIPE CRACK EVALUATION fROGRAM EPRI REPORT NP-3569-SR REV.1 BY D.M. NORRIS AND V.K. CHEXAL

[

UNITS: BRITISH, LENGTH-INCHES, MASS-LBM, TEMP-DEGF t

NEW-STYLE PICEP INPUT AS PER EPRI REPORT NP-3569-REV.1 ECHO PRINT.OF INPUT DATA

{

QUAD-1 Core Spray Elbow Leakage 9 DP=47 psi MODE IPLAS ISOL 0

2 2

{

DO THICK 6.6250

.2800 IFDIR IFAREA NDIV COD AF 0

1~

20

.0000E+00

.1400E+02 YOUNG SO EO ALPHA FACN FSR Z

SF

.258D+08

.283D+05

.000D+00

.795D+01

.370D+01

.525D+05

.000D+00

.000D+00 f

IN PRES TO PB TRACT BMOM PMSTR PBSTR 3

151.7 120.00 104.7 117.

17592.

O.

O.

EK AR N90 N45 CD FFRED

.20000D-03

'1.0.00 0

6

.610

.0000 k

END OF ECHO PRINT -

i

(

L Page B1 OfB3 l-i

Attachmsnt B QDC-0200-M-0769 CRITICAL CRACK LENGTH (NO CORRECTION FACTORS) 13.96 PIPE DATA t

PIPE OUTSIDE DIAMETER

.6625D+01

=

PIPE THICKNESS

.2800D+00

=

CRACK DATA CRACK SHAPE

= ELLIPTICAL

. CRACK ORIENTATION -

= CIRCUMFERENTIAL CRACK SURFACE ROUGHNESS

.2000D-03

=

HALF CRACK LENGTH INCREMENT

.3500D+00

=

{

NUMBER OF INCREMENTS 20

=

NUMBER OF 45 DEG TURNS

'6

=

NUMBER OF 90 DEG TURNS 0

=

EXIT TO INL5s AREA RATIO 1.00

=

MATERIAL DATA YOUNG'S MODULUS

.258D+08

=

YIELD STRESS

.283D+05

=

. R4MBERG-OSGOOD EXPONENT

.370D+01

-=

,f U.MBERG-OSGOOD CONSTANT

=

.795D+01 FLOW STRESS

.525D+05

=

. YIELD STRAIN

.110D-02

=

REFERENCE STRESS

.283D+05

=

REFERENCE STRAIN

.110D-02

=

' LOAD DATA AXIAL (NON-PRESSURE) LOAD

.117D+03

=

TOTAL BENDING MOMENT

.176D+05

=

TOTAL AXIAL STRESS

.264D+03

=

TOTAL BENDING. STRESS

.198D+04

=

l'

. FLUID DATA PRESSURE

.152D+03

=

TEMPERATURE

.120D+03

=

h~

ENTRANCE LOSS COEFFICENT

.610D+00

=

FRICTION-FACTOR

.163D-01

=

BACK PRESSURE

.105D+03

=

[

p L

Page B2 ofB3

l Attachment B i

QDC-0200-M-0769 l

OUTPUT DATA QUAD-1 Core Spray Elbow Leakage a DP=47 psi

' CRITICAL CRACK LENGTH (Z=1) 13.9590 SUBCOOLING =

239.6 CRACK LENGTH COD FL/D.

LEAK FLOW RATE CHOKED INCHES INCHES GPM 0 200 F 2

.1.4000

.000274 247.5

.0051 NO 3

2.1000

.000461 106.7

.0195 NO 4

2.8000

.000696 60.3

.0515 NO 5

3.5000

.000999 39.0

.1131 NO 6

4.2000

.001392.

27.5

.2213 NO 7

4.9000

.001904 20.5

.4006 NO 8

5.6000

.002570 16.0

.6846 NO 9

6.3000

.003433 13.0 1.1185 NO 10 7.0000

.004544 10.8 1.7631 NO 11 7.7000

.005971 9.3 2.7002 NO 12 8.4000

.007807 8.1 4.0441 NO 13 9.1000

.010187 7.1 5.9643 NO 14 9.8000

.013349 6.3 8.7401 NO 15 10.5000

.017753 5.6 12.8975 NO 16 11.2000

.024431 5.0 19.5934 NO 17 11.9000

.035977 4.4 31.7843 NO 18-12.6000

.059632 3.8 58.0600 NO 19 13.3000

.117942 3.2 126.7193 NO 20 14.0000

.289952 2.5 343.5021 NO 1

l L

L i

I L

Page B3 ofB3

QDC-0200-M-0768 RESEARCH PROGRAMS THE SUBJECT COMPUTER PROGRAM HAS BEEN CLASSIFIED BY EPRI AS A RESEARCH PROGRAM. AS SUCH, IT HAS NOT'BEEN DEVELOPED AND TESTED I

TO THE EXTENT THAT A PRODUCTION PROGRAM WOULD BE, AND UNFORSEEN RESULTS MAY OCCUR WHEN RUNNING THE PROGRAM.

EPRI DOES NOT MAKE ANY WARRANTY OR REPRESENTATION WHATSOEVER, EXPRESS OR IMPLIED, I

INCLUDING ANY WARRANTY OF ' MERCHANTABILITY OR FITNESS OF ANY PURPOSE WITH RESPECT TO THE PROGRAM; NOR DOES EPRI ASSUME ANY LIABILITY WHATSOEVER WITH RESPECT TO ANY USE OF THE PROGRAM OR ANY PORTION THEREOF OR WITH RESPECT TO ANY DAMAGES WHICH MAY RESULT FROM SUCH USE.

PICEP VERSION 06/30/87 PIPE CRACK EVALUATION PROGRAM EPRI REPORT NP-3569-SR REV.1 BY D.M. NORRIS AND V.K. CHEXAL UNITS: BRITISH, LENGTH-INCHES, MASS-LBM, TEMP-DEGF NEW-STYLE PICEP INPUT AS PER EPRI REPORT NP-3569-REV.1 ECHO PRINT OF INPUT DATA QUAD-1 Core Spray Elbow Leakage 0 DP=64 psi MODE IPLAS ISOL 0

2 2

DO THICK 6.6250

.2800 IFDIR IFAREA NDIV COD AF 0

1 20

.0000E+00

.1400E+02 YOUNG SO EO ALPHA FACN FSR Z

SF

.258D+08

.283D+05

.000D+00

.795D+03

.370D+01

.525D+05

.000D+00

.000D+00

[

IN PRES TO PB TRACT BMOM PMSTR PBSTR 3

78.7 120.00 14.7 117.

17592.

O.

{

0.

EK AR N90 N45 CD FFRED

.20000D-03 1.000 0

6

.610

.0000

[

END OF ECHO PRINT i

F Page Cl Of C3

' ~

- QDC-0200-M-0768

---

-----------------.80 CRITICAL CRACK LENGTH (NO CORRECTION. FACTORS) 13 PIPE DATA PIPC OUTSIDE DIAMF.TER

' =

.6625D+01 PIPE THICKNESS

'=

.2800D+00 h

. CRACK DATA'

[.

CRACK SHAPE

= ELLIPTICAL 1

CRACK ORIENTATION

= CIRCUMFERENTIAL CRACK SURFACE ROUGHNESS

.2000D-03

=

~ HALF CRACK LENGTH < INCREMENT

.3500D+00

=

h NUMBER OF INCREMENTS 20

=

NUMBER OF 45 DEG TURNS 6

-=

NUMBER OF 90 DEG TURNS 0

=

-EXIT TO INLET AREA RATIO 1.00

=

MATERIAL DATA

[-

YOUNG'S MODULUS

.258D+08

=

YIELD STRESS

.283D+05

=

RAMBERG-OSGOOD EXPONENT

.370D+01 f-

=

RAMBERG-OSGOOD CONSTANT

' =

.795D+01 FLON STRESS

.525D+05

=

YIELD STRAIN'

.110D-02

=

REFERENCE STRESS

.283D+05

=

REFERENCE STRAIN

.110D-02

=

f LOAD DATA.

-AXIAL (NON-PRESSURE) LOAD

=

.117D+03 j:

' TOTAL BENDING MOMENT

.=

.175D+05 l

TOTAL AXIAL STRESS

=

.352D+03

' TOTAL BENDING STRESS

.198D+04

=

FLUID DATA PRESSURE.

.787D+02

=

TEMPERATURE.

.120D+03

=

ENTRANCE LOSS COEFFICENT

.610D+00

=

-FRICTION FACTOR ~

.150D-01

=

BACK PRESSURE =

.147D+02

'=

G f

Page C2 OfC3 -

b Attachment C QDC-0200-M-0768 OUTPUT DATA QUAD-1 Core Spray Elbow Leakage 6 DP=64 psi

[

CRITICAL CRACK LENGTH (Z=1) 13.8004 SUBCOOLING =

191.2 CRACK LENGTH COD FL/D LEAK FLOW RATE.

CHOKED INCHES INCHES GPM 9 200 F 1

000

.000128 510.6

.0010 NO 2

1.4000

.0002r5 231.1

.0064 NO 3

2.1000

.0004 S 100.7

.0243 NO

{

4 2.8000

.0007 i 57.3

.0641 NO 5

3.5000

.0010 +

37.3

.1401 NO 6

4.2000

.0014'.

26.4

.2737 NO 7

4.9000

.00198b 19.8

.4949 No f

8.

5.6000

.002683 15.5

.8451 NO 9

6.3000

.003589 12.6 1.3807 NO 10 7.0000

.004761 10.5 2.1780 NO

[

11 7.7000

.006273 9.0 3.3412 NO 1

12 8.4000

.008230 7.8 5.0191 NO 13 9.1000

.010799 6.9 7.4408 NO 14 9.8000

.014277

- 6.1 11.0023 NO f

15 10.5000

.019279 5.5 16.4952-NO 16 11.2000

.027236 4.8 25.7617 NO 17 11.9000

.041905 4.2 43.7557 NO 18 12.6000

.074245 3.6 85.6513 NO

(.'

19

-13.3000

.160046 2.9 204.1029 NO 20~

14.0000

.431640 2.3 606.9734 NO 8

[L

{

(

(

[-

i f

L Page C3 ofC3 E

i

[- '

GeneralElectrse Company 175 CurtnerAvenue San Jose. C4 95125 GENE-B13-02008-L1 December 22,1998

[

['

Keith Moser, Comed cc: DS Braden, GE To:

G Vanderheyden, Comed G DeBoo, Comed

[

From:

TA Caine, GE TA

[

Subject:

Quad Cities 1 Jet Pump 7/8 Riser Crack Growth Evaluation Below is the crack growth evaluation to support continued operation of Quad Cities I with cracking at the riser brace yoke injet pump 7/8. Supporting calculations and evidence of verification are in DRF B 13-02008. Please call me at (408) 925-4047 if you

[

have questions or need additional information regarding this evaluation.

{.

Backaround:

During laWion of the jet pump risers in Quad Cities Unit 1, November 1998, two crack

[

indications were found in the jet pump (JP) 7/8 riser pipe, starting at the weld connection of the riser brace yoke to the pipe and growing diagonally away from the weld and into the pipe. A sketch of the indications, viewed from the shroud side of the annulus, is in

[

Figure 1. Note that there were no indications found along the horizontal fillet welds above and below the yoke.

(

In a separate letter [1], GE provided a qualitative assessment of the safety consequences of worst case cracking scenarios for these indications, concluding that there is not a significant safety concern W-of the numerous low probability events that would have

[

to occur together. Based on this assessment, the plant returned to operation in early December. It is Comed's intent to take a mid-cycle shutdown to install a clamp on JP 7/8. Timing of the shutdown and the associated preparations depend upon an estimate of the growth of the indications, hereafter called cracks, during present operation.

Obiectives:

GE has developed, at Comed's request, an analytical tool with which crack growth at the r.

riser brace yoke location can be estimated. Based on predictions using that tool and the t-associated inputs, a criterion for continued operation with acceptable crack growth is provided.

f _

i I

GENE-B13-02008-L1 I

The following inputs were provided by or confirmed by Comed:

Crack details (length, location, etc), provided by GE Inspection Services, as described above were confirmed by Comed for [1]. In addition, Comed confirmed that the

[

cracks are propagating at 45' relative to the riser brace yoke.

The plant is, and will continue to be, operating with recirculation drive flow at 95% of the original design rated value.

{-

The delta-K fatigue crack growth threshold property is 5 k,i-Vin. This value has been used in prior evaluations and is appropriate based on technical references [2,3].

f Assumotions:

The following assumptions were made in performing the evaluation:

The cracks are assumed to be through-wall. This is likely considering the riser's relatively thin wall (0.365 inches) and is consistent with inspection conclusions for the very similar cracks found in JP 5/6 in 1994.

[

The cracks found around the riser to yoke weld connection initiated due tr. onst IGSCC or fatigue and have grown into the riser pipe, away from the welds, due to flow induced vibration stresses in the riser pipe, with the possibility of continued f_

IGSCC contributing to the growth.

The cracks can be modeled as a straight crack in a pipe, taking into consideration

[

1) stresses normal to the direction of cracking, and 2) pipe curvature correction factors.

The profile of stress magnitudes and frequencies derived from BWR/4 data [4] is a reasonable approximation of the relative stress / frequency characteristics of the FIV in Quad Cities 1, to be used with the maximum FIV stress magnitudes calculated specific to Quad Cities 1.

.* The representative ECP for this riser location for the upcoming cycle, based on hydrogen water chemistry (HWC) performance similar to last cycle, is -50 mV, SHE, I

based on the crack environment being controlled by the higher p'ressure water inside the riser. However, as a conservatism. a growth rate of 1.2x10' in/hr, corresponding to good normal water chemistry (NWC) [5] is assumed.

(,

I f

L 2-

---

%-_--_--._-__--.m.

b GENE-B13-02008-L1 Methods:

[.

Mow Induced Vibration (FTV) Stresses In order to r=Imlate the FIV stresses in the riser near the yoke connection, a detailed model of that region was developed so that modal shape factors (MSFs) could be -

[

determined from the riser brace, where test data were taken, to the riser pipe locations of interest. 'Ihe detailed model was a NASTRAN [6] finite element model. Three dimensional modeling was used for the riser brace and attached riser pipe about 6 inches

{.

above and below the riser brace and yoke connection. The remainder of the jet pump model consisted of beam elements and pipe bend elements.

[

The process of determining the FIV stresses in the riser pipe was the same as that used to determine FIV stresses in the RS-1 riser elbow-to-thermal sleeve weld [7]:

[

1. Review the startup vibration data to determine the primary modes ofinterest for the jet Pump.

2. Using the finite element model of thejet pump, determine the analytical natural frequencies and mode shapes.

3. Adjust the finite element model such that the analytical natural frequencies and mode shapes show reasonable agreement with those from the measured strain data taken during startup testing.

4. Determine from the fmite element model the modal shape factors. The modal shape j

factors are used to analytically ratio the strains from the location where startup test data was taken to the specific riser pipe locations near the yoke connection.

h

5. Based on the measured strain data from startup and the modal shape factors from the finite element model, calculate the modal stresses in the riser pipe for each mode of interest. Absolute sum the modal stresses from each mode to arrive at the final FIV f

stresses.

[

Crack AK Model The two cracks have an unusual shape, like a flat V-shape with legs at 45* from

(

horizontal. The larger crack in Figure 1 is evaluated, as it is limiting for fatigue crack

- growth. The overall approach is to treat the crack as a straight crack equal to its total length. This crack has the stresses applied e.s they resolve normal to the crack direction, f

so for the vertical portion of the crack, the applied stress is just the hoop stress. For the angled crack, the applied stress is h

om = ca cos (0) + oh sin'(0)

(1) 2 l

, I l

lll v

GENE-B13-02008-L1

)

The linear elastic fracture mechanics (LEFM) model used for fatigue crack growth must be able to account for variation in normal stress along the crack length, as shown ac1===*ically in Figure 2. The Tada-Paris-Irwin handbook [8] has a K solution for a point load on a throughwall crack of fength 2a in an infinite plate. The solution is y

nP

-a b a p

P K at a = (P/EE)V(a+by(a-b)

K at -a = (P/EE)V (a-by(a+b)

Note that this model assumes a unit depth into the paper.

The solution to get a AK for a crack length 2a is implemented as follows:

1. Determine axial and hoop vibration stress ranges, Aer, at the crack location / trajectory based on the FIV stress inputs, using % inch increments.

2. Resolve the stresses to determine the effective stress range normal to the crack trajectory.

3. For each % inch increment, the stress is multiplied by 0.5 sq in (.5 'mch along crack times 1 inch thick model) to get the equivalent force at the midpoint of that increment, or by a smaller amount if the crack extends partially into that increment.

4. The AK,a and AK,-a for that force P is calculated.

5. This process is repeated for each increment over the length of the crack and the individual AK values are summed at a and -a.

6. The larger of the two AK values is chosen as the AK for crack, to be conservative.

A curvature correction factor is applied to the K solution above, which is for an infinite flat plate. The correction factor is based on a combination of the factors for an axial crack and a circumferential crack because the crack is angled. The amount of contribution of each factor is determined based on the magnitude of the stresses. Thus, the circumferential factor, contributes based on the magnitude of axial stresses and vice versa.

4_

H GENE-B13-02008-L1 Crack Growth Determination The fatigue crack growth methodology is similar to that which has been used at the riser elbow weld at other plants (4)..The FIV stresses calculated are maximum values. When E - C.g actual time history, many of the cycle amplitudes are sisu!&zeitly smaller than this maximum. The time history for Browns Fmy I was evaluated in detail in (4). The largest stress range has a frequency of about 0.02 Hz. As stress ranges decrease, the frequencies with which they occur increase. For example, the stress range which is about 44% of the maximum occurs at a frequency of about 3.4 Hz. Thus, most of the vibrations occurring at 20-30 Hz are at substantially lower stmas ranges.

The mean strass present in the pipe affects the AK threshold of the pipe material and the fatigue crack growth rates. h relationship of alternating and mean stresses is represented by the R ratio:

R ratio = (mean stress - alternating amplitude)/( mean stress + attemating amplitude) 4 The fatigue cracking AK threshold and the fatigue crack growth rate curve used both account for the R mtios typi::al of the stresses present in the crack. The fatigue crack growth rate curve is an air curve. For the high frequencies present, this may be reasonable. However, some environmental crack growth is included, partly for conservatism relative to the fatigue growth, but also in recognition that some IGSCC may occur at the crack tips, where the = *M K is not insignificant.

For each stress-frequency grouping (there are 12 evaluated), the AK for the current crack length is compared to the threshold of 5 ksilm. If the AK is below 5, no fatigue growth j

occurs.- Ifit is above 5, the crack growth relationship calculates the amount of fatigue

' growth for the number of cycles in the given time increment (typically 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />). The crack length is increased, a new AK is computed and the process is repeated. In this way the crack length increases vs. operating time.

Analysis:

FIV Stresses The FIV stresses at the element centerpoints of the finite element model were mapped against the crack location and trajectory. The stress values were used to interpolate axial

' and hoop stresses along the cmck. The hoop stresses are about 10x higher at the yoke than they are 5 inches away. The axial stresses do not diminish as much, showing about a 2x reduction. The axial and hoop stresses along the crack, and the stresses as they were resolved normal to the crack, are shown in Table 1.

Crack AK Model Based on the IVV1 report, the crack length is 2.75+1.5+2.9 inches, or a total of 7.15 inches. This is modeled symmetrically'as 2.85 + 1.5 + 2.85 inches, or 7.2 inches c_

\\

l GENE-B13-02008-L1 E.tatin The design pressure inside the riser pipe relative to outside is p=190 prid [9). This j

pressure causes mean stresses in the pipe of.

\\

pR/t = 190*5/.365 = 2600 psi hoop stress

]

pR/2t = 1300 psi axial stress f

These mean stresses are compared to the FIV stress ranges, which are from 700 psi to 2000 psi on the crack. The resolved mean stress is 1300*cos (45) + 2600* sin'(45) = 1950 psi 2

{

The largest R ratio would be (1950-350)/(1950+350) = 0.7 j

The smallest R ratio would be (1950-1000)/(195p1000) = 0.3 J

i l

Pine Curvature Ces 4=. Factor (Shar= Factor) j The shape factor applied to the crack considers that a comb'mation of circumferential and

[

axial effects will occur. These are ratioed based on stress magnitude.

[

The shape factor for an axial flaw applies to hoop stress and is shown in Rooke and Cartwright [10]. The shape factor for a circu;nferential flaw, also in [10), applies to axial stress. The shape factor Gm is a function of a/sqrt(Rt) and increases as a increases j

Assuming a 10" crack (a"5) a/sqrt(Rt) = 5/sqrt(5.2*.365) = 3.6 i'[

For this value, the axial Gm=3.75 and the circumferential Gm=1.8.

i The axial stresses are about 2-6 times the magnitude of the hoop stresses over the crack length. Considering a conservative ratio of 3 to 1, the overall shape factor is 0.75(1.8) + 0.25(3.75) = 2.3 l

Crack Growth Determination l

The fatigue crack growth curve used is from ASME Section XI, Appendix C Figure C-3210 a [11). The curve used is for growth in 550'F air with R ratio of 0.79.

The curve is w i d as

. da/dn = 5.0x10 '(AK)" inches / cycle 4

The fatigue crack growth AK applied is the nominal AK based on the FIV stresses multiplied by the shape factor and by the flow factor. The flow factor takes into l

consideration that the.FIV stresses are based on the most limiting startup condition, which was 100% recirculation' drive flow. FIV stresses vary according to the square of the flowrate, so a decrease in flowratq decreases the FIV stresses by the square of the flow GENE-B13-02008-L1 fraction. For example, irrecirculation drive flow is 90%, the flow factor would be (0.9)2 or0.81.

Fatigue crack growth is determined for 12 groups ofR - cycle paidngs. The groups range from the maximum R to a value about 44% of the maximum. Each R - cycle pairing contributes to fatigue crack growth if th: overall K is above the 5 ksi-Viri threshold.

IGSCC growth is added using a growth rate of 1.2x10 ' /hr, which is the value m

calail=*ad in [5] for good NWC (conductivity < 0.1 S/cm). Credit for HWC is not taken in this analysis, as a further conservatism.

calad=*imis are done in 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> inw+,-- - = summing the fatigue cracking cycles and the IGSCC growth to increase 2a for the next increment. The result is an estimate of crack length 2a as a function of operating time.

BatidtE The analysis steps were prograrnmed into a spreadsheet to facilitate calculations for various input parameters The spreadsheet was run with the FIV alternatmg stresses in Table 1 for a crack propagating at 45'. The acceptance criteria is set at a length 2a of 10 inches, or approximately 3 inches'of growth. This is a reasonably conservative criteria, given that cracking of about 15 inches occurred in JP 5/6.

Results are generated for 4 scenarios where load is adjusted to represent particular operating conditions ofrecirculation drive flow:

1. Operation with 100% drive flow - flow factor = 1.0.

2. Operation with 98% drive flow - flow factor = 0.960.

1

3. Operation with 95% drive flow - flow Iactor = 0.903.

}

_ 4. Operation with 90% drive flow - flow factor = 0.810.

i l

The results, in terms of operating hours to reach a crack length of 10 inches, are tabulated

[

- below.

i Reeire Dnve Row (% of rated)

Time to grow to 2a=10 inches i

1 100 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> i

98 2600 hours0.0301 days <br />0.722 hours <br />0.0043 weeks <br />9.893e-4 months <br /> f

j.

95 4400 hours0.0509 days <br />1.222 hours <br />0.00728 weeks <br />0.00167 months <br /> 90

>10000 hours These results are plotted in Figure 3. The plant is operstmg at 95% drive flaw. The crack 3

j-length vs. operating time plot for that condition is shown in Figure 4. The predictions presented are applicable to the longer of the two cracks at the JP 7/8 riser brace yoke, and bound the smaller crack.

4 i-

r-f GENE-B13-02008-L1

==

Conclusions:==

The crack length vs. time predictions above have conservatisms in several areas and the j

==ep;+=4 criteria, set at 10 inches, is well below the observed crack in 1994 in JP 5/6 I

which was about 15 inches long. Therefore, operation within the hours and recirculation drive Sows shown in Figure 3 is expected to result in acceptably limited growth of the JP 7/8 cracks.

References:

[1 Caine, TA to DeBoo, G, " Quad Cities 1 Jet Pump 7/8 Riser Brace. Yoke Safety J

A--'*." GE Letter GENE-B13-01980-34-2, Rev 1,12/1/98.

[2]

J.M..Barsom and S.T. Rolfe, " Fracture and Fatigue Control in Structures -

Applications ofFracture Mechanics," Prentice Hall. Inc. 2nd Edition,1987, f

[3]

P.K. Liaw, M.G. Peck and H.S. Mehta, " Fatigue Crack Propagation Behavior of Stainless Steels." Report prepared by Westinghouse STC for GE Nuclear Energy,

{

Contract No. 529-88B860X, April 1990 (GE Proprietary).

[4]

Caine et al, " Jet Pump Thermal Sleeve-to-Riser Elbow Weld Flaw Evaluation for Peach Bottom 3," GE Report GENE-523-B13-01869-121, Rev 0, March 1998, GE Proprietary.

[5]

Horn, RM, " Assessment of Crack Growth Rates Applicable to Induction Heating Stress Improvement (IHSI) Recirculation Piping in Quad Cities Unit 1," GE Report GENE-B13-01980-030-2, Rev. O, November 1998.

[6]

MSC/NASTRAN User's Manual, The MacNeal-Schwendler Corporation, Los Angeles, CA, Version 67, August 1991.

[7]

Caine, TA to DeBoo, G, " Quad Cities 1 Jet Pump Riser Elbow Weld (RS-1)

Cracking Evaluation," GE Letter GENE-B13-01980-34-1, Rev 0,11/27/98.

[8] Tada et al, "The Stress Analysis of Cracks Handbook, Second Edition," Paris

{

Productions, Inc.,1985, page 5.10.

[9] Letter, dated 1/15/69, Cooke to Distribution, " Reactor Recirculation Inlet Nozzle

{

Loading Data," see Tab 3 of this DRF.

[10] Rooke and Cartwright, " Compendium of Stress Intensity Factors," Her Majesty's

{

Stationery Office,1976.

[11) "1989 ASME B&PV Code - Rules for Inservice Inspection ofNuclear Power Plant

(

Components," Nonmandatory Appendix C.

i

-B-L-

fi GENE-B13-02008-L1 Table 1. FIV Stresses at the Crack l

NormW I4a),in.

Us, psi Gh, psi Stresses, psi

-10.25 920 50 485

-9.75 950 50 500

-9.25 980 50 515

-8.75 1010 50 530

-8.25 1040 50 545

-7.75 1070 80 575

-7.25 1100 110 605 4.75 1130 140 635

-6.25 1160 170 665

-5.75 -

1200 200 700

-5.25 1220 220 720

-4.75 1230 230 730

-4.25 1240 280 760

-3.75 1230 280 755

-3.25 1275 410 842.5

-2.75 1250 490 870

-2.25 1270 540 905

-1.75 1305 690 997.5

-1.25 1305 740 1022.5

-0.75

-1305 740 1022.5 0

1305 740 1022.5 0.75 1305 740 1022.5 1.25 1305-740 1022.5 1 75 1305 740 1022.5 2.25 1250 590 920 2.75 1225 470 847.5 3.25 1175 380 777.5 3.75 1125 300 712.5 4.25 1110 260 685 4.75 1080 210 645 5.25 1060 175 617.5 5.75 1020 130 575 6.25 960 120 540 6.75 910 110 510 7.25 860 100 480 7.75 810 90 450 8.25 760 80 420 8.75 760 70 415 9.25 760 60 410 9.75 760 50 405 10.25 760 50 405 i

_9

GENE-B13-02008-L1 4

4 4

i i

/

+

i Jet Pump #7 p 7/g gg pj Jet Pump #8 1

l 2.8" 1.2" i

Fillet Welds t

l

i:

i:!

t lll Riser Brace Yoke (view from shroud) l ((

l.5" (Ref.)

!!i

! l-

}

4

\\

1.0.

2.9" 4

4 4

Riser Pipe Seam Weld /

)

Figure 1. Sketch of Cracking at JP 7/8 Riser Brace Yoke i

, l

I 4

i GENE-B13-02008-L1 Ga a

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GENE-B13-02008-L1 Cracking Estimate for Jet Pump 7/8 Riser Yoke Region 20.000

-95% Drive Flow

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6.000 4.000 2.000 l

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1000 2000 3000 4003 5000 8000 7000 8000 9000 10000 7

Operating Time (hours)

Figure 4. Cracking Estimate for JP 7/8 with 95% Rated Recire Drive Mew !

General Electric Companv 175 Curtner Avenue, SanJose. CA 95125 GENE-B13-01980-34-1 November 27,1998 To:

Guy DeBoo, Comed cc: DS Braden, GE G Vanderheyden, Comed K Moser, Comed W Sanders, GE From:

TA Caine, GE

/

Subject:

Quad Cities 1 Jet Pump Riser Elbow Weld (RS-1) Cracking Evaluation Below is the technical evaluation to support restart of Quad Cities I with cracking at the RS-1 weld injet pump 19/20. Supporting calculations and evidence of verification are in DRF B13-01980-34. Please call me at (408) 925-4047 if you it.ve questions or need additional information regarding this evaluation.

Background:

During inspection of the jet pump risers in Quad Cities Unit 1, November 1998, three crack indications were found in thejet pump 19/20 riser at the elbow to thermal sleeve weld, designated as RS-1, on the elbow side of the weld. Based on ultrasonic examination (UT), the indications in the pipe are as follows (viewing RS-1 fror.1 outside the vessel)[l):

1. 4.1 inches in length, from 244' to 287* in the pipe,

2. 0.7 inches in length, from 212' to 219' in the pipe,

3. 5.6 inches in length, from 8' to 68'in the pipe.

Some liftoffof the UT transducer occurred near 0*, so the EVT-1 visual length of 3

6.0 inches in length, will be the value used in the analysis for indication #3, per [1].

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GENE-B13-01980 34-1 Obiectives:

Comed has requested an evaluation of the indications to determine whether operation as-is is acceptable. To determine acceptability, the following conditions are shown, assuming the indications are cracks:

Each individual crack length remains less than the flow induced vibration (FIV) threshold crack length, The total crack length, including crack growth for the upcoming cycle, is within the l

limit load allowables, Leakage from the cracks is calculated so that Comed can assess the impact of the leakage on fuel thermallimits.

Innuts:

f The following inputs were provided by or confirmed by Comed:

Crack details (length, location, etc), provided by GE Inspection Services, as described above were confirmed by Comed in [1].

The UT is done without having to reposition the tool during the scan, so there is no addition to crack length associated with inspection uncertainty. This position is consistent with the recirculation piping inspection approach, the basis being that uncertainties are covered by the analysis safety margins.

The representative ECP at the RS-1 weld location for the upcoming cycle, based on l

hydrogen water chemistry (HWC) performance similar to last cycle, is -50 mV, SHE (consensus value with Comed).

The riser delta-P for LPCI injection during long-term post-LOCA cooling, used for leakage calculation purposes, is 25 psid.

. The delta-K fatigue crack growth threshold property is 5 ksi-Vin. This value has been used in prior evaluations and is appropriate based on technical references (2,3].

l l

6 2-

GENE-B13-01980-34-1 Assumntions:

The following assumptions were made in perfonning the evaluation:

increased core flow (ICF) will not be done in the upcoming cycle. This assumption e

may be relaxed after startup with time to do more detailed analysis.

HWC in the upcoming cycle will be similar (injection level, system availability) to the previous cycle.

For leakage calculation purposes, a constant crack width of 0.01 inches over the length of the crack is used. This value has been shown to be conservative compared to linear clastic fracture mechanics-based methods for small cracks such as are being evaluated here.

Methods:

FIV Threshold Crack Length Determination The process followed to determine the FIV stress at the RS-1 weld location is summarized below:

1. Review the startup vibration data [4,5,6,7] to determine the primary modes ofinterest for thejet pump.

2. Using a finite elemeni 7odel of thejet pump, determine the analytical natural frequencies and mode shapes.

3. Adjust the finite element model such that the analytical natural frequencies and mode shapes show reasonable agreement with those from the measured strain data taken during startup testing at the corresponding locations in the jet pump.

4. Detennine from the finite element model the modal shape factors. The modal shape factors are used to analytically ratio the strains from the location where stanup test data was taken to the RS-1 weld location.

5. Based on the measured strain data from startup and the modal shape factors from the finite element model, calculate the modal stresses at the RS-1 weld location on the riser pipe for each mode ofinterest. Absolute sum the modal stresses from each mode to arrive at the final RS-1 FIV stress.

Once b FIV stress is determined, the FIV threshold crack length is calculated based on the K equation for a throughwall circumferential crack in a pipe. As long as the cracks are far enough apart that crack tip interaction is not a concern, the threshold crack length applies individually to each crack. This is checked by confirming that the crack tips are more than two pipe thicknesses (2t) apart. per ASME Code Section XI,IWA-3330.

i

[

GENE-B13-01980-34-1 Knowing the FIV threshold crack length and the current crack length, the acceptable crack growth is determined as the amount of growth that causes the crack to reach the

. threshold at the end of the cycle. This crack growth is assumed to occur over 2 years of operation (16000 hours at 90% CF), yielding an acceptable crack gmwth rase.

[

The acceptable growth rate is compared to model rates for HWC injection consistent with the HWC injection level planned for Quad Cities I to determine whether the rate is

[

reasonably conservative.

Limit Load Evaluation The crack lengths, including SCC growth for one cycle, are summed and compared to the

[

limit load allowable for one long crack. This is a conservative comparison, as the actual L

indications are distributed, providing more structural margin. He limit load calculations follow the method in Section 5 of BWRVIP-41 [8]. The RS-1 weld is treated as the

[.

worst case, a submerged arc weld (SAW), for which the Z factor is calculated to be 1.38.

Leakage Evaluation k

Leakage from tite cracks will be calculated for the case oflong-term, post-LOCA cooling,

. using the delta-P for LPCI injection. The leakage calculation is done according to the

(-

~ methods described in BWRVIP-41, with the crack area defm' ed as the crack length times a crack gap of 0.01 inches.

[

Analysis:

Acceptable Crack Growth Rate Determination Reported crack sizes: 6.0 inches (largest crack reported)

[

4.1 inches 0.7 inches

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He ligaments between these indications are all greater than 2t = 0.73 inches = 8', so each can be treated separately relative to FIV crack length.

[

FIV threshold-6.8 inches. based on a FIV stress range of 1020 psi for normal operation (no increased core flow)

[~

Acceptable growth:

0.4 in per crack tip for largest crack to reach FIV threshold Acceptable Crack Growth Rate (CGR): 0.4 inches /16000 hrs = 2.5x10 in/hr 4

The acceptable CGR is one half the NRC accepted rate for crack lengthening of 4

~

10 inihr for normal water chemistry (NWC).

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GENE-B13-01980-34-1 1

The crack growth rates for the GE PLEDGE model ana the BWRVIP-14 correlation are l,

evaluated for comparison with the acceptable rate of 2.5x10 in/hr. The water chemistry basis for the crack growth rate estimates is provided in [9], which also has the CGR for the PLEDGE model. The water chemistry assumptions for the upcoming cycle, based on the previous cycle, are an average conductivity of 0.1 uS/cm and an ECP of-50 mV, SHE. His is higher than the conductivity average last cycle of 0.09 uS/cm and is on the conservative end of the expected ECP range of-50 to -100 mV, SHE. The BWRVIP-14 CGR for this HWC condition is not calculated in [9], so the CGR was calculated using the correlation in BWRVIP-14 [10):

In(da/dt) = 2.181In(K) - 0.787Cond" + 0.00362ECP + 6730/Tm -35.567(1) where K-25 ksiVin (27.5 MPaVm), Cond=0.1 uS/cm, ECP=-50 mV, SHE, T

=561*K.

The PLEDGE and BWRVIP-14 CGRs are presented in the results section.

f The current NRC position is to accept a depth CGR of 2.2x10'8 in/hr, but a length CGR of 5x10-5 in/hr. Therefore, a ratio of 5.0/2.2 = 2.3 is imposed on PLEDGE and BWRVIP-14 CGR estimates to estimate corresponding lengthening CGRs (this is judged to be conservative because, for length growth of throughwall cracks, the depth CGRs are expected to be reasonable, especially for HWC conditions where new initiation is unlikely).

Limit Load Allowable ne acceptable CGR of 2.5x10-5 in/hr is applied at each of the 6 crack tips. For the proposed 16000 hour cycle, that represents 2.4 inches of total crack growth. The total end-of-cycle (EOC) crack length would then be 6.0+4.1+0.7+2.4 = 13.2 inches This total crack length is compared to the limit load allowable in the results.

~ Leakage The leakage r.ssociated with the predicted crack lengths is calculated for the long-term cooling LPCI injection scenario. The delta-P for this condition is an input from GE's systems group [12), confirmed by Comed. The leakage calculation is based on the relationship in BWRVIP-41 [8], using a crack opening area of the crack length times an assumed crack opening width of 0.01 inches.

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GENE-B13-01980-34-1 Results:

[

HWC Predictions vs. Acceptable Crack Growth Rate

[

. In [4], the PLEDGE CGR for a K of 25 ksi-Vin at Quad Cities 1 HWC conditions is 4

1.5x10 in/hr. Applying the length / depth factor of 2.3, the predicted !=g*='- - CGR is 4

3.5x10 in/hr. The acceptable CGR is 7 times this rate.

The BWRVIP-14 CGR, based on equation (1), is 4.7x104 in/hr. Applying the length / depth factor of 2.3, the predicted lengthening COR is 1.1x10 in/hr. He 4

I acceptable CGR is over 2 times this rate, i

Therefore, the acccptable crack growth rate is conservative relative to expected HWC crack growth rates, even allowing for a sm all amount of time at NWC conditions.

l Limit Load Allowable -

The total crack length at EOC is 13.2 inches. De limit load allowable is based on a FIV

[

stress amplitude of 510 psi (no ICF). For Schedule 40 pipe, with Z-1.38, the smallest allowable flaw size, for a single flaw, is 17.7 inches. Therefore the total cracking at EOC, including conservative crack growth, is acceptable relative to the limit load allowables.

Leakage Leakage is plotted vs. total crack length in Figure 1 for the LPCI injection condition. The leakage from the three cracks, based on EOC total length of 13.2 inches, is 25 gpm during LPCI injection. This leakage will be used by Comed to evaluate fuel thermal limits.

==

Conclusions:==

A=suming that Quad Cities _1 does not operate in increased core flow conditions, the FIV threshold crack length is 6.8 inches. The cracks found in RS-1, including a conservative estimate of crack growth given HWC operation similar to last cycle, will not reach the FIV threshold crack length. The total of the crack lengths, including crack growth for 16,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of operation, is within the limit load allowable. Therefore, operation for a two-year cycle without ICF and with HWC is acceptable give: the cracking found at RS-1 injet pump 19/20. Determination of the acceptability of the leakage from the cracks,25 gpm,is Comed's responsibility.

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GENE-B13-01980-34-1

References:

f

[1 Uhrich, M," Ultrasonic Results from Quad Cities Station Unit 1 - Weld RSI on Jet Pumps 19 and 20," Comed NDIT No. QDC-98-02%,11/27/98.

[2]

J.M. Barsom and S.T. Rolfe, " Fracture and Fatigue Contml in Structures -

Applications of Fracture Mechanics," Pmntice Hall, Inc. 2nd Edition,1987.

[3]

P.K. Liaw, M.G. Peck and H.S. Mehta, " Fatigue Crack Propagation Behavior of -

Stainless Steels," Repon prepared by Westinghouse STC for GE Nuclear Energy, Contract No. 529-88B860X, April 1990 (GE Proprietary).

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[4]

Sager, M, " Quad Cities 1 Confinnatory Vibration Measurements (data taken

~ 5/15/72 through 6/30/72)," DRF B11-00825.

(

[5]

Sager, M, " Quad Cities 2 Confirmatory Vibration Measurements (data taken 6/13/72 through 7/3/72)," DRF B11-00825.

.(

[6]

Sager, M," Quad Cities 1 Conar=mory Vibration Measurements (data taken 1/16/73 through 1/17/73)," DRF B11-00825.

[

[7] -

Sager, M, " Quad Cities 2 Confumatory Vibration Measurements (data taken 6/72, 7/72 and 1/73)," DRF B11-00825.

b

-[8] "BWRVIP Jet Pump Assembly Inspection and Flaw Evaluation Guidelines (BWRVIP-41)," EPRI Repon TR-108728, October 1997.

y t

[9] Horn, RM, " Assessment of Crack Growth Rates Applicable to Induction Heating Stress impmvement (IHSI) Recirculation Piping in Quad Cities Unit 1," GE Repon j

GENE-B13-01980-030-2, Rev. O, November 1998.

[10] "BWRVIP Evaluation of Crack Growth in BWR Stainless Steel RPV Internals

[-

~

- (BWRVIP-14)", EPRI Repon TR-105873, March 1996.

[11) Caine, TA, "BWR Core Shroud Distributed Ligament Length Computer Program

(

. [ Version 2.1]," GE Repon GENE-523-113-0894, Revision 1 October 1996.

[12] GE Drawing 730E775, " Residual Heat Removal System (RHR)," Revision 1.

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Canmonwealth Edison Campany NEP-12-03 Noelear Operations Division Revision 0 NUCLEAR DESIGN INFORMATION TRANSMITTALS (NDIT)

Attachment B, NDIT Forms, Part 1 l

COMED NUCLEAR DESIGN INFORMATION TRANSMITTAL LSAFETY-RELATED Originating Organization NDIT No. NFM9800241. SEO. O

_NON-SAFETY-RELATED LComEd

_ REGULATORY RELA'IED

_Other(specify)

Station Ouad Cities Unit (s) 1 Page 1

of 2

Design Change Authority No.:

System Designation: Core Sorav & LPCI To Martin G. Santic Subject Imanet A-=====t of Core Sorav and Recirculatimr1Finar Flaws c ^t '.OCA & Containmcat Analyses John M. Freeman Reactor Safety Analyst I ri. para posioon

's sisnense one M. H. Youssefnia Reactor Safety Analyst

.=%

~

/ MLb 8 asvieww Poemon F.-.S ' "_

Dee Status ofInformation: LApproved for Use

_ Unverified

_ Engineering Judgement -

Method and Schedule of Verification for Unverified NDITs:

N/A Description ofInformation:

I Per thz request of the Quad Cities Engineering staff, Nuclear Fuel Management (NFM) is transmitt impact on the licensing basis Quad Cities LOCA and Containment analyses due to the effect of core spray and recirculation riser flaws. This work is being provided to Quad Cities for the purpose of an operability assessment only.

l Purpose ofIssuance:

The purpose of this assessment is to address the impact on the licensing basis Quad Cities safety analyses due to the effect cf the most recently observed core spray and recirculation riser flaws.

f SourceofInformation:

" Impact Assessment of Core Spray and Recirculation Riser Flaws on the Quad Cities Safety Analysis," letter NFS:BSA:98-139 to D. B. Wozniak (QC-SEM) from R. W. Tsai (NFM), dated December 2,1998.

Distribution: Keith R. Moser (DG), Guy DeBoo (DG), Nancy J. Buck (DG), Quad Cities Central Files, DG Central Files Fils No.:

' CHRON No.:

I page

,m.e3,o

MmmiawCMD LEason(L;cmpaIy NEP-12-03 Nuclear Operations Divisio2 Revisiom 0 NUCLEAR DESIGN INFORMATION TRANSMITTALS (NDIT)

(

Attaebment B, NDIT Form, Part 2 COMED NDIT No. NFM9800241. SEO. 0

- NUCLEAR DESIGN INFORMATION TRANSMITTAL Page 2 of_2_

NFM has determined that the changes in the Quad Cities safety analysis inputs caused by Core Spray and

[

Recirculation riser flaws have acceptable impact on the Licensing basis LOCA analysis results and have no impact on containment analysis results. The impact of Emergency Core Cooling System (ECCS) leakage due to the core spray and recirculation riser flaws have been addressed by applying the LOCA analysis

(

results of the case which conservatively bounds the expected leakage.

No impact due to the CS piping flaws on 10CFR50.46 LOCA analysis or on UFSAR section 6.2

(

containment analysis.

No Impact due to the Jet Pump Riser 19/20 piping flaws on 10CFR50.46 LOCA analysis or on UFSAR section 6.2 containment analysis.

No impact due to the Jet Pump Riser 7/8 Brace Yoke piping flaws on UFSAR section 6.2 containment analysis.

Jet Pump Riser 7/8 Brace Yoke piping flaws will affect LOCA PCT while all 10CFR50.46 safety limit criteria are being met. Peak Cladding Temperature (PCT) changes are as follows:

GE Fuel SPC fuel Current Licensing Basis 1850'F 1884*F Impact of Jet Pump Riser 7/8 Brace Yoke piping flaws +175'F

+78'F Revised LOCA PCT 2025'F 1962'F 10CFR50.46 safety limit PCT

<2200'F

<2200'F

(

(

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f L

page '2(Last) sAtt e r

Memorandum l

l l

Date:

December 2,1998 NFS:BSA:98-139 To:

David B. Wozniak

Subject:

Impact Assessment of Core Spray and Recirculation Riser Flaws on the Quad Cities Safety Analysis I

References:

See Attachment Per the request of f a Quad Cities Engineering staff, Nuclear Fuel Management (NFM)is addresci Ae impact on the licensing basis Quad Cities safety analyses due to the effect t

,entified core spray and recirculation riser flaws. This work is I

being provided te ' sad Cities for the purpose of an operability assessment only.

NFM has determin, j that the changes in the Quad Cities safety analysis inputs

)

resulting from the CS and recirculation riser flaws have acceptable impact on the i

Licensing basis LOCA analysis results and have no impact on containment analysis results and the transient analyses. The impact of Emergency Core Cooling System (ECCS) leakage due to the core spray and recirculation riser flaws have been I

addressed by applying the LOCA analysis results of the case which conservatively bounds the expected leakago. The attachment presents a detailed description of the impact assessment performed by NFM.

l If you have questions or comments about this information, please contact John Freeman of my staff at Downers Grove extension 3044.

5' l

' Robert W. Tsai n

BWR Safety Analysis Supervisor l

Nuclear Fuel Management RWT/JMF/pc

Attachment:

Impact Assessment of Core Spray and Recirculation Riser Flaws on I

the Quad Cities Safety Analysis 1

L E

l

December 2,1998 (L

NFS:BSA:98-139 D vid B. Wezni;k Page 2 of 10

(

[f cc: BSA-CF -

K. P. Donovan /NFS-CF M. H. Youssefnia

(

D. A. Worthington / N. J. Buck '

C. Alguire (OC)

. A. L Misak (OC) -

D, F. Schumacher (OC)

M. G. Santic (OC)

B. R. Strub (OC)

J. R. Ullrich (OC)

Document ID: pp.9 8 '00 /307 f

I J

f

I December 2,1998 NFS:BSA:98-139 D:vid B. Wozniak Page 3 of 10

Attachment:

Impact Assessment of Core Sorav and Recirculation Riser Flaws on the Quad Cities Safety Analysis Purpose The purpose of this assessment is to address the impact on the licensing basis Quad Cities safety analyses due to the effect of the most recently observed core I

spray and recirculation riser flaws. This impact assessment for operability is based on the data received from General Electric's safety assessments and Quad Cities station calculations (References A.1 to A.4). Since those documents addressed the I

mechanical and structural requirements, only the leakage effects of the flaws are addressed for the licensing basis LOCA analysis and containment analysis.

References A.3 and A.4 concluded that normal operation and anticipated transients 1

are not affected by the Jet Pump riser flaws as described in BWRVIP-28. This conclusion is consistent with the Jet Pump Riser Flaws addressed by General Electric in Reference A.5. Clearly, the CS flaws only have impact on the reactor where CS is required to operate, i.e. LOCA events. The impact of the core spray and l

recirculation riser flaws is on the ECCS capability under accident conditions.

Description of the Chanced ECCS Data The effect of the flaws on the ECCS flow rate was described in References A.2, A.3 and A.4. References A.1, A.3 and A.4 address the structuralissues associated with the flaws. These flaws will be addressed with respect to the current licensing basis LOCA analysis. The most recent LOCA results were docketed in the Reference A.7, 10CFR50.46 report. Quad Cities UFSAR section 6.2 has the current licensing basis r

L containment analysis. The char,ges to the current licensing basis LOCA and containment analysis to be astassed can be summarized as:

[

1.

The folicwing iable summarizes the previous and current status of the Quad Cities Unit 1 CS flaws. As a result of the previous inspection on Unit 1, the bounding CS elbow flaw at weld P4d for a 24 month crack

[

growth was identified as 5 GPM for 47 psid and 6 GPM for 64 psid in Reference A.6. This maximum per crack leakage was changed to 2.5 GPM in Reference A.2. The LOCA analysis currently is analyzed for a

[

CS flaw leakage of 62 GPM at 47 psid and 92 GPM at 64 psid (References A.9 to A.12). The most recent inspections of these welds summarized in Reference A.1 revealed individual flaw lengths smaller

[

than the individual flaw lengths identified in Reference A.6. Therefore a total of 7.5 GPM of CS leakage is calculated to occur for both loops "A" and "B" combined flow after postulating 48 months of crack growth.

[

[

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l

1 December 2,1998 NFS:BSA:98-139 D vid B. Wozniak Page 4 of 10 Summary of Quad C:lties Unit 1 Core Spray Elbow Flaws CS Piping Flaw Evaluated Flaw Calculated Evaluated Flaw Calculated Location Length 24 Leakage at 64 Length 48 Leakage at 64 months growth psid (Ref. A.6) months growth paid (Ref. A.2)

(Ref. A.6)

(Ref. A.1)

Upper Sparger 8.72 "

6GPM 7.16" 2.5 GPM Elbow 290' I

Loop "A" Lower Sparger 7.32" 6GPM*

6.96" 2.5 GPM*

Elbow 260*

I Loop "B" Lower Sparger N/A N/A 6.36" 2.5 GPM*

260' Loop "B" l

Elbow 110'

• The leakage calculation was conservatively performed for the maximum observed crack size l

I Unit 1 Jet Pump Riser elbow flaws at weld RS-1 were identified. This 2.

flaw is on the riser for Jet Pump 19/20, that is recirculation Loop "B."

The leakage from this flaw was determined by GE for the LOCA differential pressure conditions to be 25 GPM (Reference A.3).

3.

Unit 1 Jet Pump Riser Brace Yoke flavs at the weld connection were identified. This flaw is on the riser for Jet Pump 7/8, that is recirculation Loop "A." The leakage from the observed size of the flaw totallength of 7.9 inches was determined at 15 GPM per Reference A.13. This leakage needs to be evaluated.

However, GE has pointed out that it would require the cracks to propagate until a hexagonal segment separated from the pipe to yield detectable leakage. Since a repair to this riser brace is being f abricated, continued operation with the flaws propagating up to the postulated detectability threshold is required. The plant estimated Jet Pump Riser leakage flow rate up to the postulated detectability threshold at rated power conditions was identified as 520 GPM in Reference A.14. A conservatively chosen 10% reduction in Jet Pump Riser flow due to leakage would be 920 GPM as described in Reference A.13. Rated conditions for leakage are not appropriate for LOCA differential pressure conditions. For the purposes of a LOCA conditions assessment which has a lower differential pressure driving the leakage, a conservative 373 GPM Jet Pump Riser leakage will be evaluated per Reference A.13. If the Jet Pump 7/8 riser has detectable leakage as described in Reference A.14, Quad Cities station will take actions upon surveillance failure will be to determine if jet pump 8 flow instrumentation problems could be the cause of the ratio shift. If instrumentation problems are not identified, shutdown of the "A" recirculation loop will commence. This compensatory action assures i

December 2,1998 NFS:BSA:98-139 D;vid B. Woznirk.

Page 5 of 10 that a LOCA cannot occur at a Jet Pump Riser leakage above the detectable threshold.

Evaluation of the Chanaes Imoact on Siemens LOCA Analysis The latest assessment which summarizes the current Siemens LOCA licensing basis results before the observation of the three previously described flaws was outlined in Reference A.B. The current licensing basis for the assessment is the Siemens LOCA analysis in Reference A.9 Appendix C which resulted in a PCT of 1884'F for the limiting case of a double ended guillotine break of the recirculation suction piping with a single failure of the LPCI injection valve. Input parameters for the current licensing basis LOCA analysis for Siemens fuelis Reference A.10. Therefore the three flaw issues will be addressed with respect to these references.

1. The Unit 1 CS elbow flaw revised leakage of 7.5 GPM for the three CS flaws together is conservatively bounded by the current LOCA analysis input value of 92 GPM at 64 psid for CS flaws. This was described in the Siemens LOCA input parameters in Reference A.10 along with all of the other analyzed penalties to the delivered CS. This reduction in leakage yields 84.5 GPM of additional conservatism in the current analysis. This amount of total CS leakage from the elbow flaws is already consentatively analyzed. Therefore, there is no impact on the LOCA analysis due to these CS elbow flaws.

2. The Unit 1 Jet Pump Riser 19/20 elbow flaws at weld RS-1 leakage of 25 GPM is conservatively bounded by the current LOCA analysis in Reference A.9. A previously identified Jet Pump riser 5/6 flaw had been repaired, but a leakage of 180 GPM has already been included in the LOCA analysis. This 180 GPM of leakage applies for two LPCI pump delivery. The 180 GPM leakage is applied in the LOCA analysis despite whether the "A" or "B" recirculation loop is selected for injection. So long as the total leakage in the "B" recirculation loop is less than the d

180 GPM assumed in the current licensing basis LOCA analysis, then it is conservatively bounded by the current LOCA analysis in Reference A.9. LPCI leakage assumptions were described in the Siemens LOCA input parameters in Reference A.10. Therefore, there is no impact on the LOCA analysis due to these Jet Pump Riser elbow flaws.

3. The current leakage from the Jet Pump 7/8 Riser of 15 GPM occurs in the "A" recirculation loop which already has the 180 GPM of leakage due to flaws in the Jet Pump 5/6 Riser. This would be a net increase in the leakage affecting the

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delivered LPCl flow to the core. This increase in LPCI leakage does not have any impact on the licensing basis LOCA case of a LPCI injection valve failure. This limiting single failure case does not credit any LPCI to mitigate the LOCA. It requires only 2 CS pumps to mitigate the LOCA. The increase in LPCI leakage could have impact on non-limiting cases where LPCl is credited, such as the Battery Failure case. In the Battery failure case, the Unit diesel generator is disabled leaving one CS pump and 2 LPCI pumps available to mitigate the LOCA. In this case, the increase of LPCI leakage by 15 GPM is offset by the reduction in CS leakage by 84.5 GPM. For the Battery failure DBA LOCA scenario, CS will inject prior to LPCI. Gallon for gallon CS is equally effective as LPCI in reflooding the reactor core in Siemens LOCA methodology. There is no impact on the LOCA analysis due to the observed Jet Pump Riser pipe flaws.

i

December 2,1998 NFS:BSA:98-139 David B. Woznick Page 6 of 10 The postulated crack propagation until a hexagonal segment separated from the pipe to yield detectable leakage can be addressed. A conservative detectability threshold at the leakage flow rate of 920 GPM at rated core power and rated core flow will be used. This 920 GPM is conservative relative to the plant estimated threshold of detectability of 520 GPM of Jet Pump Riser leakage at rated core power and rated core flow as described in Reference A.14. The pressure differential driving the leakage at rated conditions will be 153 psid (Reference A.13). This is much greater than the pressure d!fferential driving the leakage under LOCA conditions of 25 psid (References A.4 and A.13). The detectability threshold for rated conditions leakage was converted into LOCA conditions leakage in Reference A.13. LPCI flow leakage under LOCA conditions for the detectability threshold is 373 GPM (Reference A.13). Since this leakage will be on loop "A" of the recirculation piping, this would be a net increase in the leakage affecting the delivered LPCI flow to the core.

The postulated increase in LPCI leakage would have impact on non-limiting cases where LPCI is credited, such as the Battery Failure case. In the Battery failure case, the Unit diesel generator is disabled leaving one CS pump and 2 LPCI pumps available to mitigate the LOCA. In this case, the increase of LPCI leakage by 373 GPM can be conservatively assessed based on an existing LOCA sensitivity analysis for a 10% reduction in total CS and LPCI flow delivered to the core. This 10% reduction in ECCS flow rate sensitivity analysis was documented in Appendix B of Reference A.9. The Reference A.9, Appendix B analysis showed that for a 900 GPM reduction in LPCI delivered flow, along with a 900 GPM reduction in CS flow, there was a +78*F impact on the limiting case licensing basis Peak Cladding Temperature (PCT). Stating from a PCT 1884*F from Appendix C of Reference A.9, this would result in a PCT of 1962*F which is well below the 10CFR50.46 criteria of 2200*F.

Continued long term cooling of the reactor core is assured with the reduction in LPCI delivered flow rates. Only one LPCI or CS pump is required for long term cooling after water level in the vessel reaches 2/3 core height. This analysis in Appendix B of Reference A.9 conservatively bounds the Jet Pump Riser LPCI leakage flow rate at the detectability threshold of 373 GPM. The results from Appendix B of Reference A.9 conclude that the limiting case is unchanged and all of the 10CFR50.46 requirements are met. The Unit 1 Jet Pump Riser Brace Yoke flaws grown to the detectability threshold flow rate willincrease the Siemens fuel PCT, but the PCT will remain acceptable and below the 10CFR50.46 licensing safety limit of 2200F.

Evaluation of the Chances impact on GE LOCA Analysis The latest assessment which summarizes the current GE LOCA licensing basis results before the observation of the three previously described flaws was outlined in Reference A.8. The current licensing basis for the assessment is the GE SAFER /GESTR-LOCA analysis and subsequent evaluations as outlined in Reference A.7. It resulted in a PCT of 1850*F for the limiting case of a double ended t

December 2,1998

[

NFS:BSA:98-139 DIvid B. Woznitk Page 7 of 10 illotine break of the recirculation suction piping with a single failure of the 125 Volt attery. Input parameters for the current licensing basis LOCA analysis for GE fuel is Reference A.12. Therefore the three flaw issues will be addressed with respect to

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- these references:

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1. Similar to the Siemens evaluation, the Unit 1 CS elbow flaw rev sed leakage of i

7.5 GPM for the three CS flaws together is conservatively bounded by the current LOCA analysis input value of 92 GPM at 64 psid for CS flaws. This was

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described in the GE LOCA input parameters in Reference A.12 along with all of the other analyzed penalties to the delivered CS. This reduction in leakage yields 84.5 GPM of additional conservatism in the current analysis. This~ amount of total CS leakage from the elbow flaws is already conservatively analyzed. There is no impact on the LOCA analysis due to these CS elbow flaws I

2. Similar to the Siemens evaluation, the Unit 1 Jet Pump Riser 19/20 elbow flaws at weld RS-1 leakage of 25 GPM is conservatively bounded by the current GE LOCA analysis. The LPCI leakage assumption was described in Note 9 of Reference A.7 which was based on the 180 GPM GE LOCA evaluation for the Jet Pump Riser in Reference A.S. A pieviously identified Jet Pump riser 5/6 flaw had been repaired, but a leakage of 180 GPM has already been included in the LOCA analysis. This 180 GPWI of leakage applies for two LPCI pump delivery.

The 180 GPM leakage is applied in the LOCA analysis despite whether the "A" or "B" recirculation loop is selected for injection. So long as the total leakage in the "B" recirculation loop is less than the 180 GPM assumed in the current licensing basis GE LOCA analysis, then it is conservatively bounded by the current LOCA analysis as described in Note 9 of Reference A.7. There is no impact on the LOCA analysis due to these Jet Pump Riser elbow flaws.

i l

3. Similar to the Siemens evaluation, the current leakage from the Jet Pump 7/8 Riser of 15 GPM occurs in the "A" recirculation loop which already has the 180 GPM of leakage due to flaws in the Jet Pump 5/6 Riser. This would be a not

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increase in the leakage affecting the delivered LPCI flow to the core. The i

increase in LPCI leakage could have impact on the GE limiting case where LPCI i

is credited, i.e. the Battery Failure case. In the Battery failure case, the Unit

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diesel generator is disabled leaving one CS pump and 2 LPCI pumps available to mitigate the LOCA. In this case, the increase of LPCI leakage by 15 GPM is i

offset by the reduction in CS leakage by 84.5 GPM. Non-limiting single failure LPCI injection valve failure case does not credit any LPCI to mitigate the LOCA.

It requires only 2 CS pumps to mitigate the LOCA and would not be affected by I

the Jet Pump Riser leakage. For the Battery failure DBA LOCA scenario, CS will inject prior to LPCI. Gallon for gallon CS is equally effective as LPCI in reflooding j

the reactor core in GE LOCA methodology. There is no impact on the LOCA analysis due to the observed Jet Pump Riser pipe flaws.

l Similar to the Siemens evaluation, the postulated crack propagation until a l.

hexagonal segment separated from the pipe to yield detectable leakage can be i

addressed. A conservative detectability threshold at the leakage flow rate of 920 i

GPM at rated com power and rated core flow will be used. This 920 GPM is j

conservative rew,o to the plant estimated threshold of detectability of 520 GPM of Jet Pump Riser leakage at rated core power and rated core flow as described j.

in Reference A.14. The pressure differential driving the leakage at rated i

j.

e

.w..

w e,

December 2,1998

{.

NFS:BSA:98-139 D;vid B. Wozni;k Page 8 of 10 conditions will be 153 psid (Reference A.13). This is much greater than the pressure differential driving the leakage under LOCA conditions of 25 paid (References A.4 and A.13). The detectability threshold for rated conditions h

leakage was converted into LOCA conditions leakage in Reference A.13. LPCI flow leakage undar LOCA conditions for the detectability threshold is 373 GPM (Reference A.13) Since this leakage will be on loop "A" of the recirculation piping,

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this would be a net increase in the leakage affecting the delivered LPCI flow to the core.

The postulated increase in LPCI leakage would have impact on the GE linliting r.

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case where LPCI is credited, i.e. the Battery Failure case. In the Battery failure case, the Unit diesel generatoris'd!sabled leaving one CS pump and 2 LPCI pumps available to mitigate the LOCA. In this case, the increase of LPCI leakage

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by 373 GPM can be conservatively assessed based on an existing LOCA sensitivity analysis for a 10% reduction in total CS and LPCI flow delivered to the core. This 10% reduction in ECCS flow rate sensitivity analysis was documented

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in Reference A.11. The Reference A.11 analysis showed that for a 900 GPM l-reduction in LPCI delivered flow, along with a 900 GPM reduction in CS flow, there was a +175'F impact on the licensing basis Peak Cladding Temperature (PCT). Statin from a PCT 1850*F from Reference A.7, this would result in a

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PCT of 2025*h which is below the 10CFR50.46 criteria of 2200*F.

Continued long term cooling of the reactor core is assured with the reduction in LPCI delivered flow rates. Only one LPC! or CS pump is required for long term cooling after water level in the vessel reaches 2/3 core height. This analysis in Reference A.11 conservatively bounds the Jet Pump Riser LPCI leakage flow rate at the detectability threshold of 373 GPM. The results from Reference A.11 conclude that the limiting case is unchanged and all of the 10CFR50.46 requirements are met. The Unit 1 Jet Pump Riser Brace Yoke flaws grown to the detectability threshold flowrate will increase the GE fuel PCT, but the PCT will remain acceptable and below the 10CFR50.46 licensing safety limit of 2200F.

Evaluation of the Chanaes Imaad on Containment Analysis For UFSAR section 6.2 the containment analysis was based on the DBA LOCA for

' the initial fuel load. This LOCA was for a double ended guillotine rupture of the reactor recirculation piping. Conservative assumptions were used in the original mass and energy releases which bound the current Siemens and GE LOCA analysis. The bounding containment analysis case does not explicitly include ECCS leakage intomai to the reactor vessel. Long term temperature increases are driven by RHR heat exchanger capacity and RHRSW temperatures, not by overall ECCS flow rates delivered to the reactor vessel. The ECCS flow simply provides a path for decay heat power from the core to be transferred to the suppression pool where i.

RHR can remove it. Therefore, since the ECCS pumps flow rates into the reactor vessel are not changin containment analyses.g, the changed leakage can not have any impact on the

December 2,1998

[.

NFS:BSA:98-139 D:vid B. Wezniak

' Page 9 of 10 f

Conclusion NFM has determined that the impact of i;iese flaws on the Quad Cities LOCA f

Analysis will be acceptable with respect to all of the 10CFR50.46 licensing bash criteria including the 2200F PCT.

Attachment

References:

A.1" Quad Cities Unit 1 Core Spray Flaw Evaluation," Calculation Number ODC-0200-M-0768, dated November 30,1998 A.2" Quad Cities Unit 1 Core Spray Leakage Evaluation," Calculation Number QDC-0200-M-0769, dated November 30,1998 A.3" Quad Cities 1 Jet Pump Riser Elbow Weld (RS-1) Cracking Evaluation," General Electric letter report GENE-B13-01980-34-1, to G. DeBoo (Comed) from T. A.

Caine (GE), dated November 27,1998.

A.4" Quad Cities 1 Jet Pump 7/8 Riser Brace Yoke Safety Assessment," General Electric letter report GENE-B13-01980-34-2, Rev.1, to G. DeBoo (Comed) from T. A. Caine (GE), dated December 1,1998.

A.5" Safety Evaluation of Reactor Intemals Configuration for the 1994 Quad Cities 1 Restart," GE Document GE-NE-A0005873-19A, June 1994.

A.6" Quad Cities Unit 1 Core Spray Flaw Evaluation Report," Sargent and Lundy Report SL-5060, Revision 0, March 28,1996.

A.7 " Quad Cities Nuclear Power Station Units 1 and 2 Plant Specific Emergency Core Cooling System (ECCS) Evaluation Changes 10CFR50.46 Report, DPR-29 and DPR-30, NRC Docket Nos. 50-254 and 50-265," letter SVP-98-146 to Office of Nuclear Reactor Regulation (NRC) from David A. Sager (Comed-Quad), dated April 17,1998.

A.8" Impact Assessment of Changed ECCS Data Used in the Quad Cities LOCA Analysis," letter NFS:BSA:98-102 to R. S. Holbrook (OC-SEM) from R. W. Tsal (NFM), dated August 17,1998.

A.9 " Quad Cities LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM-98 Fuel,"

Siemens Power Corporation document EMF-96-185(P), Revision 4, dated August 1998.

A.10 "LOCA input Parameters for Quad Cities Units 1 and 2 for Siemens ATRIUM-9B Fuel," NDIT NFM9800175, SEO.00, dated October 23,1998.

A.11 "ECCS Performance with Instrument Uncertainties: A Qualitative Assessment for Quad Cities Nuclear Power Station Units 1 and 2," GE document GE-NE-L1200846-05P, dated April 1998.

I

December 2,1998 1

NFS:BSA:98-139 D;vid B. Wozniak l

Page 10 of 10 I

A.12 " Revised LOCA Input Parameters for Quad Cities Units 1 and 2 (GE Fuel),"

Nuclear Fuel Management Nuclear Design information Transmittal NDIT NFM-97-00195, Sequence 02, to D. B. Wozniak (OC-SEM) from J. M. Freeman (NFM-BSA), dated November 13,1998.

A.13 " Leakage Assessment of the 7/8 Jet Pump Riser Pipe Flaws," Quad Cities Unit 1, NDIT No. MSD-98-043-00 to J. Freeman dated Deceraber 2,1998.

A.14 " Jet Pump 8 Riser Leakage Detectability Limit," letter to J. D. Purkis (OC) from A. L Misak (OC), dated December 2,1998.

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