ML020720547

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Part 2 of 2, Kewaunee Nuclear Power Plant, 2001 Inservice Inspection (ISI) Summary Report
ML020720547
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 02/22/2002
From: Coutu T
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-02-015
Download: ML020720547 (92)
v • d • e


Text

{{#Wiki_filter:FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI Date 12/3/2001

1. Owner Wisconsin Public Service Corporation Sheet 1 of 2 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Unit No. I
2. Plant Kewaunee Nuclear Power Plant Work Order 01-014720 N490 HWY 42 Kewaunee, WI 54216-9511 Type Code Sym. Stamp _A_
3. Work Performed By Nuclear Management Company, LLC 700 First Street, Hudson, Wisconsin 54016 Authorization No. NA Expiration Date NA
4. Identification of System 33 Class 1 SAFETY INJECTION Code Case NA
5. (a) Applicable Construction Code B16.5-1967 1989 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements Components
6. Identification of Components Repaired or Replaced and Replacement Repaired, ASME Manufacturer National Other Year Replaced, or Code Name of Name of Board No. ID Built Replacement Stamped Component Manufacturer Serial No.

S1116-005 1967 REPAIRED N VELAN VALVE NF NA SI-304A CORPORATION BODY CLASS 1 6" SAFETY INJECTION VALVE SI

7. Description of Work OPEN FOR INSPECTION AND SEAL WELDING OF BONNET TO 304A.
8. Tests conducted Hydrostatic [- Pneumatic F Nominal Operating Pressure E- Exempt F' Pressure 2240 psi Test Temp. 551 deg. F Other
9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back) Sheet 2 of 2 Date: - 12/3/2001 Name of Component: SI-304A Work Order Number: 01-014720 Certificate of Compliance REPAIRED conforms to the rules of the We Certify that the statements made in the report are correct and this ASME Code Section XI. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed ýLa)g-**I*#'/*O7 LI/' Date ,*3_ 20 0.), Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION Vessel Inspectors I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure of Hartford, CT and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Ins. Co. to /-31/-OZ , and state that have inspected the components described in the Owner's Report during the period 7-;r-00 corrective measures described to the best of my knowledge and belief, the Owner has performed examinations and taken XI. in this Owner's Report in accordance with the requirements of the ASME Code, Section or implied, concerning By signing this certificate neither the Inspector nor his employer makes any warranty, expressed the Inspector nor the examinations and corrective measures described in this Owner's Report. Furthermore, neither any kind arising his employer shall be liable in any manner for any personal injury or property damage or a loss of from or connected with this inspection. 4 l  ; Lýýý--- Commissions NB7741, 1, N, IS, A WIS 100024 National Board, State, Province, and Endorsements Inspector4s Signature Date 20 7

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI Date 11/8/2001

1. Owner Wisconsin Public Service Corporation Sheet 1 of 2 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Unit No. 1
2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee, WI 54216-9511 Work Order 01-016057 Type Code Sym. Stamp NA
3. Work Performed By Nuclear Management Company, LLC 700 First Street, Hudson. Wisconsin 54016 Authorization No. NA 34 Class 2 RESIDUAL HEAT REMOVAL Expiration Date NA
4. Identification of System
5. (a) Applicable Construction Code B31.1-1967 Code Case NA (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989
6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Name of Name of Manufacturer National Other Year Replaced, or Code Component Serial No. Board No. ID Built Replacement Stamped Manufacturer RHR-8B FISHER 141551 NA AC012-002 1972 REPAIRED N CONTINENTAL
7. Description of Work REPAIR LOOSE NUT ON CLASS 2 RESIDUAL HEAT REMOVAL SYSTEM 8" VALVE RHR-8B SHAFT COVER.
8. Tests conducted Hydrostatic El Pneumatic Nominal Operating Pressure El Exempt El psi Test Temp.

Other D Pressure deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back) Sheet 2 of 2 Date: " 11/8/2001 Name of Component: RHR-8B Work Order Number: 01-016057 Certificate of Compliance We Certify that the statements made in the report are correct and this REPAIRED conforms to the rules of the ASME Code Section XL. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA e & LgAnw, Date 20 CA Signed & & Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors CT and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Ins. Co. of Hartford, have inspected the components described in the Owner's Report during the period 7- Sir-/V to /-3/1-0 , and state that described to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Commissions NB7741, I,N, IS, A WIS 100024 sector's gnature National Board, State, Province, and Endorsements Date * -- *. 20 V

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI Date 11/9/2001

1. Owner Wisconsin Public Service Corporation Sheet 1 of 2 700 North Adams P.O.Box 19001 Green Bay. WI 54307-9001 Unit No. 1
2. Plant Kewaunee Nuclear Power Plant Work Order 01-016342 N490 HWY 42 Kewaunee, WI 54216-9511 Type Code Sym. Stamp NA
3. Work Performed By Nuclear Management Company, LLC Authorization No. NA 700 First Street, Hudson, Wisconsin 54016 Expiration Date NA
4. Identification of System 33 Class 1 SAFETY INJECTION Code Case NA
5. (a) Applicable Construction Code B31.1-1967 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989
6. Identification of Components Repaired or Replaced and Replacement Components Kepalrea, R~epaired, ASME Code National Other Year Replaced, or Name of Name of Manufacturer Stamped Serial No. Board No. ID Built Replacement Component Manufacturer 1967 REPAIRED N TEXAS PIPE NA NA NA 1967 REPAIRED N Sl-W6S BENDING
7. Description of Work REPAIR BY LIGHT FILING CLASS 1 SAFETY INJECTION SYSTEM 2" SOCKET WELD SI-W6S DUE TO LINEAR INDICATION.

Pneumatic

8. Tests conducted Hydrostatic D-1 Nominal Operating Pressure E]7 Exempt deg. F Other E] Pressure psi Test Temp.
9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back) Sheet 2 of 2 Date: 11/9/2001 Name of Component: Sl-W6S Work Order Number: 01-016342 Certificate of Compliance We Certify that the statements made in the report are correct and this REPAIRED conforms to the rules of the ASME Code Section XI. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed d & I~vkt J.MN44#l 6&4nMNCul.hypAU Date  ! ,20 

                                                                                                                        .      *L Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Ins. Co. of Hartford, CT have inspected the components described in the Owner's Report during the period 7-,.ZS-Ov             to /-31-0;L, 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 with the requirements of the ASME Code, Section X1.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 74nsp

  • Commissions NB7741, I,N, IS, A WIS 100024 ectorsvignature National Board, State, Province, and Endorsements Date '20 OC--

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI

1. Owner Wisconsin Public Service Corporation Date 12/3/2001 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Sheet I of 2 Unit No. 1
2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee, WI 54216-9511 Work Order 01-016448 Type Code Sym. Stamp NAA
3. Work Performed By Nuclear Management Company, LLC 700 First Street, Hudson, Wisconsin 54016 Authorization No. NA
4. Identification of System 36 Class 1 REACTOR COOLANT Expiration Date NA
5. (a) Applicable Construction Code ASME III CLASS A Code Case NA (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989
6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Name of Name of Manufacturer National Other Year Replaced, or Code Component Manufacturer Serial No. Board No. ID Built Replacement Stamped WESTINGHOUSE 1151 68-23 00041 1968 REPLACEMENT Y PZR
7. Description of Work REPAIR CLASS 1 REACTOR COOLANT SYSTEM PRESSURIZER MANWAY INCLUDING REPLACING 7 BOLTS.

Nominal Operating Pressure =V

8. Tests conducted Hydrostatic Exempt 1 F Pneumatic [l Other D] Pressure 2240 psi Test Temp. [551 deg. F
9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back) Sheet 2 of 2 Date: - 12/3/2001 Name of Component: PZR Work Order Number: 01-016448 Certificate of Compliance We Certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code Section XI. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed /(Y4* /3AUA 'JMOMKLb I" O*A) Date L 4 ,20 06 Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Ins. Co. of Hartford, CT have inspected the components described in the Owner's Report during the period 14S-$%OD to /-/-3 2, 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 with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, conceming the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Commissions NB7741, I,N, IS, A WIS 100024 ature National Board, State, Province, and Endorsements Date -20 A,7-

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI Date 11/26/2001

1. Owner Wisconsin Public Service Corporation 700 North Adams P.O.Box 19001 Green Bay, Wl 54307-9001 Sheet 1 of 2 Unit No. 1
2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee, Wl 54216-9511 Work Order 01-016564 Type Code Sym. Stamp NA
3. Work Performed By Nuclear Management Company, LLC 700 First Street, Hudson, Wisconsin 54016 Authorization No. NA
4. Identification of System 36 Class 1 REACTOR COOLANT Expiration Date NA
5. (a) Applicable Construction Code B31.1-1967 Code Case NA (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989
6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Name of Name of Manufacturer National Other Year Replaced, or Code Serial No. Board No. ID Built Replacement Stamped Component Manufacturer RC-H9 ITT GRINNELL VALVE NA NA NA 1967 REPLACEMENT N COMPANY
7. Description of Work REPLACED CLASS 2 REACTOR COOLANT SYSTEM 6" HANGER RC-H9 TAIL ROD AND MODIFIED SUPPORT DUE TO DEFORMED SWAY STRUT.

Exempt [*]

8. Tests conducted Hydrostatic LI Pneumatic r* Nominal Operating Pressure E]

Other -- Pressure psi Test Temp. deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back) Sheet 2 of 2 Date: .11/26/2001 Name of Component: RC-H9 Work Order Number: 01-016564 Certificate of Compliance We Certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code Section X1. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 79J .T. ,M 1 t n ) i kl*-A' Date 20 0 Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Ins. Co. of Hartford, CT have inspected the components described in the Owner's Report during the period 7oAS'-O") to /-3/-2*, 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 with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

               .                   .Commissions                                  NB7741, I, N, IS, A   WIS 100024 National Board, State, Province, and Endorsements 61      Inspeco Signature Date                           /           20  _   _    _

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section Xl Date 10/29/2001

1. Owner Wisconsin Public Service Corporation Sheet 1 of 2 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Unit No. 1
2. Plant Kewaunee Nuclear Power Plant Work Order 01-016566 N490 HWY 42 Kewaunee, WI 54216-9511 Type Code Sym. Stamp NA
3. Work Performed By Nuclear Management Company, LLC 700 First Street, Hudson, Wisconsin 54016 Authorization No. NA Expiration Date NA
4. Identification of System 33 Class 2 SAFETY INJECTION Code Case NA
5. (a) Applicable Construction Code B31.1-1967 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989
6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME National Other Year Replaced, or Code Name of Name of Manufacturer Board No. ID Built Replacement Stamped Component Manufacturer Serial No.

N RSI-H80 ITT GRINNELL VALVE NA NA NA 1967 REPAIRED N COMPANY

7. Description of Work REPAIR CLASS 2 SAFETY INJECTION SYSTEM 2" HANGER RSI-H80 DUE TO LOOSE NUT ON PIPE CLAMP BOLT.
8. Tests conducted Hydrostatic I- Pneumatic LI Nominal Operating Pressure D1 Exempt El Pressure psi Test Temp. deg. F Other F
9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back) Sheet 2 of 2 Date: .10/29/2001 Name of Component: RSI-H80 Work Order Number: 01-016566 Certificate of Compliance REPAIRED conforms to the rules of the We Certify that the statements made in the report are correct and this ASME Code Section XI. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 7*L*!X- C. Date m ,20 Q Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION Vessel Inspectors I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Ins. Co. of Hartford, CT and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and "7-.'2io0 to /'tZ, and state that have inspected the components described in the Owner's Report during the period corrective measures described to the best of my knowledge and belief, the Owner has performed examinations and taken in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. or implied, conceming By signing this certificate neither the Inspector nor his employer makes any warranty, expressed neither the Inspector nor the examinations and corrective measures described in this Owner's Report. Furthermore, of any kind arising his employer shall be liable in any manner for any personal injury or property damage or a loss from or connected with this inspection.

1. -' Commissions NB7741, I,N, IS, A WIS 100024
  • nature National Board, State, Province, and Endorsements Inspector's Date / ,20 OX.

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI Date 12/5/2001

1. Owner Wisconsin Public Service Corporation Sheet 1 of 2 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Unit No. 1
2. Plant Kewaunee Nuclear Power Plant Work Order 01-016713 N490 HWY 42 Kewaunee, WI 54216-9511 Type Code Sym. Stamp N.A.
3. Work Performed By Nuclear Management Company, LLC 700 First Street, Hudson, Wisconsin 54016 Authorization No. NA Expiration Date NA
4. Identification of System 05A Class 2 FEEDWATER Code Case NA
5. (a) Applicable Construction Code B31.1-1967 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989
6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Repaired, ASME Manufacturer National Other Year Replaced, or Code Name of Name of Board No. ID Built Replacement Stamped Component Manufacturer Serial No.

NF NA FO13-002 1972 REPAIRED N FW-80B ROCKWELL INTERNATIONAL

7. Description of Work REPAIR BY GRINDING LINEAR INDICATIONS ON CLASS 2 FEEDWATER SYSTEM 1" VENT VALVE FW-80B NOZZLE I.D. INCLUDING REMOVING EXISTING 1" NOZZLE AND REPLACING WITH 1.9" DIAMETER NOZZLE.
8. Tests conducted Hydrostatic l Pneumatic Nominal Operating Pressure 1:1 Exempt Pressure psi Test Temp. deg. F Other n
9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back) Sheet 2 of 2 Date: 12/5/2001 Name of Component: FW-80B Work Order Number: 01-016713 Certificate of Compliance We Certify that the statements made in the report are correct and this REPAIRED conforms to the rules of the ASME Code Section XI. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed e . & A th Oa4L Title T?.WMA.-/u Date ,20 bl,, Owner or Owner's Designee, Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Ins. Co. of Hartford, CT have inspected the components described in the Owner's Report during the period '7-';'P-" to /- 31-0 X , 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 with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 

                                     '""-                        Commissions     NB7741, I, N, IS, A    WIS 100024 Inspector's     gnature                                          National Board, State, Province, and Endorsements Date                           /           20  ___.

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI Date 12/4/2001

1. Owner Wisconsin Public Service Corporation Sheet 1 of 2 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Unit No. 1
2. Plant Kewaunee Nuclear Power Plant Work Order 01-016714 N490 HWY 42 Kewaunee. WI 54216-9511 Type Code Sym. Stamp NA
3. Work Performed By Nuclear Management Company, LLC Authorization No. NA 700 First Street, Hudson, Wisconsin 54016 Expiration Date NA
4. Identification of System 05A Class 2 FEEDWATER Code Case NA
5. (a) Applicable Construction Code B31.1-1967 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989
6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASM Repaired, ASME Code Other Year Replaced, or Name of Name of Manufacturer National Stamped Board No. ID Built Replacement Component Manufacturer Serial No.

1972 REPAIRED N ROCKWELL NF NA F013-001 1972 REPAIRED N FW-80A INTERNATIONAL NOZZLE I.D.

7. Description of Work REPAIR BY GRINDING LINEAR INDICATIONS ON CLASS 2 FEEDWATER SYSTEM 1" VENT VALVE
8. Tests conducted Hydrostatic -

Pneumatic Nominal Operating Pressure D: Exempt [*] psi Test Temp. deg. F Other R Pressure

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back) Sheet 2 of 2 Date: 12/4/2001 Name of Component: FW-80A Work Order Number: 01-016714 Certificate of Compliance We Certify that the statements made in the report are correct and this REPAIRED conforms to the rules of the ASME Code Section XL. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed20 Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Ins. Co. of Hartford, CT have inspected the components described in the Owner's Report during the period TS"- to l-J,/3 - 2., 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 with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. S.Commissions NB7741, I,N, IS, A WIS 100024 Inspectis Signature National Board, State, Province, and Endorsements Date / 20 0_2-

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section Xl Date 12/4/2001

1. Owner Wisconsin Public Service Corporation Sheet 1 of 2 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Unit No. 1
2. Plant Kewaunee Nuclear Power Plant Work Order 01-016715 N490 HWY 42 Kewaunee, WI 54216-9511 Type Code Sym. Stamp NA
3. Work Performed By Nuclear Managqement Company, LLC 700 First Street, Hudson, Wisconsin 54016 Authorization No. NA Expiration Date NA
4. Identification of System 05A Class 2 FEEDWATER Code Case NA
5. (a) Applicable Construction Code B31.1-1967 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989
6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Name of Manufacturer National Other Year Replaced, or Code Name of Serial No. Board No. ID Built Replacement Stamped Component Manufacturer FW-W55BC TEXAS PIPE 356469 NA NA 1969 REPAIRED N BENDING
7. Description of Work REPAIR BY GRINDING, INDICATIONS ON CLASS 2 FEEDWATER SYSTEM 8" AUXILIARY FEEDWATER NOZZLE I.D.
8. Tests conducted Hydrostatic F] Pneumatic D Nominal Operating Pressure El Exempt El Other 1"- Pressure psi Test Temp. deg. F
9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back) Sheet 2 of 2 Date: 12/4/2001 Name of Component: FW-W55BC Work Order Number: 01-016715 Certificate of Compliance REPAIRED conforms to the rules of the We Certify that the statements made in the report are correct and this Repair or Replacement ASME Code Section XI. Type Code Symbol Stamp NA NA Expiration Date NA Certificate of Authorization No. Signed AQ.---TWA Date ,20 O.*_ Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION Boiler and Pressure Vessel Inspectors I, the undersigned, holding a valid commission issued by the National Board of Boiler Inspection and Ins. Co. of Hartford, CT and the State or Province of Wisconsin and employed by Hartford Steam 

                                                                                           ,1-X-0'?     to /-3fr-PZ , and state that have inspected the components described in the Owner's Report during the period and taken corrective measures described to the best of my knowledge and belief, the Owner has performed examinations Section XL.

in this Owner's Report in accordance with the requirements of the ASME Code, warranty, expressed or implied, concerning By signing this certificate neither the Inspector nor his employer makes any Furthermore, neither the Inspector nor the examinations and corrective measures described in this Owner's Report. damage or a loss of any kind arising his employer shall be liable in any manner for any personal injury or property from or connected with this inspection. Commissions NB7741, I,N, IS, A WIS 100024 nspector'sSi nature National Board, State, Province, and Endorsements Date / 20 OP

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI Date 11/1/2001

1. Owner Wisconsin Public Service Corporation Sheet 1 of 2 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Unit No. 1
2. Plant Kewaunee Nuclear Power Plant Work Order 01-016849 N490 HWY 42 Kewaunee, WI 54216-9511 Type Code Sym. Stamp NA
3. Work Performed By Nuclear Management Company. LLC 700 First Street, Hudson. Wisconsin 54016 Authorization No. NA Expiration Date NA
4. Identification of System 36 Class 1 REACTOR COOLANT Code Case NA
5. (a) Applicable Construction Code B31.1-1967 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989
6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Repaired, ASME National Other Year Replaced, or Code Name of Name of Manufacturer Stamped Serial No. Board No. ID Built Replacement Component Manufacturer REPAIRED N RCVC-H48 ITT GRINNELL VALVE NA NA NA 1967 REPAIRED N COMPANY
7. Description of Work REPAIR CLASS 1 REACTOR COOLANT SYSTEM 2" HANGER RCVC-H48 DUE TO LOOSE NUT ON THE CLEVIS BOLT.
8. Tests conducted Hydrostatic Pneumatic r Nominal Operating Pressure F"] Exempt El psi Test Temp. deg. F Other 1-D Pressure
9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back) Sheet 2 of 2 Date: " 11/1/2001 Name of Component: RCVC-H48 Work Order Number: 01-016849 Certificate of Compliance We Certify that the statements made in the report are correct and this REPAIRED conforms to the rules of the ASME Code Section XI. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed -"% , Date 20 6. Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Ins. Co. of Hartford, CT have inspected the components described in the Owner's Report during the period 7-4.'-r'O to /-3/-12 , 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 with the requirements of the ASME Code, Section Xl. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Commissions NB7741, I, N, IS, A WIS 100024 pect Signature National Board, State, Province, and Endorsements Date 20 ,,,2.-

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI Date 11/1/2001

1. Owner Wisconsin Public Service Corporation Sheet 1 of 2 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Unit No. 1
2. Plant Kewaunee Nuclear Power Plant Work Order 01-016849 N490 HWY 42 Kewaunee, WI 54216-9511 Type Code Sym. Stamp NA
3. Work Performed By Nuclear Management Company, LLC Authorization No. NA 700 First Street, Hudson, Wisconsin 54016 Expiration Date NA
4. Identification of System 36 Class 1 REACTOR COOLANT Code Case NA
5. (a) Applicable Construction Code B31.1-1967 (b) Applicable Edition of Section X1 Utilized for Repairs or Replacements 1989
6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Repaired, ASME Other Year Replaced, or Code Name of Name of Manufacturer National Stamped Serial No. Board No. ID Built Replacement Component Manufacturer REPAIRED N RCVC-H49 ITT GRINNELL VALVE NA NA NA 1967 REPAIRED N COMPANY
7. Description of Work REPAIR CLASS 1 REACTOR COOLANT SYSTEM 2" HANGER RCVC-H49 DUE TO LOOSE NUT ON THE UPPER SPRING CAN SUPPORT.
8. Tests conducted Hydrostatic FI Pneumatic -- I Nominal Operating Pressure n- Exempt E]

Other L] Pressure psi Test Temp. deg. F

9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back) Sheet 2 of 2 Date: " 11/1/2001 Name of Component: RCVC-H49 Work Order Number: 01-016849 Certificate of Compliance We Certify that the statements made in the report are correct and this REPAIRED conforms to the rules of the ASME Code Section XI. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed Q:)A* 7- ed t4 Date _h ,20 _. Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors Hartford, CT and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Ins. Co. of to /-31-19 , and state that have inspected the components described in the Owner's Report during the period 7-ASrtZ described to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures in this Owner's Report in accordance with the requirements of the ASME Code, Section XL. concerning By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, Inspector nor the examinations and corrective measures described in this Owner's Report. Furthermore, neither the arising his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind from or connected with this inspection. Commissions NB7741, I,N, IS, A WIS 100024 IFns ' i r National Board, State, Province, and Endorsements Dtspector's .2n___re Date "* -- *-JJ/ 20 O*

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI

1. Owner Wisconsin Public Service Corporation Date 12/3/2001 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Sheet 1 of 2 Unit No. 1
2. Plant Kewaunee Nuclear Power Plant N490 HWY 42 Kewaunee, WI 54216-9511 Work Order 01-016851 Type Code Sym. Stamp NA
3. Work Performed By Nuclear Management Company, LLC 700 First Street, Hudson, Wisconsin 54016 Authorization No. NA
4. Identification of System 33 Class 1 SAFETY INJECTION Expiration Date NA
5. (a) Applicable Construction Code B16.5-1967 Code Case NA (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989
6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME Name of Name of Manufacturer National Other Year Replaced, or Code Component Manufacturer Serial No. Board No. ID Built Replacement Stamped SI-304B VELAN VALVE NF NA S1116-006 1967 REPLACEMENT N CORPORATION
7. Description of Work SEAL WELD BODY TO BONNET ON CLASS 1 SAFETY INJECTION SYSTEM 6" VALVE SI-304B DUE TO BODY TO COVER LEAK INCLUDING REPLACEMENT OF 3 VALVE BONNET STUDS.

Exempt

8. Tests conducted Hydrostatic D-1 Pneumatic 1 Nominal Operating Pressure E Other D Pressure 2240 psi Test Temp. 551 deg. F
9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back) Sheet 2 of 2 Date: ' 12/3/2001 Name of Component: SI-304B Work Order Number: 01-016851 Certificate of Compliance We Certify that the statements made in the report are correct and this REPLACEMENT conforms to the rules of the ASME Code Section XI. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed 19X"A./'fP/

  • fMM"*Z
                                                                      *W1'I*                Date                4        20 Title Owner or Owner's Designee, Certificate of INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Wisconsin and employed by Hartford Steam Boiler Inspection and Ins. Co. of Hartford, CT have inspected the components described in the Owner's Report during the period 7- 24,*OV             to / 0 2., and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Commissions NB7741, I,N, IS, A WIS 100024 4spodignature National Board, State, Province, and Endorsements Date / ,20 -,1-

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENT As Required by the Provisions of the ASME Code Section XI Date 11/23/2001

1. Owner Wisconsin Public Service Corporation Sheet 1 of 2 700 North Adams P.O.Box 19001 Green Bay, WI 54307-9001 Unit No. 1
2. Plant Kewaunee Nuclear Power Plant Work Order 01-016868 N490 HWY 42 Kewaunee. WI 54216-9511 Type Code Sym. Stamp NAA
3. Work Performed By Nuclear Management Company, LLC Authorization No. NA 700 First Street, Hudson, Wisconsin 54016 Expiration Date NA
4. Identification of System 33 Class 2 SAFETY INJECTION Code Case NA
5. (a) Applicable Construction Code B16.5-1967 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989
6. Identification of Components Repaired or Replaced and Replacement Components Repaired, AMI Repairedl,or ASME Code Other Year Replaced, Name of Name of Manufacturer National Stamped Board No. ID Built Replacement Manufacturer Serial No.

Component N S1009-001 1970 IPAIU SI-5A ANCHOR VALVE 9193-3/70 NA S1009-001 1970 RE PAIRED.L IN COMPANY STEM.

7. Description of Work OPEN FOR REPAIR CLASS 2 SAFETY INJECTION SYSTEM 6" VALVE SI-5A TO REPLACE DAMAGED
8. Tests conducted Hydrostatic Pneumatic r] Nominal Operating Pressure E Exempt L' Other n Pressure 10 psi Test Temp. LO deg. F
9. Remarks NOT APPLICABLE.

Applicable Manufacturer's Data Reports to be Attached

NIS-2 (Back) Sheet 2 of 2 Date: 11/23/2001 Name of Component: SI-5A Work Order Number: 01-016868 Certificate of Compliance REPAIRED conforms to the rules of the We Certify that the statements made in the report are correct and this ASME Code Section XI. Repair or Replacement Type Code Symbol Stamp NA Certificate of Authorization No. NA Expiration Date NA Signed )ODeW__* e. 6A .*,* * 'Ln Date 6 n 20 0_.. Owner or Owner's Designee, Title Certificate of INSERVICE INSPECTION Vessel Inspectors I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Inspection and Ins. Co. of Hartford, CT and the State or Province of Wisconsin and employed by Hartford Steam Boiler period '7-4?,5ov to /-3 (-O Z , and state that have inspected the components described in the Owner's Report during the and taken corrective measures described to the best of my knowledge and belief, the Owner has performed examinations Section Xl. in this Owners Report in accordance with the requirements of the ASME Code, expressed or implied, concerning By signing this certificate neither the Inspector nor his employer makes any warranty, Furthermore, neither the Inspector nor the examinations and corrective measures described in this Owner's Report. or a loss of any kind arising his employer shall be liable in any manner for any personal injury or property damage from or connected with this inspection. Alnsp-- Commissions NB7741, I,N, IS, A WIS 100024 ignature National Board, State, Province, and Endorsements Inspector's Date --* *,20 / 0 2-

ATTACHMENT 7 Letter from T. Coutu (NMC) To Document Control Desk (NRC) Dated February 22, 2002 Examination Summary for Scheduled and Augmented Inservice Inspection (ISI) Program

NUCLEAR MANAGEMENT COMPANT, LLC KEWAUNEE NUCLEAR POWER PLANT 3RD INTERVAL: 3RD PERIOD: 1ST OUTAGE 2001 EXAMINATION

SUMMARY

INTRODUCTION An Inservice Inspection (ISI) Program (Scheduled and Augmented) was performed at the Kewaunee Nuclear Power Plant from March 27, 2001 through September 12, 2001 (Non Refueling Outage), September 19, 2001 through December 4, 2001 (Closing of G1 following Refueling Outage) and December 6, 2001 by Kewaunee Nuclear Power Plant and Lambert, MacGill, and Thomas, Inc.(LMT) examination personnel. Examinations were performed to satisfy the requirements of: "*ASME Boiler and Pressure Vessel Code Section XI 1989 Edition "*ASME Boiler and Pressure Vessel Code Section XI 1995 Edition 1996 Addenda Appendix VIII Performance Demonstration for Ultrasonic Examination Systems as required by Code of Federal Regulations 10CFR50.55 a(g)(6)(ii)(c) and Nuclear Regulatory Commission 10CFR Part 50 Federal Register/Vol.64, Number 183/September 22, 1999/Rules and Regulations "*United States Nuclear Regulatory Commission IE Bulletin 79-13 "*United States Nuclear Regulatory Commission Generic Letter 88-05 The Inservice Inspection Program Plan and Augmented Inspection Program Plan located under Tab C was prepared by Nuclear Management Company, LLC - Kewaunee Nuclear Power Plant for the 3rd Interval: 3rd Period: 1st Outage as identified in the Kewaunee Nuclear Power Plant Third 10-Year Inservice Inspection (ISI) Program 1994-2004. Examinations during this Refueling Outage were performed to start the 3rd Interval: 3rd Period Examination Requirements of ASME Boiler and Pressure Vessel Code Section XI 1989 Edition and Kewaunee Nuclear Power Plant Third 10-Year Inservice Inspection (ISI) Program 1994-2004. The following items were examined: 

"*Reactor Vessel Closure Head Flange Weld
"*Reactor Vessel Closure Head Studs, Nuts ,Washers and Control Rod Drive Mechanisms
"*Pressurizer Circumferential and Longitudinal Welds
 "*Steam Generator Head Circumferential Weld, Nozzle Inside Radius Sections and Nozzle To Shell Weld Page 1 of 5

"*Reactor Coolant Pump Main Flange Bolting and No. 1 Seal Housing Bolting "*Seal Water Injection Filter Shell Circumferential Weld "*Letdown Heat Exchanger Head Circumferential Weld "*Charging Pump Pulsation Dampener Head Circumferential Weld "*Class 1 Valve Bodies "*Class 1 Piping Integrally Welded Attachment "*Class 1 and Class 2 Piping Welds ", Class 2 Safety Injection Pump Casing Weld and Welded Attachments "*Class 2 Piping Integrally Welded Attachments "*Class 1, Class 2 and Class 3 Piping and Component Supports and Hangers "*Class 1 and Class 2 Reactor Vessel Conoseal Bolting, Pressurizer Manway Bolting, Flange Bolting and Valve Bonnet Bolting "*Class 1 System Leakage Test "*Class 2 and Class 3 System Inservice and Functional System Pressure Tests EXAMINATIONS The examinations performed were in accordance with an approved Inservice Inspection Program Plan located under Tab C of the final report. Examination Procedures were approved prior to the start of examinations and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory. Some of the arrangements and details of the Kewaunee Nuclear Power Plant Components and Piping Systems were designed and fabricated before ASME Boiler and Pressure Vessel Code Section XI Code requirements were established. Examinations performed were intended to examine 100% of the required surface or volume. In some cases, examinations were limited by geometric, metallurgical or design/access restrictions. In each case, the occurrence and cause of the limitation was documented. In all cases the maximum amount achievable was examined. Witnessing and surveillance of the examinations were conducted by: Hartford Steam Boiler Inspection and Insurance Company. RESULTS Examinations resulted with the following Recordable Indications being noted on the basis of procedure recording criteria, which are generally more restrictive than specified ASME Boiler and Pressure Vessel Code Section XI Acceptance Standards. Page 2 of 5

Recordable Indications detected during the 2001 Refueling Outage are listed in Table 1 with a brief summary following. Specific data relative to all Recordable Indications and their dispositions by either corrective measures or acceptance by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Acceptance Criteria, Repair/Replacement or Evaluation are located in Tab F of the Final Report. TABLE 1 TYPE OR LOCATION OF RECORDABLE INDICATION (RI) METHOD NO. OF RI'S "*Reactor Vessel Closure Head Flange Weld Surface (MT) 1 Weld "*Steam Generator Circumferential Head Weld Volumetric (UT) 1 Weld "*Seal Water Injection Filter Shell Weld Volumetric (UT) 1 Weld "*Piping Integrally Welded Attachment Surface (PT) 1 Weld "*Piping Circumferential Butt Weld Surface (PT) 1 Weld "*Piping Socket Weld Surface (PT) 1 Weld "*Reactor Vessel Conoseal Bolting Visual (VT-3) 1 Conoseal "*RC Pump No. 1 Seal Housing Bolting Visual (VT-1) 1 Pump "*Pressurizer Manway Bolting Visual (VT-3) 1 Manway "*Component Supports and Hangers Visual (VT-3) 31 Supports "*Valve Bonnet Bolting Visual (VT- 1) 1 Valve "*Valve Bonnet Bolting Visual (VT-3) 6 Valves "*System Pressure Tests Visual (VT-2) 51 Items

1. A 0.125" Long Linear Indication was recorded on the Reactor Vessel Closure Head Flange Weld RV-W12 during performance of Magnetic Particle Examination. This Linear Indication was Acceptable per ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Table IWB-3510-3.
2. A spot indication on Steam Generator 1B Circumferential Head Weld SG-W9 was recorded during performance of Ultrasonic Examination. This Ultrasonic Spot Indication was Acceptable per ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Table IWC-3510-1.

Page 3 of 5

3. 5 Laminar Indications combined into 4 laminar indications to due proximity of Indications were recorded on Seal Water Injection Filter 1A Circumferential Shell Weld AFSI-W1 during performance of Ultrasonic Examinations. These Laminar Indications were Acceptable per ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Table IWC-3510-2 and were typical of Laminations recorded on Seal Water Injection Filters 1A and 1B during Refueling Outages 1982, 1986, 1988, 1992 and 1998.

4.3 rounded Indications 0.0625", 0.125" and 0.1875" in diameter were recorded on 2" Piping Integrally Welded Attachment RSI-H72 during performance of Liquid Penetrant Examinations. These 3 Rounded Indications were Acceptable per ASME Boiler and Pressure Vessel Code Section III 1989 Edition Section NC-5352(b).

5. A 0.125" long Linear Indication and a 0.125" Rounded Indication were recorded on 6" Circumferential Butt Weld ICS-W43 during performance of Liquid Penetrant Examinations.

The 0.125" Long Linear Indication was Acceptable per ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Table IWB-3514-2. The 0.125" Rounded Indication was Acceptable per ASME Boiler and Pressure Vessel Code Section III 1989 Edition Section NC-5352.

6. A 0.55" long Linear Indication on 2" Socket Weld SI-W6S was recorded during performance of Liquid Penetrant Examinations. This Linear Indication was Unacceptable per ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Table IWB-3514-2. The Linear Indication was removed under Work Order 01-016342 by light filing with a jewelers file, reexamined and Accepted with No Indications.
7. Visual (VT-1, VT-2 and VT-3) Indications recorded on Reactor Vessel Conoseal Bolting, Reactor Coolant Pump No. 1 Seal Housing Bolting, Pressurizer Manway Bolting, Valve Bonnet Bolting, Piping Supports and Hangers and during System Pressure Tests were: (1)

Evaluated and Accepted or (2) Repaired, Reexamined and Accepted by: Nuclear Management Company, LLC - Maintenance, Quality Control, Engineering and Technical Support or Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector. Page 4 of 5

SUMMARY

An Inservice Inspection Program Plan was performed at the Kewaunee Nuclear Power Plant from March 27, 2001 through September 12, 2001 (Non Refueling Outage) and September 19, 2001 through December 4, 2001 (Closing of G1 following Refueling Outage) and December 6, 2001. Examinations were performed as scheduled in the Kewaunee Nuclear Power Plant Third 10-Year Inservice Inspection (ISI) Program 1994-2004 to start examinations for the 3rd Interval; 3rd Period. A total of 98 Recordable Indications were detected. All Recordable Indications were corrected or accepted by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Acceptance Criteria, Repair/Replacement or Evaluation. Phillip E. Bukes Date Engineering and Technical Support Inservice Inspection Program Owner Page 5 of 5

ATTACHMENT 8 Letter from T. Coutu (NMC) To Document Control Desk (NRC) Dated February 22, 2002 Examination Summary for Inservice Inspection (ISI) Class MC Program

NUCLEAR MANAGEMENT COMPANY, LLC KEWAUNEE NUCLEAR POWER PLANT 1ST INTERVAL: 2ND PERIOD: 1ST OUTAGE 2001 EXAMINATION

SUMMARY

INTRODUCTION An Inservice Inspection (ISI) Program for the Class MC Reactor Building Containment Vessel was performed at the Kewaunee Nuclear Power Plant from September 18, 2001 through December 4, 2001 (Closing of G1 following Refueling Outage) by Kewaunee Nuclear Power Plant and Lambert, MacGill and Thomas Inc. examination personnel. Examinations were performed to satisfy the requirements of: - ASME Boiler and Pressure Vessel Code Section XI 1992 Edition up to and including 1992 Addenda The Inservice Inspection Program Plan located under Tab C was prepared by Nuclear Management Company, LLC - Kewaunee Nuclear Power Plant for the 1st Interval: 2nd Period: 1st Outage as identified in the Kewaunee Nuclear Power Plant First 10-Year Inservice Inspection (ISI) Program 1996-2006. The following items were examined for the Class MC Reactor Building Containment Vessel: 

  "*Accessible Surface Areas
  "*Longitudinal Welds and Circumferential Welds
  "*Sleeve to Bellows Welds
  "*Flange Welds
  "*Seals and Gaskets
  "*Moisture Barriers
  "*Dissimilar Metal Welds
  "*Bolted Connections
  "*Containment Penetration Bellows
  "*Airlocks EXAMINATIONS The examinations performed were in accordance with an approved Inservice Inspection Program Plan located under Tab C of the final report. Examination Procedures were approved Page 1 of 3

prior to the start of examinations and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory. Some of the arrangements and details of the Kewaunee Nuclear Power Plant Components and Piping Systems were designed and fabricated before ASME Boiler and Pressure Vessel Code Section XI Code requirements were established. Examinations performed were intended to examine 100% of the required surface or volume. In some cases, examinations were limited by geometric, metallurgical or design/access restrictions. In each case, the occurrence and cause of the limitation was documented. In all cases the maximum amount achievable was examined. Witnessing and surveillance of the examinations were conducted by: Hartford Steam Boiler Inspection and Insurance Company. RESULTS Examinations resulted with the following Recordable Indications being noted on the basis of procedure recording criteria, which are generally more restrictive than specified ASME Boiler and Pressure Vessel Code Section XI Acceptance Standards. Recordable Indications detected during the 2001 Refueling Outage are listed in Table 1 with a brief summary following. Specific data relative to all Recordable Indications and their dispositions by either corrective measures or acceptance by ASME Boiler and Pressure Vessel Code Section XI 1992 Edition up to and including 1992 Addenda Acceptance Criteria, Repair/Replacement or Evaluation are located in Tab F of the Final Report. TABLE 1 TYPE OR LOCATION OF RECORDABLE INDICATION (RI) METHOD NO. OF RI'S Reactor Building Containment Vessel General Visual 11 Plates Reactor Building Containment Vessel VT-3 5 Plates Moisture Barriers Reactor Building Containment Vessel VT-i 1 Bolt Emergency Airlock Page 2 of 3

1. General Visual Indication consisting of a 4" x 8" Surface Defect was recorded on Plate 155. This Surface Defect was previously recorded and accepted in 1998 and showed no change in dimension or surface condition during the 2001 Refueling Outage.
2. General Visual Indication consisting of a slight inward bulge on Plates 74, 75 and 83 was recorded. The slight inward bulge was evaluated by Engineering and Accepted under Kewaunee Nuclear Power Plant Specification TS-1052, Addendum No. 4, Item No. 19 Section 10.3 - Shell Tolerance.
3. General Visual Indication consisting of slight Outward Bulges on Plates 144, 145, 146, 147 and 148 were recorded. The slight Outward Bulges were evaluated and Accepted by Engineering Analysis.
4. General Visual Indications consisting of Weld Deposits on Plate 62 and Arc Strikes on Plate 99 were recorded and are Acceptable per ASME Boiler and Pressure Vessel Code Section XI 1992 Edition 1992 Addenda.
5. VT-3 Indications consisting of Lack of Bonding and Tears were recorded in the Moisture Barriers on Plates 62, 64, 65, 66 and 67 and were repaired under Work Order 01-018045.
6. A VT-1 Indication on an Emergency Airlock Bolt was recorded and was repaired under Work Order 01-018283.

SUMMARY

An Inservice Inspection Program for the Class MC Reactor Building Containment Vessel was performed at the Kewaunee Nuclear Power Plant from September 18, 2001 through December 4, 2001 (closing of GI following Refueling Outage). Examinations were performed as scheduled in the Kewaunee Nuclear Power Plant First 10-Year Inservice Inspection (ISI) Program 1996-2006. A total of 17 Recordable Indications were detected. All Recordable Indications were corrected and accepted by: ASME Boiler and Pressure Vessel Code Section XI 1992 Edition up to and including 1992 Addenda Acceptance Criteria, Repair/Replacement, Evaluation or Kewaunee Nuclear Power Plant Technical Specifications. Phillip E. Bukes Date Engineering and Technical Support Inservice Inspection Program Owner Page 3 of 3

ATTACHMENT 9 Letter from T. Coutu (NMC) To Document Control Desk (NRC) Dated February 22, 2002 Examination Summary for Preservice Inspection (PSI) of Steam Generators

NUCLEAR MANAGEMENT COMPANY, LLC KEWAUNEE NUCLEAR POWER PLANT REPLACEMENT STEAM GENERATORS PRESERVICE INSPECTION EXAMINATION

SUMMARY

3RD INTERVAL: 3RD PERIOD: 1ST OUTAGE 2001 INTRODUCTION A Preservice Inspection (PSI) was performed at the Kewaunee Nuclear Power Plant on the Replacement Steam Generators 1) in the Steam Generator Storage Building from June 5, 2001 through June 26, 2001 and 2) during installation in conjunction with the 2001 Refueling Outage from September 19, 2001 through December 4, 2001 (Closing of G1 following Refueling Outage) by Kewaunee Nuclear Power Plant and Lambert, MacGill, and Thomas, Inc. (LMT) examination personnel. Examinations were performed to satisfy the requirements of: "*ASME Boiler and Pressure Vessel Code Section XI 1989 Edition "*ASME Boiler and Pressure Vessel Code Section XI 1995 Edition 1996 Addenda Appendix VIII Performance Demonstration for Ultrasonic Examination Systems as required by Code of Federal Regulations 10CFR50.55a(g)(6)(ii)(c) and Nuclear Regulatory Commission 10CFR Part 50 Federal Register/Vol.64, Number 183/Septemeber 22, 1999/Rules and Regulations "*Kewaunee Nuclear Power Plant Nuclear Regulatory Commission Commitment Tracking No.95-046 "*Kewaunee Nuclear Power Plant Augmented Program for examinations performed in conjunction with Steam Generator Replacement Activities The Preservice Inspection Program Plan and Augmented Inspection Program Plan located under Tab C was prepared by Nuclear Management Company, LLC Kewaunee Nuclear Power Plant for the 3rd Interval: 3rd Period: 1st Outage and as identified in the Kewaunee Nuclear Power Plant Third 10-Year Inservice Inspection (ISI) Program 1994-2004. The following items were examined:

  • Replacement Steam Generators: Tubesheet to Head Welds, Nozzle Inside Radius Sections, Nozzle to Safe End Butt Welds, Primary Side Manway Bolting, Integrally Welded Attachments, Shell Circumferential Welds, Tubesheet to Shell Welds and Class 1 Support Components
  • New Class 1 Reactor Coolant Piping Welds Page 1 of 5

"*New and Replacement Class 2 Main Steam and Feedwater Piping Welds "*Reexamination of Existing Steam Generator Circumferential Welds SG-W2 and SG-Wl0 to verify previously recorded Ultrasonic Planar Indications "*Existing 16", 8" and 1" Feedwater Inside Diameter Surfaces "*Existing Steam Generator Inside Diameter Feedwater Nozzle Inner Radius and Shell Circumferential Welds "*Existing Steam Generator Class 2 Supports EXAMINATIONS The examinations performed were in accordance with an approved Preservice Inspection Program Plan located under Tab C of the final report. Examination Procedures were approved prior to the start of examinations and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory. Some of the arrangements and details of the Kewaunee Nuclear Power Plant Components and Piping Systems were designed and fabricated before ASME Boiler and Pressure Vessel Code Section XI Code requirements were established. Examinations performed were intended to examine 100% of the required surface or volume. In some cases, examinations were limited by geometric, metallurgical or design/access restrictions. In each case, the occurrence and cause of the limitation was documented. In all cases the maximum amount achievable was examined. Witnessing and surveillance of the examinations were conducted by: Hartford Steam Boiler Inspection and Insurance Company. Surveillance of the examinations were conducted by: United States Nuclear Regulatory Commission. RESULTS Examinations resulted with the following Recordable Indications being noted on the basis of procedure recording criteria, which are generally more restrictive than specified ASME Boiler and Pressure Vessel Code Section XI Acceptance Standards. Recordable Indications detected during the 2001 Refueling Outage are listed in Table 1 with a brief summary following. Specific data relative to all Recordable Indications and their dispositions by either corrective measures or acceptance by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Acceptance Criteria, Repair/Replacement or Evaluation are located in Tab F of the Final Report. Page 2 of 5

TABLE 1 TYPE OR LOCATION OF RECORDABLE INDICATION (RI) METHOD NO. OF RI'S 

"*Replacement Steam Generator Integrally             Surface (MT)                        1 Weld Welded Attachment SG-1B-23B

"*Replacement Steam Generator Tubesheet Volumetric (UT) 1 Weld To Head Weld SG-W32 "*Replacement Steam Generator Primary Visual (VT-1) 1 Stud Side Manway SG-lB-CLMWB "*Replacement Steam Generator Tubesheet Volumetric (UT) 1 Weld To Shell Weld SG-W31 "*Existing Steam Generator Feedwater Surface (MT) 1 Nozzle Nozzle Inner Radius SG-IR8 "*Existing Steam Generator Feedwater Surface(MT) & Visual (VT-1) 1 Nozzle Nozzle Inner Radius SG-IR 16 "*Existing Steam Generator Circumferential Volumetric (UT) 2 Welds Welds SG-W2 and SG-W10 "*Existing 16", 8" and 1" Feedwater Piping Surface (MT) 1 ID Section FW-W27BC "*Existing 16", 8" and 1" Feedwater Piping Surface (MT) & Visual (VT-1) 1 ID Section FW-W55BC

1. Two separate linear indications on Replacement Steam Generator lB Integrally Welded Attachment SG-1B-23B were recorded during performance of Magnetic Particle Examinations. These two linear indications due their close proximity to each other were classified as one Linear indication with a length of 0.21875". This linear indication was Acceptable per ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Sections IWB-3516.1, IWB-3510.3 and IWB-3510-3.
2. Ultrasonic Recordable Indications at 3 separate locations on Replacement Steam Generator 1B Tubesheet to Head Weld SG-W32 were noted during performance of Manual Ultrasonic Examinations. These 3 separate Planar Indications were Acceptable per ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Table IWB-3510-1.
3. One Visual Indication was recorded by the VT-1 method on Replacement Steam Generator lB Primary Side Manway Stud SG-1B-CLMWB #17. Although this Primary Manway Stud was Acceptable per ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Section IWB 3517. l(b), a new VT-1 Acceptable Replacement Stud was installed.

Page 3 of 5

4. Ultrasonic Recordable Indication at one location on Replacement Steam Generator 1B Tubesheet to Shell Weld SG-W31 was noted during performance of Manual Ultrasonic Examination. This Planar Indication was Acceptable per ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Table IWC-3510-1.
5. Recordable Indications on the Existing Steam Generator 1B Feedwater Nozzle Inside Radius Section SG-IR8 were recorded during Augmented Examination by Magnetic Particle. These Indications were repaired by Bechtel Corporation under Bechtel's NCR's and Kewaunee Nuclear Power Plant Work Orders as part of Replacement Steam Generator Activities.
6. Recordable Indications on the Existing Steam Generator 1A Feedwater Nozzle Inside Radius Section SG-IR16 were recorded during Augmented Examinations by Magnetic Particle and Visual (VT-1) Methods. These Indications were repaired by Bechtel Corporation under Bechtel's NCR's and Kewaunee Nuclear Power Plant Work Orders as part of Replacement Steam Generator Activities.

7 & 8. Prior to severing the Existing Steam Generators and following welding the Replacement Steam Generators to the Existing Steam Generators a Manual Ultrasonic Examination was performed on existing Circumferential Shell Welds SG-W2 and SG-W1O to insure that there was no growth in the previously recorded planar indications. These Indications were recorded in 1991 for SG-W2 and in 1991 and 1996 for SG-WlO. All indications previously recorded as well as new indications recorded do to amplitude recording criteria change were Acceptable either by ASME Boiler and Pressure Vessel Code Section XI 1989 Acceptance Standards or by Fracture Analysis as provided in Westinghouse Electric Corporation WCAP 11476 Rev. 3 Handbook on Flaw Evaluation Kewaunee Unit 1 Steam Generator Upper Shell To Cone Weld, May 1991 and evaluation by Kewaunee Nuclear Power Plant during 1996 and 2001 Refueling Outages.

9. Recordable Indications on Loop A Existing 16", 8" and 1" Feedwater Piping ID Surface for FW-W27BC were recorded during Augmented Magnetic Particle examinations. These indications were repaired by Bechtel Corporation under Kewaunee Nuclear Power Plant Work Orders generated during Steam Generator Replacement Activities.
10. Recordable Indications on Loop B Existing 16", 8" and 1" Feedwater Piping ID Surface for FW-W55BC were recorded during Augmented Examinations by Magnetic Particle and Visual (VT-1) Methods. These indications were repaired by Bechtel Corporation under Kewaunee Nuclear Power Plant Work Orders generated during Steam Generator Replacement Activities.

Page 4 of 5

SUMMARY

A Preservice Inspection Program was performed at the Kewaunee Nuclear Power Plant from June 5, 2001 through June 26, 2001 (Non Refueling Outage) and September 19, 2001 through December 4, 2001 (Closing of GI following Refueling Outage). Examinations were performed as scheduled in the Replacement Steam Generator Preservice Inspection Program Plan and Kewaunee Nuclear Power Plant Third 10-Year Inservice Inspection (ISI) Program 1994-2004. A total of 10 Recordable Indications were detected. All Recordable Indications were corrected or accepted by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Acceptance Criteria, Repair/Replacement or Evaluation. Phillip+E.Bukes Date Engineering and Technical Support Inservice Inspection Program Owner Page 5 of 5

ATTACHMENT 10 Letter from T. Coutu (NMC) To Document Control Desk (NRC) Dated February 22, 2002 Examination Summary for Replacement Steam Generator Eddy Current

KEWAUNEE NUCLEAR POWER PLANT REPLACEMENT STEAM GENERATOR PRESERVICE INSPECTION

SUMMARY

REPORT 1.0 Introduction This report provides a summary of inspections performed and the inspection results for the preservice inspection (PSI) of the Kewaunee Nuclear Power Plant (KNPP) replacement steam generators (RSG). The KNPP RSGs were delivered to the Kewaunee site in December 2000. The PSI was performed inside the RSG storage building at the Kewaunee site in January 2001. The RSGs were in a horizontal position during the examination. Personnel from Siemens performed the data acquisition and primary data analysis and Zetec personnel performed the secondary analysis. SG2 (ASME Nameplate NB 0202) was located in the south bay of the RSG storage building and was the first steam generator examined. The PSI depicted SG2 as the "B" steam generator. SG1 (ASME Nameplate NB 0201) was located in the north bay of the RSG storage building and was the second steam generator examined. The PSI depicted SGI as the "A" steam generator SG2 (ASME Nameplate NB 0202) will be installed as the "A" steam generator and SGI (ASME Nameplate NB 0201) will be installed as the "B" steam generator. 2.0 RSG PSI Eddy Current Inspection Scope The RSG PSI eddy current examinations included the following:

1. A 100% bobbin coil examination through the entire length of all tubes (3592 tubes/SG).
2. Supplemental +Point rotating coil examinations of ambiguous signals, as required.

3.0 RSG PSI Inspection Results No tubes contained indications in excess of the 50% plugging limit as defined in KNPP Technical Specification 4.2.b.4. No tubes were preventatively plugged. KNPP Technical Specification 4.2.b defines a degraded tube as a tube containing an imperfection > 20% of the nominal tube wall thickness. In addition, TS 4.2.b defines an imperfection as an exception to the dimension, finish, or contour required by drawing or specification. With these definitions, the RSG PSI did not identify any degraded tubes. Some imperfections were identified during the PSI. In SGI, 27

imperfections were reported 25 tubes. In SG2, 18 imperfections were reported in 16 tubes. The locations of the reported imperfections are tabulated and discussed below. KNPP PSI Reported Indications SG1 SG2 Location BLG BMG DNG FSD MBM BMG DNG MBM HL TTS 1 Between 03H and 04H 1 Between 04H and 05H 1 Between 05H and 06H I Between 06H and 07H 1 TSP 07H 2 6 Between 07H and 07C (U-bend) 3 2 1 6 3 TSP 07C 13 1 Between 07C and 06C 1 CL TTS 1 2 3 18 1 3 6 10 2 TOTALS Bulge (BLG) A Bulge is defined as a tube diameter that is greater than nominal. The BLG indications were in 2 initiated during RSG fabrication. In SG1, inspection revealed 2 BLG indications located tubes. Both are located at the top surface of the tubesheet (TTS), one at the hot leg TTS and one at the cold leg TTS. Subsequent inspections with the +Point rotating coil revealed no degradation at either of the BLG locations. There were no BLG indications reported in SG2. Bending Machine Geometry (BMG) In Bending Machine Geometry is defined as a dent-like indication at the u-bend tangent point. row-9 u-bends and 1 SG1, inspection revealed 3 BMG indications in 3 tubes, 2 of which were in row-5 u in a row 16 u-bend. In SG2, inspection revealed 6 BMG indications in 6 tubes (two in and one in a row bends, one in a row-7 u-bend, one in a row-1I u-bend, one in a row-16 u-bend, The tube 22 u-bend). All of the BMG indications were present in the tube mill eddy current data. with bending manufacturing step is the likely source of BMG indications. Subsequent inspections the +Point rotating coil revealed no degradation at any of the BMG locations. Dinz (DNG) 18 A Ding is defined as a tube diameter that is less than nominal. In SGI, inspection revealed in 8 DNG indications located in 16 tubes. In SG2, inspection revealed 10 DNG indications largest reported tubes. The reporting threshold for reporting DNG indications was 2 volts. The

DNG indication was 4.66 volts in SG1 and 5.71 volts in SG2. DNG indications were concentrated in the upper bundle region, primarily at the upper TSP elevations. The DNG indications were not present in the tube mill eddy current data; they were likely initiated during RSG fabrication. Subsequent inspections with the +Point rotating coil revealed no degradation at any of the DNG locations. Free-SpanDifferential(FSD) A Free Span Differential signal is defined as a free-span indication reported on a differential channel. In SG1, inspection revealed one FSD indication in one tube. This indication was present in the tube mill data. Subsequent inspections with the +Point rotating coil revealed no degradation at the FSD location. There were no FSD indications reported in SG2. ManufacturingBurnish Marks (MBM) A Manufacturing Burnish Mark is defined as a material discontinuity at a location which has been repaired in the tube mill by buffing. In SG1, inspection revealed 3 MBM indications in 3 tubes. In SG2, inspection revealed 2 MBM indications in 2 tubes. All of the reported MBM indications were present in the tube mill eddy current data. Subsequent inspections with the +Point rotating coil revealed no degradation at the MBM locations.

ATTACHMENT 11 Letter from T. Coutu (NMC) To Document Control Desk (NRC) Dated February 22, 2002 Examination Summary for Steam Generator 900 KIP Hydraulic Snubbers

SUMMARY

OF VISUAL EXAMINATION, FUNCTIONAL TEST, DISASSEMBLY, OVERHAUL AND INSTALLATION ACTIVITIES provide Wyle Laboratories was contracted by Nuclear Management Company, LLC to and overhaul of two personnel and equipment to support the functional testing, disassembly Power Plant. These 900 Kip Anker-Holth Steam Generator snubbers at the Kewaunee Nuclear Program. activities were performed in accordance with Wyle's approved Quality Assurance to removal, at hot Additionally, Wyle was asked to perform Visual Examinations (VT-3) prior and installation functional and to provide technical support during removal, transportation activities. Lead Technician/Machine Personnel required to accomplish these activities consisted of a Site Specialist. Equipment Operator, A Mechanical Test Specialist and a Quality Assurance trailer, associated supplied consisted of an API/Barker In-Place Test Machine, a 48' rebuild tools and fixtures. with Paragraph 6.2 As-Found Visual Examinations (prior to removal) performed in accordance examinations were of SP-55-313 Rev. D did not identify any recordable indications. The documented on SP-55-313 Rev. D Appendix A. Generators 1A and Functional testing of the large bore hydraulic snubbers installed on Steam Rev. D "Steam 1B was performed in accordance with the requirements of SP 55-313 "Procedure For In-Place Generator Hydraulic Snubber Testing" and Wyle procedure 41378-1 Plant". Testing Of 900 Kip Anker-Holth Snubbers At Kewaunee Nuclear Power were subjected The 900 Kip Anker-Holth snubbers, S/N 25.12620.004-1 and 25.12620.004-7 to the following tests: in the tension and

1) Breakaway Force: Measured the force required to initiate movement compression directions.

the tension and

2) Drag force: Measured the force required to maintain movement in compression directions.

to a piston velocity) at

3) Lockup Velocity / Activation: Measured the fluid flow (equivalent and which the snubber activated to the velocity limiting mode in the tension compression directions.

(equivalent to a piston

4) Bleed / Release Rate @ 100 +5/-0 Kips: Measured the fluid flow limiting mode in the velocity) at which the snubber bled / released while in the velocity confirm test technique tension and compression directions. This test was performed to at a lower force.

flow (equivalent to a piston

5) Bleed / Release Rate @ 500 +5/-0 Kips: Measured the fluid limiting mode in the velocity) at which the snubber bled / released while in the velocity tension and compression directions.

The following is a tabulation of As-Found functional test results: SIN 25.1260.004-1 installed on Steam Generator 1A Examination # 1 As-Found Test Load @ 100 +51-0 Kips Test Parameter Tension Compression Lockup velocity 1.06 IPM 0.92 IPM Bleed Rate 0.0095 IPM 0.0093 IPM Test Load @ 500 +5/-0 Kips Breakaway Force < 2.0 Kips < 2.0 Kips Drag Force < 2.0 Kips < 2.0 Kips Lockup Velocity 1.04 IPM 0.88 IPM Bleed Rate 0.1099 IPM 0.1116 IPM S/N 25.1260.004-7 installed on Steam Generator 1B Examination # 2 As-Found Test Load @ 100 +5/-0 Kips Test Parameter Tension Compression Lockup velocity 0.97 IPM 0.93 IPM Bleed Rate 0.0121 IPM 0.0114 IPM Test Load @ 500 +51-0 Kips Breakaway Force < 2.0 Kips < 2.0 Kips Drag Force < 2.0 Kips < 2.0 Kips Lockup Velocity 0.95 IPM 0.93 IPM Bleed Rate 0.1277 IPM 0.1217 IPM These test results are within the values specified in SP-55-313 Rev. D Overhaul activities consisted of disassembly, cleaning, inspection, photographing, seal replacement and assembly of S/N 25.12620.004-1 and SIN 25.12620.004-7. Performance of these activities was documented on Wyle's Hydraulic Snubber Control Cards. Upon disassembly some light corrosion was found in the snubbers. However, the corrosion was not sufficient enough to be considered anomalous. The corrosion was removed during parts cleaning. Plant Quality Control requested Hold Points for cleanliness inspection at Steps 4.5 and 4.15 "Parts acceptable for reassembly". Hold Points were placed at these steps in each control card and Quality Control was called when each step was reached during overhaul. Plant QC and Wyle QA initialed these steps in the Hydraulic Snubber Control Cards.

Upon completion of overhaul, As-Left functional tests were performed on each snubber. During the As-Left tension release rate test, Examination #3, Steam Generator 1 B's snubber SIN 25.12620.004-7 exhibited fluid leakage around the cylinder head bolts. Testing was terminated and Notice of Anomaly (NOA) #1 and KNPP KAPWO #01-016757 were initiated. The NOA recommended disassembly and the replacement of the leaking seal. Inspection after disassembly identified that the cylinder head o-ring's backup ring had been cut during assembly. The cylinder head's o-ring and backup ring were replaced with new parts from the warehouse. Additional sheets (2 of 4 & 3 of 4) of the Hydraulic Snubber Control Card were used to document disassembly, inspection, assembly and parts used. The following is a tabulation of the As-Left functional test results: SIN 25.1260.004-1 installed on Steam Generator 1A Examination # 4 As-Left Test Load @ 100 +5/-0 Kips Test Parameter Tension Compression Lockup velocity 1.04 IPM 0.89 IPM Bleed Rate 0.0094 IPM 0.0091 IPM Test Load @ 500 +5/-0 Kips Breakaway Force --2.0 Kips < 2.5 Kips Drag Force -<2.0 Kips < 2.5 Kips Lockup Velocity 1.07 IPM 0.87 IPM Bleed Rate 0.1079 IPM 0.1084 IPM SIN 25.1260.004-7 installed on Steam Generator lB Examination # 5 As-Left Test Load @ 100 +5/-0 Kips Test Parameter Tension Compression Lockup velocity 0.97 IPM 0.91 IPM Bleed Rate 0.0113 IPM 0.0105 IPM Test Load @ 500 +5/-0 Kips Breakaway Force < 2.5 Kips < 2.5 Kips Drag Force < 2.5 Kips < 2.5 Kips Lockup Velocity 0.99 IPM 0.88 IPM Bleed Rate 0.1270 IPM 0.1197 IPM These test results are within the values specified in SP-55-313 Rev. D

Additional Activities:

1) Fluid Sampling: A 1-liter fluid sample was taken from each snubber for analysis. The following is a tabulation of the fluid analysis:

Steam Generator 1A 25.12620.004-1 Viscosity @ 100 deg. F 497.5 SUS SSU = (SUS x 0.0022 - 1.80/ SUS) x 100 Viscosity @ 210 deg. F 112.7 SUS Acid Number < 0.01 mg KOH/g Particle Count 5 to 10 microns 104294 /100 mL 10 to 25 microns 14550 /100 mL 25 to 50 microns 4651100 mL 50 to 100 microns 15 /100 mL 

 > 100 microns                                                       0 100 mL Steam Generator lB 25.12620.004-7 Viscosity @ 100 deg. F                     494.0 SUS         SSU = (SUS x 0.0022 - 1.80/ SUS) x 100 Viscosity @ 210 deg. F                                                 112.3 Acid Number                                                     < 0.01 mg KOH/g Particle Count 5 to 10 microns                                                113994/100 mL 10 to 25 microns                                                21937 / 100 mL 25 to 50 microns                                                 706 / 100 mL 50 to 100 microns                                                  30/100 mL
  > 100 microns                                                      0 / 100 mL installation of
2) Reservoir Fitting Replacement (Flare): Inspection of reservoir lines after flare Steam Generator 1A's snubber identified that the reservoir line was leaking at the fitting was obtained from the fitting (fitting to tube joint) on the control valve. A new flare the warehouse, installed in the control valve and the line reconnected. Inspection The tubing following morning identified the fitting was still leaking at the same location.

The tubing was disconnected the old flare was cut off and the tubing was flared again. was reconnected and tightened. Inspection the following morning identified that the the best fitting was still leaking, just slightly but leaking. The decision was made that type fitting way to stop the leaking joint was to replace the flared fitting with the same (Swage-Lok) used on the snubber installed on Steam Generator 1 B. obtained from the

3) Reservoir Fitting Replacement (Swage-Lok): A Swage-Lok fitting was flare fitting was warehouse, the reservoir line disconnected and the flare cut off. The The reservoir removed from the control valve and replaced with the Swage-Lok fitting.

identify any line was reconnected and tightened. Subsequent inspections failed to further leakage. Final Report. All All parts were provided by KNPP and are listed in Section 5.0 of the document for snubber work was documented in Bechtels Steam Generator replacement removal and installation.

Additional Activities (cont.)

4) The reservoirs on 1A and 1B Steam Generators were filled to approximately 50% with new fluid provided by KNPP.
5) Post installation VT-3 examinations were performed on Steam Generator 1A and 1B snubbers upon completion of installation activities. These exams revealed no recordable indications.
6) As-Left VT-3 examinations were performed on Steam Generator 1A and 1B snubbers at a generator temperature of 547* F. The generators had stabilized at 547* F for more than four hours prior to the exams being performed. These exams revealed no recordable indications.

Michael L. Miller Sr. Sr. Enger. Specialist Wyle Laboratories

ATTACHMENT 12 Letter from T. Coutu (NMC) To Document Control Desk (NRC) Dated February 22, 2002 Summary of Examinations Which Were Limited by Geometric, Metallurgical, or Design/Access Restrictions and Associated Data Sheets

Docket 50-305 NRC-02-015 February 22, 2002 2, Page 1 Examinations performed during the first outage, third period, third interval, were intended to examine 100% of the required surface or volume. In some cases, examinations were limited by geometric, metallurgical or design/access restrictions. In each case, the occurrence and cause of the limitation was documented. In all cases, the maximum amount of examination area/volume achievable was examined. The following is a list of examinations performed during the first outage, third period, and third interval, identifying those components where limitations occurred. 2 of this report transmits NDE data sheets for the 2001 examinations, which were limited by geometric, metallurgical, or design/access restrictions. 2001 Summary of Limitations for V Outage, 3 rd Period, 3 rd Interval Inservice Inspection 1 Method of  % Recorded As Not Year Component Identification Examination Examined and Limitation 2001 Reactor Vessel Closure Head UT 23%: Lifting Lug: Head to Flange Weld RV-W12 Flange Configuration 2001 Longitudinal Weld P-W2 on UT 3%: Insulation Support Ring Pressurizer 2001 Cirumferential Weld P-W3 on UT 3%: 2 Welded Pads, Pressurizer 2 Instrumentation Lines and Curvature of Pressurizer Head 2001 Circumferential Weld P-W5 on UT 2%: 2 Welded Pads and Pressurizer 2 Instrumentation Lines 2001 Nozzle Inside Radius Section SG- UT 6.3%: Integrally Welded IR25 on Replacement Steam Attachment Generator 1A 2001 Nozzle Inside Radius Section SG- UT 6.3%: Integrally Welded IR26 on Replacement Steam Attachment Generator 1A 2001 Nozzle Inside Radius Section SG-IR27 UT 6.3%: Integrally Welded on Replacement Steam Generator 1B Attachment 2001 Nozzle Inside Radius Section SG-IR28 UT 6.3%: Integrally Welded on Replacement Steam Generator 1B Attachment 2001 Circumferential Weld SG-W2 on UT 11.1%: 4 Welded Pads and Existing Steam Generator 1A Weld Crown 2001 Circumferential Weld SG-W9 on UT 0.113%: 4 Welded Pads Existing Steam Generator 1B 2001 Circumferential Weld SG-Wl0 on UT 7.9%: 4 Welded Pads Existing Steam Generator 1B 3-Nozzles and Weld Crown 2001 Circumferential Weld SG-W25 on UT 9%: 3 Handholes and 4", 2"/4'" Replacement Steam Generator 1A and 2" Nozzles (7 total) 2001 Circumferential Weld SG-W31 on UT 9%: 3 Handholes and 4", 21/4" Replacement Steam Generator 1B and 2" Nozzles (7 total)

Docket 50-305 NRC-02-015 February 22, 2002 2, Page 2 2001 Summary of Limitations for 1st Outage, 3 rd Period, 3 rd Interval Inservice Inspection Method of  % Recorded As Not Year Component Identification Examination Examined and Limitation 2001 Circumferential Weld AHNR-W2 on UT 43%: 2 Welded Supports and Letdown Heat Exhanger 2 - 2" Nozzles 2001 Circumferential Weld APD-1B-W4 on UT 8.6%: Welded Name Tag Charging Pump Pulsation Dampener APD-1B 2001 Circumferential Weld AFSI-W1 on UT 67.06%: Flange Seal Water Injection Filter AFSI- 1A Configuration, Flange Cover Hinge Plate and Welded Name Plate 2001 Integrally Welded attachment MT 14.6%: Support Configuration APSI-1A-S3 on Safety Injection Pump APSI-lA 2001 Integrally Welded attachment MT 14.6%: Support Configuration APSI-iB-S1 on Safety Injection Pump APSI-1B 2001 Integrally Welded attachment MT 14.6%: Support Configuration APSI-1B-S4 on Safety Injection Pump APSI-IB 2001 Circumferential Weld MS-W50 on 30" UT 8%: O.D. Configuration Diameter Main Steam 2001 Longitudinal Weld MS-W90L on 32" UT 22%: 1" Elbow Taper Diameter Main Steam 2001 Longitudinal weld MS-W91L on 32" UT 63%: 1" Vent Line Diameter Main Steam 2001 Longitudinal weld MS-W91L on 32" MT 50%: 1" Vent Line Diameter Main Steam 2001 Circumferential Weld SI-W307 on 3" UT 47.5%: 3" x 3" x 3" Tee Diameter Safety Injection Configuration 2001 Circumferential Weld SI-W108 on 6" UT 50%: Valve Configuration Diameter Safety Injection 2001 Circumferential Nozzle to Safe End UT 50%: Material Configuration Butt Weld PR-Wl6DM on 6" Diameter and O.D. Taper Reactor Coolant - From Pressurizer 2001 Circumferential Weld RHR-W10 on 8" UT 63%: Valve Configuration and Diameter Residual Heat Removal 3/4" Drain Line 2001 Circumferential Weld RHR-WlO on 8" PT 1%: 3/4" Drain Line Diameter Residual Heat Removal

Docket 50-305 NRC-02-015 February 22, 2002 2, Page 3 2001 Summary of Limitations for 1 st Outage, 3 rd Period, 3 r" Interval Inservice Inspection Method of  % Recorded As Not Year Component Identification Examination Examined and Limitation 2001 Circumferential Weld RHR-W48 on PT 20%: Rigid Restraint 10" Diameter Residual Heat Removal 2001 Circumferential Weld RHR-414 on 12" UT 59%: Valve Configuration and Diameter Residual Heat Removal 2 Weldolets 2001 Circumferential Weld FW-W24 on 16" UT 8%: Valve Configuration Diameter Feedwater 2001 Circumferential Weld FW-W52 on 16" UT 8%: Valve Configuration Diameter Feedwater 2001 Integrally welded attachment VT-3 100% of Saddle Weld: Pipe FDW-H170 on 16" Diameter Encapsulation Feedwater Line 2001 Replacement Steam Generator IA UT 38.1%: Nozzle Configuration Nozzle to Safe End Butt Weld RC-W76DM 2001 Replacement Steam Generator 1A UT 38.1%: Nozzle Configuration Nozzle to Safe End Butt Weld RC W77DM 2001 Replacement Steam Generator lB UT 40.25%: Nozzle Configuration Nozzle to Safe End Butt Weld RC-W78DM 2001 Replacement Steam Generator lB UT 40.25%: Nozzle Configuration Nozzle to Safe End Butt Weld RC-W79DM

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