ML052440263

Inservice Inspection Third 10-Year Interval June 16, 1994 - June 16, 2004 Limitation to Examination Relief Requests of the Kewaunee Nuclear Power Plant

ML052440263
Person / Time
Site:	Kewaunee
Issue date:	06/23/2005
From:	Gaffney M Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0209, NRC-05-081
Download: ML052440263 (412)

Text

y!W COperatd Kewaunee Nuclear Power Plant Committed to by Nuclear Management Company, LLC June 23, 2005 NRC-05-081 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Kewaunee Nuclear Power Plant Docket 50-305 License No. DPR-43 Inservice Inspection Third 10-Year Interval June 16, 1994 - June 16. 2004 Limitation To Examination Relief Requests of the Kewaunee Nuclear Power Plant Kewaunee Nuclear Power Plant (KNPP) is required to have an Inservice Inspection (ISI) Program for examination of American Society of Mechanical Engineers (ASME)

Class 1, 2, and 3 systems and their supports. During the third Inservice Inspection interval, ISI examinations were performed on the required number of components in accordance with 10 CFR 50.55a and ASME Section Xl, 1989 Edition with no Addenda.

On June 16, 2005, KNPP ended its third interval ISI Program (incorporating the ASME Boiler and Pressure Vessel Code Section Xl 1989 Edition Section IWA-2430(d) One Year Extension).

All examinations were completed by November 30, 2004. The required examinations were conducted in a manner that met all Section Xl Code requirements to the extent practical. There were areas where the Code required coverage could not be obtained. Where possible, KNPP substituted other welds and supports to avoid those situations where complete Code compliance could not be attained. In some cases, KNPP was successful with finding an alternate area where full Code compliance could be achieved. This Request for Relief details those areas where the Code required examination criteria could not be completely met, and to what extent Code compliance was achieved.

N490 Highway 42 . Kewaunee, Wisconsin 54216-9511 Telephone: 920.388.2560 7V(1

Document Control Desk Page 2 Photographs showing the Examination Limitations in most cases were taken well after the actual performance of the examinations. This was due to improved technology from the start of the third Ten-Year Interval, the desire to document the limitation in addition to the required procedure sketch, and to supply an actual photograph of the limitation as a process improvement for better understanding of the restriction. Nuclear Management Company, LLC requests relief in accordance with 10 CFR 50.55a(g)(5)(iii), as these areas either could not be examined in accordance with Section Xl Code requirements or without significant modifications to the plant.

Mchael fe Site Vice Presiden, ewaunee Nuclear Power Plant Nuclear Manageme Company, LLC Enclosure (1) cc: Administrator, Region l1l, USNRC Project Manager, Kewaunee Nuclear Power Plant, USNRC Resident Inspector, Kewaunee, USNRC Mr. Mike Verhagen, Department of Commerce, State of Wisconsin

ENCLOSURE I INSERVICE INSPECTION THIRD 10-YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 LIMITATION TO EXAMINATION RELIEF REQUESTS OF THE KEWAUNEE NUCLEAR POWER PLANT 408 pages follow

KEWAUNEE NUCLEAR POWER PLANT Component Identification Code Class: 1,2 Examination Categories: Reference attached RR-G-7-1 through RR-G-7-73 Item Numbers: Reference attached RR-G-7-1 through RR-G-7-73

==

Description:==

Limited Section XI Code examinations during Code required examinations Code Requirements Third Inservice Inspection Interval 1989 Edition of Section XI, no Addenda ASME Code Case N-460, Alternative Examination Coverage for Class I and 2 Welds Volumetric and surface examinations of welds and base material will be examined in accordance with the applicable Examination Category and Item Number.

Basis for Relief During the third inservice inspection interval, Kewaunee Nuclear Power Plant (KNPP) used the requirements of the 1986 Edition of ASME Section XI for examination of components. This edition of Section XI has specific requirements for what components will be examined and to what extent they will be examined. This edition of Section XI was followed with the exception of the selection of Class 1 piping welds. In accordance with 10 CFR 50.55a(b)(2)(ii), KNPP used the 1974 Edition of Section XI for selection of Class 1 Category B-J piping welds. This selection criteria states that for each inservice inspection interval, a different 25% of the population of class 1 piping welds shall be examined. Since this was the third 10-year interval, essentially 50% of the Class 1 piping welds had already been examined, leaving only 50% of the total Class I welds available for selection and examination. This factor led to many of the welds being examined having a higher probability of having limited examinations. For all other Examination Categories, KNPP used the Section XI required examination selection criteria.

During the performance of scheduled examination, there were numerous instances where examiners reported some type of interference. KNPP personnel evaluated every instance where this situation was reported, and when possible, alternative examination areas were selected to avoid having to examine restricted areas. This reduced the population of welds where a limited examination would be encountered. On welds where alternatives were not available, additional techniques were performed to increase coverage where possible, such as using steeper angle beam ultrasonic techniques or approaching the examination area from a different direction. In each case, this increased examination area coverage to the extent practicable and reduced the number of welds with limited examinations.

In order to gain additional access to the areas where limited examinations were encountered, major modification of components would be required. These modifications could be extensive, up to and including complete replacement. In cases where minor grinding would allow additional coverage, this was performed.

Major modification of components is not a feasible approach nor is it required to obtain additional coverage. Modifying systems and components to improve examination area coverage would result in additional dose with marginal improvement in quality or safety.

10 CFR 50.55a(g)(1) states that plants of KNPP's vintage (construction permit before January 1, 1971) must meet the requirements, except design and access provisions and preservice examination requirements, set forth in ASME Section XI. Access has been improved over the years to many areas of the plants, further reducing those areas with limitations, but it is not a requirement to make every area available for examination.

Removal of structural interferences to gain additional examination area coverage is costly in time and dose with little impact to quality or safety. Structural steel and component supports, were not designed for removal. If any were removed, temporary support structures would need to be designed and installed to compensate for the reduction in load bearing capacity. Temporary modifications, such as these, could require extensive scaffold building and temporary structural components, resulting in additional accumulated radiation dose.

For volumetric examinations, KNPP examined the required areas to the extent practical using ultrasonic examination techniques. Since May 22, 2000, many of these components were examined using personnel qualified in accordance with Appendix VIII of Section XI and as implemented by the Performance Demonstration Initiative (PDI). All examinations performed prior to the implementation of the 10 CFR 50.55a(g)(6)(i)(C) Appendix VIII requirements, show the limitations of the 1989 Edition of Section XI. All examinations performed after the implementation of the Appendix VIII requirements show limitations based on component configuration, material, or limitations in the PDI procedures being used. Where possible and allowed by the applicable PDI Generic Procedure, additional angles were used to increase coverage. In many cases, no combination of ultrasonic angle beam examinations would cover the entire examination area. In each case, the maximum feasible coverage was obtained.

KNPP performs system leakage tests in accordance with the Pressure test requirements of Section XI, Examination Categories B-P and C-H. These pressure tests cover every component within the Code boundaries established by KNPP. Where leakage was noted at mechanical connections, these were corrected in accordance with maintenance procedures.

Proposed Alternative KNPP proposes to use the examination volume or surface coverage obtained during the third interval examinations on the listed components in lieu of the Code required volumes and surfaces (Reference RR-G-7-1 through RR-G-7-73 (see attachments). The coverage obtained meets the intent of ASME Section XI and provides an acceptable level of quality and safety.

Conclusion The examinations performed during the third inservice inspection interval were performed to the extent possible. Additional coverage was impractical, as modification of systems, structures, and components would have resulted in significant radiation exposure with minimal increase in the level of quality and safety.

Period for Which Relief is Requested Relief is requested for the third inservice inspection interval at KNPP, which ended on June 16, 2005 incorporating the ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Section IWA-2430(d) One Year Extension.

Attachments RR-G-7-1 through RR-G-7 Listing and sketches of Limited Examinations for the Third Inservice Inspection Interval

INSERVICE INSPECTION 3RD 10,YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 LIMITATION TO EXAMINATION RELIEF REQUESTS OF THE KEWAUNEE NUCLEAR POWER PLANT N490 HIGHWAY 42 KEWAUNEE, WISCONSIN 54216-9511

INSERVICE INSPECTION 3RD 10-YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 LIMITATION TO EXAMINATION RELIEF REQUESTS OF THE KEWAUNEE NUCLEAR POWER PLANT N490 HIGHWAY 42 KEWAUNEE, WISCONSIN 54216-9511 PREPARED BY:

KEWAUNEE NUCLEAR POWER PLANT ENGINEERING PROGRAMS N490 HIGHWAY 42 KEWAUNEE, WISCONSIN 54216-9511

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-1 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Integrally Welded Attachment AHRS1-SW1 and AHRS1-SW2 to Residual Heat Exchanger AHRS1-1A

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-C; Item No. C3.10

4. Impracticality of Compliance: 20.7% of the Integrally Welded Attachments were inaccessible due to configuration of the Welded Attachment in close proximity to the Residual Heat Exchanger thus restricting application of the Surface Examination Liquid Penetrant.

5. Burden Caused by Compliance: To provide for access to the 20.7% weld area between the welded attachment and the Residual Heat Exchanger would require modification from the Original Design of the Residual Heat Exchanger and the Welded Attachment.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-1

6. Proposed Alternative and Basis for Use: No alternative Code required Surface examination is available due to limited access. VT-2 and VT-3 Examinations were performed during the 3rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: VT-2 Table IWC-2500-1; Examination Category C-H; Item C7.10 each 3 1/3 Year Period for evidence of leakage and VT-3 as required by Table IWF-2500-1; Examination Category F-A; Item No. F1.40B for general mechanical and structural condition.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-2 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Integrally Welded Attachments APSI-lA-S1, APSI-1A-S3 and APSI-1A-S4 to Safety Injection Pump APSI-IA and APSI-lB-S1, APSI-1B-S2 and APSI-1B-S4 to Safety Injection Pump APSI-1B

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-C; Item No. C3.30

4. Impracticality of Compliance: 14.6% of each Integrally Welded Attachment was inaccessible due to configuration of the Welded Attachment in close proximity to the Safety Injection Pump thus restricting application of the Surface Examination Magnetic Particle.

5. Burden Caused by Compliance: To provide for access to the 14.6% weld area between the welded attachments and the Safety Injection Pump would require modification from the Original Design of the Safety Injection Pump and the Welded Attachments.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-2

6. Proposed Alternative and Basis for Use: No alternative Code required Surface examination is available due to limited access. VT-2 and VT-3 Examinations were performed during the 3rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: VT-2 Table IWC-2500-1; Examination Category C-H; Item C7.50 each 3 1/3 Year Period for evidence of leakage and VT-3 as required by Table IWF-2500-1; Examination Category F-A; Item No. F1.40B for general mechanical and structural condition.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,'2004 RELIEF REQUEST NO: RR-G-7-3 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Integrally Welded Attachments APSI-1A-S2 to Safety Injection Pump APSI-1A and APSI-1B-S3 to Safety Injection Pump APSI-1B

2. Applicable Code Edition and Addenda: -1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-C; Item No. C3.30

4. Impracticality of Compliance: 17.0% of each Integrally Welded Attachment was inaccessible due to configuration of the Welded Attachment in close proximitylto the Safety Injection Pump thus restricting application of the Surface Examination Magnetic Parfticle.--

5. Burden Caused by Compliance: To provide foraccess to the 17.0% weld area between the welded attachments and the Safety Injection Pump would require modification from the Original Design of the Safety Injection Pump and the Welded Attachments.

Page 1-of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994- JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-3

6. Proposed Alternative and Basis for Use: No alternative Code required Surface examination is available duelto limited access. VT-2 and VT-3 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: VT-2 Table IWC-2500-1; Examination Category C-H; Item C7.50 each 3 1/3 Year Period for evidence of leakage and VT-3 as required by Table IWF-2500-1; Examination Category F-A; Item No. F1.40B for general mechanical and structural condition.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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-- l NONE IAD - M-l 707 IB

WISCONSIN PUBLIC SERVICE CORPORATION [REV. ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEMORCOMPONENT: <AFT IALJE(TION PUMPS APSI - 1A AND APS - IB DRAWING NO.: M - /707 COMPNENTA PSJJ- - 537 COMPONENTIDENTIFICATION:A P -IA -52 PROCEDURE:NFPNO. / 7 REVISION: Dri .

ULTRASONIC:.. LIQUID PENETRANT: - MAGNETIC PARTICLE: X VISUAL:

EXAMINER: - DATE: --// - .3 - 99 LEVEL

'-7~& l EXAMINER: DATE: // 398 3-LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

830/ EXAMINED

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_ XAMA AREA

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KEWAUNEE NUCLEAR POWER PLANT REVIEW: rot_ _ _______ _ DATE_ _Nl__q_

AUTHORIZED NUCLEAR X INSERVICE INSPECTOR REVIEW: ___DATE: /---?f i

y-)

Safety Injection- Pump APSI-lA Integrally Welded Attachments Typical

SaveTYe1LQL-?UO( T eLI,?T Ct \iPIlL lvXae(OEuLy WaLoeb aTaS6imt-Ss

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-4 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Reactor Vessel Closure Head To Flange Weld RV-W12

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-A; Item No. B1.40

4. Impracticality of Compliance: 23.0% of the Reactor Vessel Head to Flange Weld RV-W12 was inaccessible due to configuration of the Reactor Vessel Closure Head Flange and the 3 Welded Lifting Lugs thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 23.0% of the Head to Flange Weld RV-W12 would require modification from the Original Design of the Reactor Vessel Closure Head and removal of the 3 Welded Lifting Lugs. During the Fall 2004 Refueling Outage Kewaunee Nuclear Power Plant replaced it's Reactor Vessel Closure Head. The Replacement Reactor Vessel Closure Head was manufactured as a one piece forging. Thus a Reactor Vessel Closure Head to Flange Weld does not exist and ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Table IWB-2500-1 Examination Category B-A, Item No. B1.40 no longer applies.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-4

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the 3rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: VT-2 Table IWB-2500-1; Examination Category B-P; Item B15.10 each Refueling Outage for evidence of leakage. Surface Magnetic Particle Examinations were performed as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Table IWB-2500-1; Examination Category B-A; Item No. B1.40. During the Fall 2004 Refueling Outage Kewaunee Nuclear Power Plant replaced it's Reactor Vessel Closure Head. The Replacement Reactor Vessel Closure Head was manufactured as a one piece forging.

Thus a Reactor Vessel Closure Head to Flange Weld does not exist and ASME Boiler and Pressure Vessel Code Section XI 1989 Edition Table IWB-2500-lExamination Category B-A, Item No. B1.40 no longer applies.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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REACTOR VESSEL CLOSURE HEAD FLANGE AND CONTROL ROD DRIVE MECHANISM

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GREENBAY. WISCONSIN CONTROL ROD DRIVE HECHANISH E TYP.)

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KEWAUNEE NUCLEAR POWER PLANT REVIEW: ___ DATEO______

AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: __ DATE: "" -J 18

Rca.ToR VesseL CLosupa eaet ttFh4CG6 LLuL

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-5 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Head Circumferential Weld APD-1A-WI to Charging Pump Pulsation Dampener IA;Head Crcumferential Weld APD-1B-W4 to Charging Pump Pulsation Dampener lB and Head Circumferential Welds Top and Bottom to Spare Charging Pump Pulsation Dampener K> 2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-A; Item No. C1.20

4. Impracticality of Compliance: 9.0% of the Weld APD-1A-W1, 8.6% of Weld APD-1B-W4 and 9.0% of Top and Bottom Spare Head Welds were inaccessible due to a Welded Name Plate in close proximity to the Charging Pump Pulsation Dampener Circumferential Head Welds thus restricting the Ultrasonic Examination.

5. Burden Caused by Compliance: To provide access to the 9.0% of APD-lA-W1, 8.6% of APD-1B-W4 and 9.0% of Top and Bottom Spare Head weld scan area between the Welded Name Plate and circumferential weld on the Charging Pump Pulsation Dampener would require removal and reinstallation of the Welded Name Plate.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-5

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to limited access. VT-2 Examinations were performed during the 3rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-H; Item C7.10 each 3 1/3 Year Period for evidence of leakage.

7. Duration of Proposed Alternative: 3rd Ten Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable K ' 9.

References:

Not Applicable Page 2 of 2

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I. DRAWING APPLICABLE FOR 3RD(S4TN IS CHARGING PUMP PULSATION It1TERVAL ASKtE BOILER AND PASUR VESSEL CODE SECTION XI CLASS 2 DAMPENERS

2. APO-I A-WI . APO-I A-WZ. APO-I 8-W3. APO-I 8-V4. -

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3. NO BOLTING OA INTEGRALLY WELDED ATTACHmENTS GREEN SAY. WISCONSIN ON CHARGING PUP PULSATIONI OANPENERSAPO-IA.

APO-t AND APO-IC.

LOCATIONh AUXILIARY BUILDING 586' ELEVATION CHARGING PUM' ROOM GATE 208 X. 1Tio l CAO. NO I 0

WISCONSIN PUBLIC SERVICE CORPORATION KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD C4A&QDA%- L Puto PuL%  % r~bo SYSTEMORCOMPONENT:MDH S/V 5 G.IM I24, DRAWING NO.: NN-t2:1.

COMPONENT IDENTIFICATION: Ao -iA- t PROCEDURE: GcP;l-' REVISION: -p(.

ULTRASONIC: X LIQUID PENETRANT: MAGNETIC PARTICLE: __ VISUAL:

EXAMINER: . ' DATE: _ _3 __

LEVEL EXAMINER: lzzl I -b DATE: __ _3_/0 __

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INSERVICE INSPECTOR REVIEW: 2 Y Cf DATE: 7 Cz ,4 61

Charging: Pump Puls'ation-Dampener 1A

Weld APD 1A-WI:

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC;PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT:--HA~tr.IP PLPLLATicAlO 4MPuesA5 Apb -IA AP -Ii Atio APt- I c DRAWING NO.: M 10 COMPONENT IDENTIFICATION: APO w PROCEDURE: AEP-J6&.I REVISION: A ULTRASONIC: LIQUID PENETRANT: _ MAGNETIC PARTICLE: VISUAL:

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Charging Pump Puisation Dampener lB Weld APD-lB-W4

WISCONSIN PUBLIC SERVICE CORPORATION KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SST OCMN CTaR:Ia.m PutA PuL.SkriOf SYSTEM OR COMPONENT: -Dam~euep Sim Gl 4 I M DERAWING NO.: M-Ao COMPONENT IDENTIFICATION: Te~WCL'.ba e tctt&.D PROCEDURE: QCP ql REVISION: -R\ 6.

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AUTHORIZED NUCLEAR . //

INSERVICE INSPECTOR REVIEW: 7DATE: e2/" -'S

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-6 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Pressurizer Head Circumferential Welds P-W3 and P-W5

2. Applicable Code Edition and Addenda: 1989, No Addenda K.. 3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-B; Item No. B2.11

4. Impracticality of Compliance: Approximately 2.0% of the scheduled examination of 100% of Weld P-W3 and 2.0% of the scheduled examination of 100% of Weld P-W5 were inaccessible due to Integral Welded Attachment Pads, 1" and 33/44" Instrumentation Lines,Curvature of the Pressurizer Head, or a 3" ground area in close proximity to the Pressurizer Circumferential Head Welds thus restricting the Ultrasonic Examination.

5. Burden Caused by Compliance: To provide access to the 2.0% of PW-W3 and P-W5 weld scan area between the Integral Welded Attachment Pads, 1" and 3/4" Instrument Line, Curvature of the Pressurizer Head or 3" ground area would require modification of the original design of the Pressurizer.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-6

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to limited access. VT-2 Examinations were performed during the 3rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.20 each 3 1/3 Year Period for evidence of leakage.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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OOZ I W I._ i I RAP 0d-d0id3B OODEO 4TH INTERVAL.

REVISEDuATERIAL.

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SEEREVISIONE-l.

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BYoJ.SPICE 2-21-97 APP ),PCuI 02-21-9?

0 CpR 0149 COUPL.

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Bv, Bn 7-19-99 D. P2R HEATER PENETRATION 10 *So PtR-PI THRU PZR-P7t PPPO,BAK7-26-n 41*. ATERIAL

• SHELL. SA 533 CRACE A CLASS I CARBON STEEL £ERE PVR0295 CMIL.

HEAO. SA 216 CR. lCC CARBON STEEL SEE REV. 0-1

• FEASURED WITHOUTINSULATION. FILLOIWPSI 8-3-99 WISCONSIN PUBLIC SERVICE CORPORATION KEWAUNEENUCLEAR POWR PLANT CARLTON. KEWAUNEECOUNTY. WISCONSIN PRESSUR I ZER PZR OESICNEO BY WISCONSIN PUBLIC SERVICE CORP.

HEATERS £70 TOTAL$ GREEN SAY. WISCONSIN I NPHILLIPE. BUKES -lr *>s}

In I _ ' I I REV.13-011 LOCATION, CONTAINWENT PRESSURIZER VAULT I CAoo0 IE COO IM-I 200 IIF F

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT:- PRae75sue e  ;>zep DRAWING NO.: M - 12.00 COMPONENT'IDENTIFICATION::?-u3 /P-i-35 PROCEDURE:NE? ,O. ISqREVISION: Oril ULTRASONIC: X LIQUID PENETRANT:.. MAGNETIC PARTICLE:.. VISUAL:

EXAMINER: J/-' a . DATE: /3o 1e v__l -LEVEL J ,-

EXAMINER: A LV DATE: w A LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

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WISCONSIN PUBLIC SERVICE CORPORATION R ORIG.

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WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: 5 P Q SSE1' 2/ElZ PZR DRAWINGNO.: MJl 1O

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REDVCED PocEEDVZ~t COVEAA&E C 21.

KEWAUNEE NUCLEAR POWER PLANT REVIEW: eC.. 7J DATE: _04 _8,a3001 AUTHORIZED NUCLEAR , -* ,

INSERVICE INSPECTOR REVIEW: + DATE: /A-ff-

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-7 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Pressurizer Head Longitudinal Weld P-W2

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-B; Item No. B2.12

4. Impracticality of Compliance: 3.0% of the scheduled examination of 12" of Weld P-W2 was inaccessible due to an insulation support ring in close proximity to the Pressurizer Longitudinal Weld thus restricting the Ultrasonic Examination.

5. Burden Caused by Compliance: To provide access to the 3.0% of PW-W2 would require removal of the insulation support ring and the insulation panels being supported on the ring. Removal of the insulation support ring and the insulation panels could cause a unsafe condition and an increase in personnel exposure due to the amount of time requiring Kewaunee Nuclear Power Plant to construct a temporary support to maintain the remaining Pressurizer Insulation Panels and the difficulty in removing and reinstalling the Insulation Support Ring and Insulation Panels in the correct location.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-7

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.20 each 3 1/3 Year Period for evidence of leakage.

7. Duration of Proposed Alternative: 3rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable K) 9.

References:

Not Applicable Page 2 of 2

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REVISEDUATERIAL.

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• HASUREOWEttOUKT INSULAT IO.

WISCONSIN PUBLIC SERVICE CORPORATION KEWAUNEENUCLEAR POWERPLANT CARLTON. KEWAUNEECOUNTY. WISCONSIN PRESSURIZER PZR DESIGNED BY WISCONSIN PUBLIC SERVICE CORP.

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-8 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Residual Heat Exchanger AHRS1-1A Shell Circumferential Weld AHRS1-W1

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-A; Item No. C1.10

4. Impracticality of Compliance: 77.0% of the Residual Heat Exchanger Shell Circumferential Weld AHRS1-Wi was inaccessible due to configuration of the Residual Heat Exchanger Flange to Shell, 2 Welded Supports and the 8" Inlet Nozzle and the 8" Outlet Nozzle thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 77.0% of the Shell Circumferential Weld AHRS1-Wi would require modification from the Original Design of the Residual Heat Exchanger.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-8

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-H; Item C7.10 each 3 1/3 Year Period for evidence of leakage.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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AHRS1-IA RESIDUAL HEAT EXCHANGER AHRSI-WI AHRSl-W2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-9 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).-

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Residual Heat Exchanger AHRS1-4A Head Circumferential Weld AHRS1-W2

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-A; Item No. C1.20

4. Impracticality of Compliance: 37.6% oof the Residual Heat Exchanger Head Circumferential Weld AHRS1-W2 was inaccessible due to configuration of the Residual Heat Exchanger Welded Support thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 37.6%%of the Head Circumferential Weld AHRS1-W2 would require modification from the Original Design of the Residual Heat Exchanger.

Pagel~f 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-9

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were perform'ed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Categdry C-H; Item C7.10 each 3 1/3 Year Period for evidence of leakage.

7. Duration of Proposed Alternative: 3rd Ten Year Interval June 16, 1994 -

June' 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT:2-e-sl0AL 4-ATct 9t16jCA2S AHeSI.IA m06 ANQs2 he DRAWING NO.: t - ilo.

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-ONAOMMW7 AHRSl-lA RESIDUAL HEAT EXCHANGER AHRSI -WI AHRSl -W2

-KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-10 PROPOSED ALTERNATIVE IN ACCORDANCE WITH'IOCFR 50.55a(g)(5)(iii).

INSERVICE INSPIECTIONIIMPRACTICALITY

1. ASME Code Component Affected: 'Reactor Coolant Pump 1A Main Flange'

-Bolting RCP-B1 though RCP-B8, RCP-B9 and RCP-B11through RCP-17

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-G-1; Item No. B6.180

4. Impracticality of Compliance: 7.3% of each Reactor Coolant Pump lA Main Flange Bolt was inaccessible due to configurationmof Main Flange Bolt thus' restricting Bore Hole Probe Ultrasonic Examination during the 1 st and 2nd Period.

5. Burden Caused by Compliancei To provide for access to the 7.3 % of the Main Flange Bolt would require modification'from the Original Design of the Reactor' Coolant Pump Main Flange Bolt.

Page I of 2

K) KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994- JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-10

6. Proposed Alternative and Basis for Use: Kewaunee Nuclear Power Plant Bore Hole'Probe examinations required a 700 Forward, 700 Reverse and

-90 Surface Scan to cover 100o% of the required length 'of the Main Flange Bolt during the 1, and 2 nd Examination Periods. Configuration of the Main Flange Bolt limited by 7.3% the 70 0 Forward and 900 Surface Scans. I.,-

Alternative Code required 0 °Straight Beam Examination per ASME Boiler and PressureVessel Code Section'XI 1995 Edition Appendix VIII Supplement 8 was performed on the remaining 8 Main Flange Bolts during the 3 rd Examination Period. The 0° Straight Beam Examination although less restrictive in number of transducers requires less access and thus No Limitations were recorded. If KNPP would have continued use of the' Ultrasonic Probe technique as permitted by ASME Boiler and Pressure Vessel Code Section XI 1995 Edition Appendix VIII Supplement 8 during the 3 rd Period limit to examinations would have been encountered and additional identical Relief Requests would require submittal. 4H Interval Examinations will be performed utilizing the approved Appendix VIII Supplement 8 - 00°Straight Beam to eliminate the Limitation on the Reactor Coolant Pump Main Flange Boltinggan4 the need for Relief Request Submittal.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable K Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT

,THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-11 PROPOSED -ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Reg'enerative Heat Exchanger, Head Circumferential Weld ARG-W9

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-A; Item No. C1.20

4. Impracticality of Compliance: 1.5% of the Regenerative Heat Exchanger Head Circumferential Weld ARG-W9 was inaccessible due to configuration of the Regenerative Heat Exchanger 2" Nozzle thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 1.5% of the Head Circumferential Weld ARG-W9 would require modification from the Original Design of the Regenerative Heat Exchanger.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-11

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 rd Examinations were performed during the 3 Interval as required bykASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table-,

IWC-2500-1; Examination Category C-H; Item C7.10 each 3 1/3 Year Period for evidence of leakage.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16,- 1994 -

June 16, 2004

8. Precedents: Not Applicable 9 9.

References:

Not Applicable

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AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: + DATE: -

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,92004 RELIEF REQUEST NO: RR-G-7-12 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Steam Generator 1A Nozzle Inside Radius Sections SG-IR25 and SG-IR26 and Steam Gener'ator 1B Nozzle Inside Radius Section SG-IR27 and SG-4R28

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-D; Item No. B3.140

4. Impracticality of Compliance::6.3% 'of each of the 4 Nozzle Inside Radius Sections SG-IR25, SG-IR26, SG-IR27 and SG-IR28 were inaccessible due to the configuration of the Steam'Generator Nozzle Inside'Radius Section Integrally Welded Attachment thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 6.3% of each of the Steam Generator lA and 1B Nozzle Inside Radius Sections would require modification from the Original Design' of the Steam Generators and the Integrally Welded Attachments supporting the Steam Generators.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16 2004 RELIEF REQUEST NO: RR-G-7-12

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: VT-2 Table IWB-2500-1; Examination Category-B-P; -Item B15.10 each Refueling Outage for evidence of leakage.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June16, 2004

8. Precedents: Not Applicable

) 9.

References:

Not Applicable K)Page 2of 2

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WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

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WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

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WISCONSIN PUBLIC SERVICE CORPORATION [REV.: ORIG.

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KEWAUNEE NUCLEAR 5,;)/

POWER PLANT REVIEW: DATE: 4;5aL) l(

AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: 7v76: - DATE: 6 - /

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,-2004 RELIEF REQUEST NO: RR-G-7-13 PROPOSED ALTERNATIVE IN ACCORDANCE-WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Letdown Heat Exchanger Head Circumferential Weld AHNR-W2

2. Applicable Code Edition and Addenda:' 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-A; Item No. C1.20

4. Impracticality of Compliance: 43.0% of the Letdown Heat Exchanger Head Circumferential Weld AHNR-W2 was inaccessible due to configuration of the Letdown Heat Exchanger 2-Welded'Supports and the 2" Inlet Nozzle and the 2" Outlet Nozzle thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To -provide for access to the 43.0% of the Head Circumferential Weld AHNR-W2 would require modification from the Original Design of the Letdown Heat Exchanger.

Page'

- of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-13

6. Proposed Alternative and Basis for Use: No alternative'Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table:

IWC-2500-1; Examination Category C-H; Item C7.10 each 3 1/3 Year Period for evidence of leakage.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

C. (* C.

, j v WILTING DATA I w; l a; v; L w n § _J l X I I I Cfov.^bWTIot CAVA

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Al OJULET C-l KAP 01-001633 DRAWINGAPPLICABLE FOR 3RO) BH ISI INTERVAL ASKE BOILER AND PR VESSEL CODESECTION Xi CLASS 2 WISCONSIN PUOLIC SERVICE CORPORATION KEWAUNEENUCLEAR POWERPLANT A"f-R SIl CARLTON. KEWAUNEECOUNTY. WISCONSIN LETDOWN HEAT EXCHANGER r AeTLETTO i 2 INLET TO VALVE*D0-8

_ V LVE .7 AHLD 0 EPIRENCE DESIGNED BY.

WISCONSIN PUBLIC SERVICE CORP.

GREEN RAY. WISCONSIN R.PRIE 1 35-041 LOCATION. AUXILIARY BUILDING 606' LETDOWN HEAT EXCHANGER ROOM GATE 53

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEMORCOMPONENT:LET)OWA, H EAT- £EYCHANG:&ER AHLb DRAWING NO.: AM- 1209 COMPONENT IDENTIFICATION: AH4NR - W2 PROCEDURE: NP- 15.41 REVISION: A ULTRASONIC: X LIQUID PENETRANT:-.. MAGNETIC PARTICLE:.. VISUAL:

EXAMINER: TFtk Cf-I-or-l S DATE: __l__ _ _l_

f/ (/'LEVEL EXAMINER: NAA tIA DATE: NA LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF IMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

' OUTLET LiMiTS 1IELb AHfIR- WZ FROM 42h q-q Wamb SuPPoprT LIMI'ITS WELD _

AYNR -WZ FRom IS 7-ZO AA 36- 4 _ _

45 - RESTRICTEb SrAN 2,5 78 bLE h w bEL) .5PPoRrS.

45* - RESTRICTEIb SCAN 5 buE TO INLET ANL1 OUTLET 2' LU./ES.

REbuCEb CobE COVERAGE 9Y 43/:

KEWAUNEE NUCLEAR POWER PLANT REVIEW: /?/21DATE: < X Oct' AUTHORIZED NUCLEAR R _ D 0/

NS IINSPECTOR REVI.W: __ ____ DATE:

/09/

LETDOWH-X AHLD sea; 4. Iv bifd

KEWAUNEE NUCLEAR POWER PLANT K)

THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004'-

RELIEF REQUEST NO: RR-G-7-14 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Seal Water Injection Filter 1A Shell Circumferential Weld AFS1-Wi

2. Applicable Code Edition and'Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-A; Item No. C1.10

4. Impracticality of Compliance: 67.06% of the Seal Water Injection Filter-1A Shell Circumferential Weld AFSI-W1 was inaccessible due to configuration, of the Seal Water Injection Filter 1A Flange to Shell Conflguration',Flange, Cover Hinge Plate,; Weld Crown and Welded -Name Plate thus restricting -

Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the-67.06% of the Shell Circumferential Weld AFSI-W1-would require modification from the Original Design of the Seal Water Injection Filter 1A.-

K> Page 1of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-14

-6. Proposed Alternative and Basis for-Use: No alternative Code required Ultrasonic examination is available due to the limited access. Howeverr nd during the Kewaunee Nuclear Power Plant 2n Interval 1984-1994; 100%"

Radiography in 1988, 100% Visual From the I.D. in 1988 and 100% Liquid Penetrant From the I.D. in 1988 were performed on Seal Water Injection' Filter IA-Shell Circumferential Weld AFSI-W1. VT-2 Examinations were performed during the 3 rd Interval as're'quired by ASME Boiler and - -

Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-H; Item C7.10'each 3 1/3 Year Period for evidence of leakage.

-rd "

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16,-1994 -

IJune 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

Cf' C, WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: SEAL WATER TkEC.TfOMAJ rIL1Rs AFSI- IA AWD AFST1-8 DRAWINGNO.: M-Iia2 COMPONENT IDENTIFICATION: -AFSI- WI PROCEDURE: NEP-I5JLI REVISION:,

ULTRASONIC: L LIQUID PENETRANT: MAGNETIC PARTICLE: VISUAL:

EXAMINER: , 4 C7 DATE: 1o /h 6 /O I

- LEVEL EXAMINER: AZA IVA DATE: )A LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

FLSLCR CVESXAt#VCf PLRT£71-FLPCE qu-. I I Ct f ______._____

AVSI-wi - FLASGE COmnrCULArlAdJ iMrS 5,148 1SCAN hR 145ORL. vJE.LD ERowg LMrTs .5,F1ft5 PLS SCAIJg FoR q5'dRL. FLAN&PCoorCR14HJaE PLA-ET LoCATED PRoM 1D.o tW rc Iq. 6" C VJ FROM C REFERE.ICE LIMITS I.,742 SCAMS PR 145 0 RL NAME PLATE L  !?R M Fxo&2 r.WT6 S9.0o 14.o" keLA VP6o 6 REFERE 0.q4 CTs RL TE ar- WELD AFST-wl LIMITS .2 SCANJ FP -149RL.

O \ (2L

.- L~fo0% PROCE.DLLIE C E>GRAGE. Nf cSAD.

KEWAUNEE NUCLEAR H 7  : T POWER PLANT REVIEW:/C DATE:AaS0 AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: - DATE:__-______

I KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-15 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY 1., oASp En Cn d fetd Sa ae neto itrl

1. ASME Code Component Affected:'S6&lWater Injection Filter 1A:

Head Circumferential Weld AFS 1-W2

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-A; Item'No. C1.20

4. Impracticality of Compliance: 35.8%of the Seal Water Injection Filter 1A Head Circumferential Weld AFSI-W2 was inaccessible due to configuration of the Seal Water Injection FilterlA - 3 Welded Supports and the 2" Inlet Nozzle thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance::To provide for access the 35.8% of the Head Circumferential Weld AFSI-W2 would require modification'from the Original Design of the Seal Water Injection Filter. 1A.

Page lof 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994- JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-15

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the-limited access. However,'

during 'the Kewaunee Nuclear Power Plant 2nd Interval 1984-1994;'100%

Radiography in 1988 and 100% Visual From the I.D. in -1988 were

-performed on Seal Water Injection Filter 1A Head Circumferential Weld AFSI-2.-VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code SectionXI 1989 Edition: Table IWC-2500-1; Examination Category C-H; Item C7.10 each 3 1/3 Year Period for evidence of leakage.

7. Duration of Proposed Alternative: 3rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

l C. ,C. C" I

I

WISCONSIN PUBLIC SERVICE CORPORATION ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD .

SYSTEM OR COMPONENT:5XWAWtR /NJAc5roNV ;17rR5 Arl-IA AJD AfS/- /B .

DRAWING NO.: Al -1212 COMPONENT IDENTIFICATION: AfQ-*2 PROCEDURE: 1fE io. L5. 16 REVISION: &ja.

ULTRASONIC: X LIQUID PENETRANT: MAGNETIC PARTICLE: __ VISUAL:

EXAMINER: 6. ( -. , - DATE: 11 - 14 .;-'fc F

LEVEL EXAMINER: e - I- DATE: 1 14 - 98 LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

I__ P[RCC7r Of LIMITED CODE cOVyf8Aa6: 3581

_pf?~Cfi'JT of LIA 4IZ PED RO(ovRfaCvERA4c: 35.9,.

450 60 0 *fCAAJ u/A4rED B- 2" INtEr NozzLt /.3' fROM TOroor IA-7 (AFS) -w2).

2O 45* AND 600 5,CA14S L/MI6rD BY 4.25 rqoM j4 -

AI-5VIS 51-sY2 AJ, AFSI,-- \ APNP AFI-.v3 AR A rorAL or

z. z 7 Arsl- - - /2 .75 APSJ - Sz/2 _

AFSI- SW3 -

KEWAUNEE NUCLEAR POWER PLANT REVIEW: _ _ _ __ _ _ _ __ _ __ DATE:__ __ _ _ _

AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: _ _ __ ADATE:___ _ _

- AFSI-W2 KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994- JUNE 16,-2004, RELIEF REQUEST NO: RR-G-7-16 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Steam Generator lA Shell Circumferential Weld SG-W2

2. Applicable Code Edition and Addenda: 1989, No Addenda K ' 3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C--A; Item No. C1.10

4. Impracticality of Compliance: 11.1% of the Steam Generator LA Shell Circumferential-Weld SG-W2 was inaccessible due to configuration-of--

the Steam Generator 1A - 4 Welded Pads and the configuration of the Weld Crown thus restricting Ultrasonic Examination.'

5. Burden Caused by Compliance: To provide for access to the 11.1% of the Shell Circumferential Weld SG-W2 would require modification from the' Original Design of Steam Generator 1A.-

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-16

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and.Pressure Vessel Code Section XI 1989 Edition: Table-' '

IWC-2500-1; Examination Category C-H; Item C7.10ech 3 1/3 Year Period for evidence of leakage. Magnetic Particle Examination of 100% of the I.D. was performed during the 2001 Steam Generator Replacement for evidence of I.D. Cracking.

7. Duration'of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

C'1 C C

^T KTIFC D^l EACRHbHbAr 32' WIN STEAlSNOZZLE COMPONENT DATA SO-IRIS LOWGITUDINAl WVELS LoINlTWINAL WILOS l I TYP.I 5HOWNFOR  : rP. I SHO~NFOR

- REFrERENCEONLY K

I REFERENCE ONLY W.L 5rEAN CEN 5G-t SEACtieN. Sr -18 rANWAT MANWAY A HaNA

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• ~ ~ SG-5eH2 NN ADSC H4 M CTODESPRING

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.I I I. CAN HANGERS FOR -SC-Hi AND SO-H3 RIGID RESTRAINTI

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PICI CO CCE 5PRINC AN NADeNGER FOR 0 REFERENCE,SG-W24.

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FUIUREAS BUILTS.

BYe JMS 02-01 -01 I, I APP BT

• FR DA PESERVICE EXAMSO REFERENCE C[NTEAtLIE OF PE PUR-ACOEO 4h INTERV TONOTE I-. BREFEENCE i - SWv21 D-1 ~ CAP01t-o0639 APP' IO RE PUR 6.Oj .R/

I i DRAWING APPLICABLE FOR 3rdig 4h t151 INTERVAL ASIC BOILER AND PRCiiR CODE SECTION XI CLASS 2 VESSEL E IOCR Z055-I COWFL.

SEEREV.0-I PFI LHEIfI WS)

WISCONSIN PUBLIC SERVICE CORPORATION KEWAUNEENUCLEAR POWERPLANT CARLTON. KEWAUNEECOUNTY. WISCONSIN STEAM GENERATORS I'M II- Old1 Vi' W1 3 rVIA. EXISTING AND REPLACEMENT 4lZ4.24-CIRcum. \24' 4Z.. CIRCUK SGS 31 OCR 2858-I SG-1A AND SG-1B I\ 134-011 TtuBE PLatE U 134 O2 DOESIGNED BY

.__'_______ I l5L.3A CSI PLACE WISCONSIN PUBLIC-.SERVICE CORP.

I .GREEN SAY. WISCONSIN ASHEBOILER ANo PRESSURE \ S E WOILER ANIO PRESSURE I- I SESSEL V COOE SECTION xi b VESSELCOOE SETION XI

- , CLASSI REFERENCE 1201EC

, . CS E LOCATION: CONTAINMENT

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEMORCOMPONENT: 6TEAM 6ElRAme5 xAsr( Nt, R&PLcjE/4T 3&-tl/ AATh <&-I DRAWING NO:_ M__- 1____

COMPONENTIDENTIFICATION: 5St- cd2 PROCEDURE:kEP -1509 REVISION: iq ULTRASONIC: X LIQUID PENETRANT: MAGNETIC PARTICLE:.. VISUAL:..

EXAMINER: -rm C0U" , -7 -,DATE:- /4 0 /

I ~'/ ~~ - -LEVEL EXAMINER: / 4l .. DATE: _ _//__/_ __

/ g LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

0 REF.

.-J SIDE SI DEr roUR WELDED PADS7.75'X ID.75 MEASuRED WTI14E CDRE.TmFlOM OREF.

LOCATED O4THE WELD TOE NTZAE -5 SiDE Or T'4E WELD LMITS 6,f1AND2SCA4S.

a WELD CROWN LimirS ScANS OJ 11AND 2 FD THI1 (oC--

3. $EbOc.cb Cc_& / PAccbctlRE COUEPA&G 8Y 0.5/. Fb Psc-i9S 7 A1 P.

tLJE To LAJELlbEfb PPAD .

Q4. IZA LEI- bCOE I PRZC L).E ovpEA&. Y 0.S'f. PoP StAA S 5, 9E.dCE Co /) PgOc E c PAcrc BY 2( OiL) Fn k SrA M 2.

KEWAUNEE NUCLEAR POWER PLANT REVIEW: r't,( c. DATE: Il AUTHORIZED NUCLEAR IN'SERVICE INSPECTOR REVIEW: / DATE: //--°-

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD EXSi7ihv OVC' T£PLMEJr SYSTEM OR COMPONENT: STEAM 4VERAEORS SGt IA ANID SG-1B DRAWING NO.: MI O16 COMPONENT IDENTIFICATION: S - PROCEDURE: AEP-16A5. REVISION: A ULTRASONIC: X LIQUID PENETRANT: -.- MAGNETIC PARTICLE:.. VISUAL:

EXAMINER: 21C DATE: 11 ID -I16 LEVEL D///A:/0 I EXAMINEF DATE: II/lo10/01

/111 (/,LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

0 REF.

-.-J 5SIDF 1.L 37'.5 g'~5~ I.J-.5 I I cUR WELDED PAoS 7.75'1X ID.15 MEAS1URED INT-4E COVtERTizFIOM OREp.

LoCAtED DR THE WELD TOE 6M THIE 5 9aDE Or TSiE WELD LIMITS 5,liALDS SCAWS.

. WELD CROWN LMITMS SCANS O,,qANDS FVD THE M45

3. L50- RE()ocfDlcovO/PRO CozlJRA66BY 73%

KEWAUNEE NUCLEAR POWER PLANT REVIEW: . D . & - DATE:. ]a 1 1 1 AUTHORIZED NUCLEAR IINSERVICE INSPECTOR REVIEW: _ DATE: /1 F

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: 5TE-Am EylsTIAihgEpLRcErtENT 5&-m 4 5&DS6 _emEQ2T~a5 DRAWING NO: m- 12cL COMPONENT IDENTIFICATION: -S&-L52- PROCEDURE:NEP -IS.e9 REVISION: A ULTRASONIC: L LIQUID PENETRANT: ____MAGNETIC PARTICLE: _ VISUAL:

EXAMINER: 'Tim Coos eM S Ad - . DATE: L /L1D l

-. /l I 1 II/ (/ LEVEL EXAMINER: I DATE: Ic' / O (o

LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

5 SIDE.

- ASIDE lPOUR WELDED PADS 1.75'X ID.15 MEAS'uLRED UNTRECVJDiRze-lo FRo M DREV.

LDCATED D)JTRFI WELD TOE 6M!lAEgb TDE 0S T"AUWELD

1. C) - REflcEb Cooe / ORcLtnLc 1 C-UEP-A&EB. A1l( ON s SItB.

KEWAUNEE NUCLEAR 49#/ j POWER PLANT REVIEW: tf 2d.y e. &'J.,4 DATE: MAtML4,6 1 iP AUTHORIZED NUCLEAR --

INSERVICE INSPECTOR REVIEW: / .- f8 DATE: -

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUESTNO: RR-G-7-17 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Steam Generator 1B Shell Circumferential Weld SG-W10

2. Applicable Code Edition and Addenda: 1989, No Addenda K 3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-A;'Item No. C1.10

4. Impracticality of Compliance: 7.9% of the Steam Generator lB Shell Circumferential Weld SG-W10 was inaccessible due to configuration of

- the Steam Generator lB - 4 Welded Pads, 3-2".Nozzles' and the --

configuration of the Weld Crown thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access tothe 7.9% of the Shell Circumferential Weld SG-W10 would require modification from the Original Design of Steam Generator 1B.-'

Page Ilof 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-17

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler'and Pressure Vessel Code Section XI 1989 Edition: Table ;

IWC-2500-1; Examination Category C-H; Item C7.10 each 3-1/3 Year Period for evidence of leakage. Magnetic Particle Exa-ination of 100% of-

-the I.D. was performed during the 2001 Steam Generator Replacement 'for evidence of I.D. Cracking.

7. Duration of Proposed Alternative: 3 rd Ten' Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

C. C f' REVISION 90Z1-W -

WAA l(S1SNC EAA ChT i-i PDO 0011 COWL SEE REV 0-I APPO: CAT 10/23/89 D-1 2' lVAIN 5TEAM NOZZLE 32' FAIN STEAM NOZZLE C OCR 2858-1 SG- 7 COFPONENT ZTHICKNESS OAit I ~ FalsA FILH-OtWPSI 11/7/89 5C- IS . ( I ISR3 OR ACL

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_51. 02' CIIRCU _ SO-WIn ADDEDCODESPRANM AND

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- I ADED REFNOS.

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POWER PLANT REVIEW: 2 r

. DATE: IVAr-d, 0 o1 AUTHORIZED NUCLEAR D 7.s INSERVICE INSPECTOR REVIEW: 7 I DATE: "/-#Z/

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-18 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Steam Generator 1B Head Circumferential Weld SG-W9

2. Applicable Code Edition and Addenda: '1989, No Addenda K) 3. Applicable Code Requirement: Table IWC-2500-1; Examination Category

'C-A; Item No. C1.20

4. Impracticality of Compliance: 0.113% of the Steam Generator lB Head Circumferential Weld SG-W9 was inaccessible due to configuration of the Steam Generator 1B - 4 Welded Pads thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance.: To provide for access to the 0.113% of the Head Circumferential Weld SG-W9 would require modification from the Original Design of Steam Generator- lB.-

Page I of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-18

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2' Examinations were performed during the 3 rd -Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination-Category C-H; Item C7.10 each 3 1/3 Year Period for evidence of leakage.

rd

7. Duration of Proposed -Alternative: 3 Ten Year Interval June 16,-1994 -

June- 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-19 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Steam Generator 1A Tubesheet -To-Shell Circumferential Weld SG-W25 and'Steam Generator lB Tubesheet -

To-Shell Circumferential Weld SG-W31'

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-A- Item No. C1.30

4. -Impracticality of Compliance: 9.0% of the Steam Generator 1A Tubesheet-To-Shell Circumferential Weld SG-W25 and'9.0% of the Steam Generator 1B Tubesheet -To-Shell Circumferential Weld SG-W31 were inaccessible due to each weld possessing 3 Handholes, 2- 4" Nozzles, 1-2 I /4' Nozzle and 4- 2" Nozzles thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 9.0% of the Steam Generator 1A Tubesheet-To-Shell Circumferential Weld SG-W25 and 9.0% of Steam Generator lB Tubesheet-To-Shell Circumferential Weld SG-W31 would require modification'of the design of Steam-Generator 1A and Steam Generator 1B.'-

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004; -

RELIEF REQUEST NO: RR-G-7-19

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available' due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code-Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-H; Item C7.10 'each 3 1/3 Year Period for evidence of leakage. ASME Boiler and Pressure Vessel'Code Section III Radiography was performed as part of Kewaunee Nuclear Power Plant Steam Generator Replacement during the 2001 Refueling Outage.

7. Duration of Proposed Alternative: 3 rd Ten-Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10- YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-20 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Reactor Vessel Outlet Nozzle To Vessel Weld RV-W7

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category--

B-D; Item No. B3.90

4. Impracticality of Compliance: 2.84% of the Remote Ultrasonic Perpendicular Scan and 56.76% of the Remote Ultrasonic Tangentiai Scan of the Reactor Vessel Outlet Nozzle to Vessel Weld RV-W7 were inaccessible due to the Outlet Nozzle Boss Radius and the Outlet Nozzle Boss thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 2.84%

Perpendicular Scan and 56.76% of the Tangential Scan of the Reactor Vessel Outlet Nozzle to Vessel Weld RV-W7 -would require modification of the original design of Reactor Vessel Outlet Nozzle.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-20

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable

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Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant 1st Outage; 1st Period; 3rd Interval Automated Reactor Vessel Too!

Examination Coverage Program - Weld Description Direction  % , l Lmitations Item Number __ _ _ _ _Coverage_l 2 RV-W7 Loop A Outlet Nozzle to Vessel Perpendicular 97.16% Nozzle Boss Radius Weld Tangential 43.24% Nozzle Boss 3 RV-W10 Loop B Outlet Nozzle to Vessel Perpendicular 97.16% Nozzle Boss Radius Weld Tangential 43.24% Nozzle Boss 4 RV-IR7 Loop A Outlet Nozzle Inside Circumferential 100.00%

Radius Section 5 RV-IR10 Loop B Outlet Nozzle Inside Circumferential 100.00%

Radius Section 6 RC-W1DM Loop A Reactor Coolant Pipe Parallel 100.00%

Outlet Nozzle to Safe End Perpendicular 100.00%

7 RC-W30DM Loop B Reactor Coolant Pipe Parallel 100.00%

Outlet Nozzle to Safe End Perpendicular 100.00%

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-21 PROPOSED 'ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Reactor Vessel Outlet Nozzle To Vessel Weld RV-W10

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-D; Item No. B3.90

4. Impracticality of Compliance: 2.84 % of the Remote Ultrasonic Perpendicular Scan and 56.76%, of the'Remote Ultrasonic Tangential Scan of the Reactor Vessel Outlet Nozzle to Vessel'Weld RV-W10 were inaccessible due to the Outlet Nozzle Boss Radius and the Outlet Nozzle Boss thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide'for access to the 2.84 %

Perpendicular Scan and 56.76%' of the Tangential Scan of the Reactor Vessel Outlet Nozzle to Vessel Weld RV-W1O would require modification of the original design of ReactorNVessel Outlet Nozzle. '

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-21

6. Proposed Alternative and Basis for Use:'No alternative Code required Ultrasonic examination is available due to the limited access.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval'June 16, 1994 -

June'16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant 1st Outage; 1st Period; 3rd Interval

- Automated ReactorVesselTool Examination Coverage Program l Weld Description Direction  % Limitations Item l Number Coverage 2 RV-W7 Loop A Outlet Nozzle to Vessel Perpendicular 97.16% Nozzle Boss Radius Weld Tangential 43.24% Nozzle Boss 3 RV-WIO Loop B Outlet Nozzle to Vessel Perpendicular 97.16% Nozzle Boss Radius Weld Tangential 43.24% Nozzle Boss 4 RV-IR7 Loop A Outlet Nozzle Inside Circumferential 100.00%

Radius Section 5 RV-IR1O Loop B Outlet Nozzle Inside Circumferential 100.00%

Radius Section 6 RC-W1DM Loop A Reactor Coolant Pipe Parallel 100.00%

Outlet Nozzle to Safe End Perpendicular 100.00%

7 RC-W3ODM Loop B Reactor Coolant Pipe Parallel 100.00%

Outlet Nozzle to Safe End Perpendicular 100.00%

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-22 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Steam Generator 1A Nozzle To Safe End Butt Welds RC-W76DM and RC-77DM

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table'IWB-2500-1; Examination Category B-F; Item No. B5.70

4. Impracticality of Compliance: 38.1% of the Steam Generator 1A Nozzle To Safe End Butt Welds RC-W76DM and RC-W77DM were inaccessible due 'to the Nozzle Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 38.1%-of the Steam Generator 1A Nozzle To Safe End Butt Welds RC-W76DM and RC-W77DM would require modification of the design of Steam Generator 1A Nozzles and Reactor Coolant Pipe.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-22

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code&Section XI 1989 Edition: Table i IWB-2500-1; Examination Category B-P; Item B15.30 each-Refueling Outage for evidence of leakage'. Surface Liquid Penetrant Examination was performed on Steam Generator lA-Nozzle to Safe End Butt Welds RC--

W76DM and RC-W77DM during the 3 rd Interval as required by ASME, Boiler and Pressure Vessel Code'Section XI 1989 Edition: Table'IWB-2500-1; Examination Category B-F and Item No:.B5.70. ASME Boiler and Pressure Vessel Code Section III Radiography was performed as part of Kewaunee Nuclear Power Plant Steam Generator Replacement during the 2001 Refueling Outage.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable f

9.

References:

Not Applicable X,; 0;,---

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WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: Zemcrox ckA, L-to4 iA DRAWING NO.: iSIMA- n7o0 COMPONENTIDENTIFICATION: e- . btA PROCEDURE: tdO -i-5.4fREVISION: A ULTRASONIC: X LIQUID PENETRANT: MAGNETIC PARTICLE: _ VISUAL:

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KEWAUNEE NUCLEAR POWER PLANT REVIEW: /CDATE: zoo00 AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: _ DATE:__________

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.I KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEMORCOMPONENT: 2-Fe r0 CxcL&m Loop A DRAWING NO.: ISIA-\1-Vl°3 COMPONENT IDENTIFICATION: RL-V1bitA PROCEDURE: PIlS.4f REVISION: A ULTRASONIC: X LIQUID PENETRANT: MAGNETIC PARTICLE: VISUAL:

EXAMINER: 6- -- DATE: / -

LEVEL EXAMINER: _ _ _ ___ _DATE: _ _ _l_ _ _ _

SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

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-107ALC-NE. NCT-a(G P-rOAWAE0 3 soI.

T C>rO1 rasa >.I . I I KEWAUNEE NUCLEAR 4? /

POWER PLANT REVIEW:/. dL\v/ (0. l DATE:

AUTHORIZED NUCLEAR -

INSERVICE INSPECTOR REVIEW: /- DATE:________

RC-W76DM KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-23 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected:'Steam Generator 1B Nozzle To Safe End'Butt Welds RC-W78DM and RC-79DM

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1;,Examination Category B-F; Item No. B5.70

4. Impracticality of Compliance: 40.25% of the Steam Generator lB Noizie To Safe End Butt Welds RC-W78DM and RC-W79DM were inaccessible due to the Nozzle Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance:'To provide for access to the 40.25% of the Steam Generator 1B Nozzle To Safe End Butt Welds RC-W78DM and RC-W79DM would require modification of the'design of Steam Generator 1B Nozzles and Reactor Coolant Pipe.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,'2004 RELIEF REQUEST NO: RR-G-7-23

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the-3 rd Interval as required by ASME Boiler'and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.30 each Refueling Outage for evidence of leakage. Su'rface Liquid Penetrant Examination was performed on Steam Generator lBNozzle to Safe End Butt Welds RC-W78DM and RC-W79DM during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code'Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-F and Item No. B5.70. ASME Boiler and Pressure Vessel Code Section III Radiography was performed as part of Kewaunee Nuclear Power Plant Steam Generator Replacement during the 2001 Refueling Outage.

7. Duration of Proposed Alternative:' 3rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEMORCOMPONENT: Z rbP CoLA#l ThPAA Loop i3 DRAWING NO.: ISINN- fl04 COMPONENT IDENTIFICATION: ZC- -Lz b m PROCEDURE: M)IP-.14rREVlSION: -

ULTRASONIC: X LIQUID PENETRANT: MAGNETIC PARTICLE: __ VISUAL:

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KEWAUNEE NUCLEAR POWER PLANT REVIEW: &' -e 4 DATE:-" 19,L01 AUTHORIZED NUCLEAR  :

IINSERVICE INSPECTOR REVIEW: 7= f DATE: 6______

WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: 2CAEcr- clt--r 'PQt-P Lo°a P?

DRAWINGNO.: LSIM-11704 COMPONENT IDENTIFICATION: tC- --'itK tM PROCEDURE: t 1P-Sr.4fREVISION: A ULTRASONIC: X LIQUID PENETRANT: _ MAGNETIC PARTICLE: __ VISUAL:

EXAMINER: Jx1 i2 iY  : 7 - DATE: 6-19-6)1 LEVEL EXAMINER: 3 Q t-a DATE: It 0 Co o LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

Ci:.

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N0.Z2L£ 5Wb E jsJe- CAMAIMSO 100 /.,

-T-csrr cIc/eIeAOLLL ioCT o&--Aw 4?

r- _ _ I 1-KEWAUNEE NUCLEAR i ,D,D9 k POWER PLANT REVIEW: r C.7J-/'C DATE: 6Illool AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: A_=_ - _ _ _ DATE: _ __'_-__

KEWAUNEE NUCLEAR POWER PLANT THIRD 10- YEAR INTERVAL JUNE 16,1994- JUNE 16,'2004 RELIEF REQUEST NO: RR-G-7-24 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Reactor Coolant Pump 1A Flywheel RCP-1A-FLY

2. Applicable Code Edition and Addenda: Not Applicable Nuclear Regulatory Commission Regulatory Guide 1.14 Reactor Coolant Pump Flywheel Integrity

3. Applicable Code Requirement: Not Applicable

4. Impracticality of Compliance: 9.0% of the Reactor Coolant Pump lA Flywheel RCP-1A-FLY was inaccessible due to the 5 Anti Rotation Paws and the Flywheel In Place Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 9.0% of the Reactor Coolant Pump 1A Flywheel would require removal of the 5 Anti Rotation Paws which would affect thie balance of the Reactor Coolant Pump Motor and would also require modification of the original design of Reactor Coolant Pump Flywheel Motor.-'

Page l of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-24

6. Proposed Alternative and Basis for-Use: No alternative Regulatory Guide required Ultrasonic examination is available due to the limited access.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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WISCONSIN PUBLIC SERVICE CORPORATION KEWAUNEENUCLEAR POWERPLANt CARLTON. KEWAUNEECOUNTY. WISCONSIN REACTOR COOLANT PUMPS RCP-1A AND RCP-18 OESIGNEO BY WISCONSIN PUBLIC SERVICE CORP.

GREENBAY. WISCONSIN RCP-IA PHILLIP E- BUKES RCP-tE .4tsf1 A.l r 3~r PV33Ow 1 45-021 1 45-022 I REV.

LOCATION. CWNTAIKENT I

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VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM ORCOMPONENT: hJ'Ec-fAr- CLi.&,7 "'L4 W /-/ / 14 DRAWING NO.: m - .. o.(

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EXAMINER:

o(]A 2 __r;I-

//5 10- /76,

- . \l.l , '. . DATE:

- LEVEL EXAMINER: ..ann v, -  : DATE: /' A/*/ '6, 7 LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

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Evms LchAVAET kA-v~p FROM GA E.s $oLE

-S 7- ).o3' ws Top /..5" oF LpPFR PLtqrE RE.5T-rcrs \ycwy I 4-vO R4DJ01AL GA,6iE HOLE ExAv5. -

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• Yo°O cF Re~ VoLume. J-NoT EXAn\irac KEWAUNEE NUCLEAR %S / i POWER PLANT REVIEW: r. C, DATE: 5 AUTHORIZED NUCLEAR /

INSERVICE INSPECTOR REVIEW: ____ DATE: /° ?9

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994- JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-25 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 16" Feedwater Integrally Welded Attachment FDW-H170

2. Applicable Code Edition and Addenda: 1989, No Addenda KU 3. Applicable Code Requirement: Table IWC-2500-1;'Examination Category C-C; Item No. C3.20 and Table IWF-2500 Examination Category F-A; Item No.'

F1.20B

4. Impracticality of Compliance: 100% of the Integrally Welded Attachment Saddle Weld Portion of 16" Feedwater Support FDW-H170:is inaccessible for Surface Examination as required by IWC-2500-i, Category'C-C, Item No. 3.20 and Visual examination as required by IWF-2500-1 Examination Category F-A, Item No. F1.20B due to Encapsulation surrounding the 16" Feedwater Piping. Visual Examination of the remaining portion of FDW-H170 support is available for examination.

5. Burden Caused by Compliance: To provide for access to' perform Surface Examination and Visual examination on the Integrally Welded Attachment Saddle Weld for FDW-H170 would require removal of the 16" Feedwater Piping Encapsulation.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-25

6. Proposed Alternative and Basis for Use: No alternative Code required Surface 'examination is available of the FDW-H170 Saddle Weld due to the restricted access-caused by the encapsulation. VT-3 Examinnation of the rd accessible portion of the Support was performed during the 3 Interval.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT. FkPJJWATEER RcM A.-14oHrp5 Th

-L4STMAI /B DRAWING NO.: I S5M - gil COMPONENT IDENTIFICATION: -Fr nWH t-H1 PROCEDURE: AIELPA6.5REVISION: c6it ULTRASONIC: _ LIQUID PENETRANT:_ MAGNETIC PARTICLE: _ VISUAL: X EXAMINER:. 4-7 X-Z 71? DATE: //11/O/

LEVEL EXAMINER:. IAM A/A? DATE: g/,q LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

\ L

, ,,, CZEr4CAPPILLLATiON P1PfL A'RouLNh THE Z FEEDWA-MP L-INE..

r g uTHE 5 ADOL-E WEL-D CA~sq0r BE SEE-4 W KEWAUNEE NUCLEAR C/./ DATz1 i.

POWER PLANT REVIEW: 18. 7.00 12,& eil3f&A/DATE:QcŽCl6?ŽlPoo AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: __ DATE: - ' /

O-t.

FDW-HI 70

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,-1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-26 PROPOSED ALTERNATIVE IN ACCORDANCE WITH'10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 3" Safety Injection Integrally Welded Attachment SI-H17A

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-C; Item No. C3.20

4. Impracticality of Compliance: 1% of Integrally Welded Attachment SI-H17A was inaccessible for Surface Liquid Penetrant Examination due to Welded Name Plate located -next to 2 of the 4 Welded Lugs thus restricting Surface Examination.

5. Burden Caused by Compliance: To provide for access to perform Surface Examination for SI-H17A would require removal and then rewelding of the Name Plate located on the Name ~~ PId the3::

3" Safety Injection Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-26

6. Proposed Alternative and Basis for-Use: No alternative Code required Surface examination is available for the SI-H17A Welded Lug' Area due to-restricted access caused by the Welded Name Plate. VT-3 Examination of the accessible portion of SI-H17A Support and Welded Lugs were performed.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

C. C.

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K:U.1.r XK H

.ETILA ar SECTION B-8 -: .I ." - .

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WISCONSIN PUBLIC SERVICE CORPORATION -REV ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SAfgEfy ITN;YEJCTIOM PUMPS DWcCH.

.SYSTEM OR COMPONENT: PMMG T, VETM asM £h V JST.

DRAWING NO.: ISITN-939-a COMPONENT IDENTIFICATION: Sl-51411 A PROCEDURE:AIEP ?JO. I5d.CREVISION: DR1G.

ULTRASONIC: LIQUID PENETRANT: X MAGNETIC PARTICLE: _ -VISUAL:

- A T D L-r.

A- "La' US: A EXAMINER:, _ UAlt: *LJ I I a LEVEL EXAMINER: Al i DATE: N

/VA LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

51- 14 I NAME VL RTP I aal - FIDRA TOE OF WILM DAJ a L GS P-C-rJTAGE DF EGfUCM EIRMIM RTIODU C-Dm VAGE = 1%

KEWAUNEE NUCLEAR C POWER PLANT REVIEW: f e. &4&/ DATE: o199a7 AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW:. ____________ _________ _ DATE: /' '-EJ P c I/

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-27 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 8" Reactor Coolant Pipe Branch Connection Weld RC-W3BC

2. Applicable Code Edition and Addenda': 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item-No. B9.31

4. Impracticality of Compliance: 42.4% of Reactor Coolant Pipe 8" Branch Connection Weld RC-W3BC was inaccessible for Ultrasonic Examination due to the Branch Nozzle Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access'to perform Ultrasonic Examination for Reactor Coolant Pipe 8" BranchlConnection Weld RC-W3BC would require modification of the original design of the Reactor Coolant Pipe.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-27

6. Proposed Alternative and Basis for Use: No alternative Code requireda Ultrasonic Examination is available for Reactor Coolant Pipe Branch

Connection RC-W3BC due to the Nozzle Configuration. VT-2 Examinations were performed'during the 3 rd Interval as required by ASME ,-

Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item No. B15.50 each Refueling Outage for evidence of leakage. Surface Liquid Penetrant Examination was performed on Reactor Coolant Pipe 8" Branch Connection Weld RC-W3BC during rd the 3 Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-J and Item No. B9.31.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

C CI#- C al aI uK CODE CLASSI -1 "K 3 LOCATION: CONTAINMENT ELEV.6060'-0 SANOPLUG. 810 SHIELD. CAVITY A XK Lb. -

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WISCONSIN PUBLIC SERVICE CORPORATION ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEMORCOMPONENT: 2eAcTbe C-ooerr 'pps Loc? A DRAWING NO.: tsim-1-70S COMPONENT IDENTIFICATION: 1 3 EC. PROCEDURE: P J.i3i REVISION:_ O__

ULTRASONIC: X_ LIQUID PENETRANT: __ MAGNETIC PARTICLE: __ VISUAL:

EXAMINER: - 1 dL Q I ._ < D _ DATE: IL I o3 L 5/

LEVEL EXAMINER: a 4 Z z' DATE: // 96 I'l LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

si---

8-,1 NDOTE: MD SUciJ 5. '5CA g LMLIr ia U ,L bow4 s -eFA4L ByA-6 MET&L o4Ll b1e Tro dopjE(6uesa-oto oF LibJis CiJerdt.

. . 7tcEtxjeL LirkvT-kTIO 4'2.4%I KEWAUNEE NUCLEAR POWER PLANT REVIEW: _ ___DATE: __l____q_

AUTHORIZED NUCLEAR D INSERVICE INSPECTOR REVIEW: DATE: _______

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-28 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 6" Reactor Coolant Pipe Branch Connection Weld RC-W4BC

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.31

4. Impracticality of Compliance: 65.0% of Reactor Coolant Pipe 6" Branch Connection Weld RC-W4BC was inaccessible for Ultrasonic Examination due to the Branch Nozzle Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to perform Ultrasonic Examination for Reactor Coolant Pipe 6"Branch Connection Weld RC-W4BC would require modification of the original design of the Reactor Coolant Pipe.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-28

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic Examination is available for Reactor Coolant Pipe 6" Branch Connection RC-W4BC due to the Nozzle Configuration. VT-2 Examinations were performed during the 3rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item No. B15.50 each Refueling Outage for evidence of leakage. Surface Liquid Penetrant Examination was performed on Reactor Coolant Pipe 6" Branch Connection Weld RC-W4BC during the 3d Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-J and Item No. B9.31.

7. Duration of Proposed Alternative: 3rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEMORCOMPONENT: R^EArToR CooLAm-4 PiPwq LOOP A DRAWING NO.: TS'AM- 1703 COMPONENT IDENTIFICATION: RC-ELl DC PROCEDURE:RE:jo.15.3I REVISION:.FR4E ULTRASONIC: XI LIQUID PENETRANT:.. MAGNETIC PARTICLE:.. VISUAL:

EXAMINEF I. - - . t.

LEVEL DATE: J' 7- 9 EXAMINER: = 6z/4<- DATE: P 576 LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

Re PIPE I-40T L

'74 SCA. - 8 F. ~ t BSt RC.-L A ?4 SCtM 5 burg Tt BRVVC. CLbNF(lqutRArIoM.

-A SCANS '7 BLIMITE IUE To BRACHl Co9FzquWkTIot4.

PRQC.EbuWRE COVERkC REmucsD Eb i3 > US KEWAUNEE NUCLEAR A8 POWER PLANT REVIEW: DATE: 9A?419 AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: ___ DATE: //-9*f

• - ' i- h; ' -  ;;--- '- _

_-::- ,../!;.._ w r .. -,.* .>!23 S . - - . '.. ' . .. '

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-29 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 29" I.D. Reactor Coolant Pipe Circumferential Weld RC-W5

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.11

4. Impracticality of Compliance: 4.6% of Reactor Coolant Pipe 29" I.D.

Circumferential Weld RC-W5 was inaccessible for Ultrasonic Examination due to the O.D. Taper on the Elbow thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to perform Ultrasonic Examination for Reactor Coolant Pipe 29" I.D. Circumferential Weld RC-W5 would require modification of the original design of the Reactor Coolant Pipe.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-29

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic Examination is available for Reactor Coolant Pipe 29" I.D.

Circumferential Weld RC-W5 due to the O.D. Taper on Elbow. VT-2 Examinations were performed during the 3rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item No. B15.50 each Refueling Outage for evidence of leakage. Surface Liquid Penetrant Exanmination was performed on Reactor Coolant Pipe 29" I.D. Circumferential Weld RC-W5 during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-J and Item No. B9.11.

7. Duration of Proposed Alternative: 3rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

Co c I amit1s!

CCDE CLASSI .Im to Vo LOCATION: CONTAINWNT ELEY. CO I A0 SANOPLM~BIG SHIELO. CAVITY A XK

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FUTURE AS BUILT let MnO it P~EFERENCE DRAWIG _ __ I ISI ISCKTRIC NOTESs tINCIONCO2ffT PIPING LOOP A I. wvnmN MINIM M W WftN ,mmm plim'som Mr.

DETAIL B *14 A*IWICIIN or 1444cic IIIO*I.

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WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: /?c4l* rog cooe/A~r el/A/o egop A DRAWING NO.: /A7AI -1743 COMPONENT IDENTIFICATION: --RC - WM PROCEDURE: 46,?/o. /3A/3 REVISION: A.

ULTRASONIC:. X LIQUID PENETRANT:' MAGNETIC PARTICLE:.. VISUAL:

EXAMINER: (- ,

0eJ.0. .xl LEVEL DATE: I) - 30 -- 9 EXAMINER: 9 < _x DATE: /la-63 - 9g LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

.5  :),1< 2 8

'II

- 4 AIOfE: $CA N 2 LiIM ri-D ON (/PSrEAAM 5/Ilr 0i Wvt DUE TO 0.D. 7IPER ON ElBOW - SP6 Pmf loj Agovli PfA'CA'TA(&( OF POCEDURAL iMnrAr0fionP KEWAUNEE NUCLEAR POWER PLANT REVIEW: / 6. DATE:Mo I em&1.Icc8 AUTHORIZED NUCLEAR ,)

INSERVICE INSPECTOR REVIEW: / 5ac- DATE: /-?-

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-30 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 3" Pressurizer Relief Circumferential Weld PR-W12

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.21

4. Impracticality of Compliance: 74.0% of the 3" Pressurizer Relief Circumferential Weld PR-W12 was inaccessible due to a Whip Restraint RRRC39 thus restricting Surface Liquid Penetrant Examination.

5. Burden Caused by Compliance: To provide for access to the 74.0% of the 3" Pressurizer Relief Circumferential Weld PR-W12 would require removal of the Whip Restraint RRRC39.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-30

6. Proposed Alternative and Basis for Use: No alternative Code required Liquid Penetrant examination is available due to the limited access. VT-2 Examinations were performed during the 3rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.50 each Refueling Outage for evidence of leakage.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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PR-W12

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004' RELIEF REQUEST NO: RR-G-7-31 PROPOSED ALTERNATIVE IN ACCORDANCE-WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Pressurizer 6" Nozzle To Safe End Butt Weld PR-WlDM

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table'IWB-2500-1; Examination Category B-F; Item No. B5.40

4. Impracticality of Compliance: 50.0% ofthe Pressurizer 6" Nozzle To Safe End Butt Weld PR-W1DM was inaccessible due to the Carbon Steel Nozzle Configuration and Nozzle O.D. Taper Configuration thus'restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 50.0% of the Pressurizer 6" Nozzle To Safe End Butt Weld PR-W1DM would require modification of the original design of Pressuriier Nozzle to Safe Ends.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-31

6. Proposed Alternative and Basis for Use: No alternative Code required.

Ultrasonic 'examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.20 each Refueling Outage for evidence of leakage. Surface Liquid Penetrant Examination was performed on Pressurizer 6" Nozzle To Safe'End Butt Weld PR-W1DM during the 3 r3dInterval as required by ASME Boiler and Pressure Vessel Code Section XI-1989 Edition: Table IWB-2500-1; Examination Category.

B-F and Item No. B5.40.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST-NO: RR-G-7-32 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Pressurizer 6" Nozzle To Safe End Butt Weld PR-W16DM

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-F; Item No. B5.40

4. Impracticality of Compliance: 50.0%-of the Pressurizer 6" Nozzle To Safe End Butt Weld PR-W16DM was inaccessible due to the Carbon Steel Nozzle Configuration and Nozzle O.D. Taper Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the .50.0% of the Pressurizer 6"' Nozzle To Safe End Butt Weld PR-W16DM would require modification of the original design of Pressurizer Nozzle to Safe Ends.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,u2004 RELIEF REQUEST NO: RR-G-7-32

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during theT3 rd Interval as required by ASME Boiler and-Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; ExaminationCategory B-P; Item B15.20 each Refueling Outage for' evidence of leakage. Surface Liquid Penetrant Examination was performed on Pressurizer 6" Nozzle To Safe End Butt Weld PR-W16DM during the 3 rd Interval as required-by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-F and Item No. B5.40.

rd

7. Duration of Proposed Alternative: 3 Ten Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-33 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Pressurizer 6" Nozzle To Safe End Butt Weld PR-W26DM

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category K. B-F; Item No. B5.40 4.'Impracticality of Compliance: 50.0% of the Pressurizer 6" Nozzle To Safe -0 End Butt Weld PR-W26DM was inaccessible due to the Carbon Steel Nozzle Configuration and Nozzle O.D. Taper Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 50.0% of the Pressurizer 6" Nozzle To Safe End Butt Weld PR-W26DM would require modification of the original design of Pressurizer Nozzle to Safe Ends.

K) Page 1 of2

-KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004' RELIEF REQUEST NO: RR-G-7-33

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT Examinations were performed during 'the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.20 each Refueling Outage for evidence of leakage. Surface Liquid Penetrant Examination was performed on Pressurizer 6" Nozzle To Safe End Butt Weld PR-W26DM during the 3 rd Interval as required byASME Boiler and Pressure Vessel.

Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-F and Item No. B5.40.

K) 7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR oI A1 POWER PLANT REVIEW: 7 6 t DATE: A/oV IIT9.

AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: + DATE: /'-7

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994- JUNE 16,-2004 RELIEF REQUEST NO: RR-G-7-34 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Pressurizer 10" Nozzle To Safe End Butt Weld PR-W67DM

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-F; Item No. B5.40

4. Impracticality of Compliance: 30.0%-of the Pressurizer 10" Nozzle To Safe End Butt Weld PR-W67DM was inaccessible due to the Nozzle Configuration and the Weld Crown Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance. ,To provide for access to the 30.0% of the Pressurizer 10" Nozzle To Safe End Butt Weld PR-W67DM would require modification of the original design' of Pressurizer Nozzle to Safe Ends.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004, RELIEF REQUEST NO: RR-G-7-34 6.Proposed Alternative and Basis for Use: No alternative Code required' Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required byASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table --

IWB-2500-1; Examination Category B-P; Item B15.20 each Refueling Outage for evidence of leakage. Surface Liquid Penetrant Examination was performed on Pressurizer 10" Nozzle To Safe End Butt Weld PR-W67DM during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-F and Item No. B5.40.

7. Duration of Proposed Alternative:= 3 rd Ten Year Interval June 16, 1994 -

June -16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 X RELIEF REQUEST NO: RR-G-7-35 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 12" SafetyInjection Circumferential Weld SI-W120

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.11

4. Impracticality of Compliance: 50.0% of the 12" Safety Injection-Circumferential Weld SI-W120 was inaccessible due to the Valve To Pipe Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 50.0% of the 12" Safety Injection Circumferential Weld&SI-W120 would require modification of the original design of Safety Injection Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16 2004-RELIEF REQUEST NO: RR-G-7-35

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 rd Examinations were performed during the 3 Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category 'B-P;Item B15.50 each Refueling.-

Outage for evidence of leakage. Surface Liquid Penetrant Examination .was performed on 12" Safety Injection Circumferential Weld SI-W120 during the 3 rd Interval as require'd by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-J and Item No. B9.11.

7. Duration of Proposed Alternative: 3 rd Ten' Year Interval June 16, 1994 -

June -16, 2004 8.Precedents: NotApplicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-36 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 12" Safety Injection Circumferential Weld SI-W123

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.11

4. Impracticality of Compliance: 50.0% of the 12" Safety Injection Circumferential Weld SI-W123 was inaccessible due to the Elbow to Branch Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provde for access to the 50.0%.of the 12" Safety Injection Circumferential Weld SI-W123 would require modification of the original design of Safety Injection Piping.

Page-1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994- JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-36

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table --

IWB-2500-1; Examination Category',B-P; Item B15.50 each Refueling Outage for evidence of leakage. Surface Liquid Penetrant Examination was performed on 12" Safety Injection Circumferential Weld SI-W123 rd during the 3rInterval as required by ASME Boiler and Pressure VessseI Code Section'XI 1989 Edition: Table IWB-2500-1; Examination Category B-J and Item No. B9.11.

K) 7. Duration of Proposed Alternative: 3 rd-Ten Year Interval June 16, 1994 -

June-16, 2004 0 DAA.  ; k ATY+ A _ W. ,. .

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9.

References:

Not Applicable

. o II Page 2 of 2

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INSERVICE INSPECTOR REVIEW: - _ _ _ _ DATE:_____

SI-W123 KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-37 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 6" Safety Injection Circumferential

-WeldSI-W13

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table'IWB-2500-1; Examination Category B-J; Item No. B9.11

4. Impracticality of,Compliance: 62.5% of the 6" Safety -Injection Circumferential Weld SI-W13 was inaccessible due to the Valve to Pipe Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To' provide for access to the 62.5% of the 6" Safety Injection Circumferential Weld SI-W13 would require modification of the original design of Safety Injection Piping.

Page 1 of 2

KEtWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-37

6. Proposed Alternative and Basis for Use:'No alternative Code -required:

Ultrasonic examination is available due to the limited access. VT-2' Examinations were performed during the 3 rd Interval as required by ASME' Boiler and'Pressure Vessel'Code Section XI 1989 Edition: Table IVB-2500-1; Examination Category B-P; Item B15.50 each Refueling Outage for evidence of leakage. Surface Liquid Penetrant Examination wa's performed on 6" Safety Injection Circumferential Weld SI-W13 during the 3rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI -1989 Edition: Table IWB-2500-1; Examination Category B-J and Item No. B9.11.

7. Duration of Proposed Alternative: 3-d Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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Sil-W 1 3 KEWAUNEE NUCLEAR POWER PLANT THIRD'10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-38 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 01OCFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 6":Safety Injection Circumferential' Weld SI-W14

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B19.11

4. Impracticality of Compliance: 6.5% of the 6" Safety Injection Circumferential Weld SI-W14 was inaccessible due to a 2" Socket Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 6.5% of the 6" Safety Injection Circumferential Weld SI-W144would require modification of the original design of Safety Injection Piping.

P age 1 ~of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-38

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination-is available due to the limited access. VT-2 Examinations were performed during the-3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.50 each Refueling Outage for evidence of leakage. Surface Liquid Penetrant Examination was performed on 6" Safety Injection Circumferential Weld SI-W14 during the 33rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-J and Item No. B9.11.

KY 7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994- JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-39 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 6" Pressurizer Relief Circumferential Weld PR-W2

2. Applicable Code Edition and Addenda:, 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.11

4. Impracticality of Compliance: 61.3% of the 6" Pressurizer Relief Circumferential Weld PR-W2 was inaccessible due to the 6" Pressurizer ~

Nozzle Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access t-othe 61.3%-of the 6" Pressurizer Relief Circumferential Weld PR-W2 would require modification of the original design of Pressurizer and Presisurizer Relief Nozzle.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-39

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 rd Examinations were performed during the 3rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table  :

IWB-2500-1; Examination Category B-P; Item B15.50 each Refueling Outage for evidence of leakage. Surface-Liquid Penetrant Examination was performed on 6" Pressurizer Relief Circumferential Weld PR-W2-during; the 3 rd Interval as required -by ASME Boiler and Pressure Vessel Code'_

Section XI 1989 Edition: Table IWB-2500-1; Examination Category, B-J and Item No. B9.11.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable 9.

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-40 PROPOSED ALTERNATIVE IN ACCORDANCE WITH -OCFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 8" Residual Heat Removal.

Circumferential Weld RHR-W33'"

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.11

4. Impracticality of Compliance: 62.5% of the 8" Residual Heat Removal Circumferential Weld RHR-W33 was inaccessible due to the Valve Body to Pipe Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To'provide for access to'the 62.5% of the 8" Residual Heat Removal Circumferential Weld RHR-W33 would require modification of the original design of Residual Heat Removal Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-40

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed -during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination'Category B-P; Item B15.50 each Refueling Outage for evidence of leakage. Surface Liquid Penetrant Examination was performed on 8" Residual Heat Removal Circumferential Weld RHR-W33 during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-J and Item No. B9.11.

K) 7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-41 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: !6",Safety Injection Circumferential Weld SI-W108

2. Applicable Code Edition and Addenda: 1989, No Addenda K> 3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.11

4. Impracticality of Compliance: 50.0% of the 6" Safety Injection Circumferential Weld SI-W108 was inaccessible due to the Valve Body to-Pipe Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: Tolprovide for access to'the 50.0% of the 6" Safety Injection Circumferential Weld SI-W108 would require modification of the original design of Safety Injection Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,'2004 RELIEF REQUEST NO: RR-G-7-41

6. Proposed Alternative and Basis for Use:' No alternative Code required Ultrasonic examination is available due to the limited access. VT-22 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.50 each Refueling Outage for evidence of leakage. Surface Liquid Penetrant Examination was performed on 6" Safety Injection Circumferential Weld SI-W108 during the 3 rd IInterval as required by ASME Boiler and Pressure'Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examinatio'n Category B-J and Item No. B9.11.

K.) 7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-42 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 12" Safety Injection Circumferential Weld SI-W67

2. Applicable Code-Edition and Addenda: 1989, No Addenda i 2 3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.11

4. Impracticality of Compliance: 30.0% of the 12" Safety Injection Circumferential Weld SI-W67 was inaccessible due to the O.D. Taper of 12" x 12" x 10" Tee Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 30.0% of the 12" Safety Injection Circumferential Weld SI-W67 would require modification of the original design- of Safety Injection Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-42

6. Proposed Alternative and Basis for-Use: No alternative Code required Ultrasonic examination is available due to the limited access.' VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P;' Item B15.50 each Refueling Outage for evidence of leakage. Surface Liquid Penetrant Examination was performed on 12" Safety Injection Circumferential Weld SI-W67 during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code,'

Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-J and Item No. B9.11.

K) 7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable K)Page 2of 2

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Or AN~m- i N SI-W67

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-43 PROPOSED ALTERNATIVE IN ACCORDANCE WITH41OCFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected:'6" Pressurizer Relief Circumferential Weld PR-W17

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.11

4. Impracticality of Compliance: 51.8% of the 6" Pressurizer Relief Circumferential Weld PR-W17 was'inaccessible due to the Safe End to Elbow Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access toethe 51.8% of the 6" Pressurizer Relief Circumferential Weld PR-W17 would require modification of the original-design of the Pressurizer and Pressurizer Relief Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-43

6. Proposed Alternative and Basis for Use:'No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed du'ring the 3rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table:-

IWB-2500-1; Examination Category B-P; Item B15.50 each Refueling' Outage for evidence of leakage. Surface Liquid Penetrant Examination was performed on 6" Pressurizer Relief Circumferential Weld PR-W17 during'.

theth3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination' Category B-J and Item No. B9.11.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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.xv

KEWAUNEE NUCLEAR POWER PLANT K'

THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-44 PROPOSED ALTERNATIVE

-IN ACCORDANCE WITH IOCFR'50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 10"' Pressurizer Surge Circumferential Weld RC-W64

2. Applicable Code Edition and Addenda: 1989, No Addenda

'I 3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.11

4. Impracticality of Compliance: 21.6%-of the 10" Pressurizer.Surge-Circumferential Weld RC-W64 was inaccessible due to Rigid Restraint RR134-6 Configuration thus restricting Ultrasonic Examination. 12.7% of the 10" Pressurizer Surge Circumferen'tial'Weld RC-W64 was inaccessible due to Rigid Restraint RR134-6 Configuration thus restricting Surface Liquid Penetrant Examination.

5. Burden Caused by Compliance:-To provide-for access to the 21.6% and 12.7% of the 10" Pressurizer Surge Circumferential Weld RC-W64 would require modification or removal of Rigid Restraint RR134-6.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-44

6. Proposed Alternative and Basis for Use: No alternative. Code required Ultrasonic or Liquid Penetrant examination is available due to the limited access. VT-2'Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.50 each Refueling Outage for evidence of leakage.

7. Duration of Proposed Alternative: 3rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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WISCONSIN PUBLIC SERVICE CORPORATION JREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEMORCOMPONENT: PRESSLARIZl& SuR 6E LtI JE DRAWING NO.: E-S r\ - "39 2 COMPONENT IDENTIFICATION: RC - Ld ta' -PROCEDURE:r ,ePrO.IS. PREVISION: 6 -IG.

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,' 1994 - JUNE 16, 2004 i

RELIEF REQUEST NO: RR-G-7-45 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 8" Residual Heat Removal Circumferential Weld RHR-W10

2. Applicable Code Edition and Addenda: -1989, No Addenda

3. Applicable Code Requirement: Table' IWB-2500-1; Examination Category B-J; Item No. B9.11

4. Impracticality of Compliance: 63.0% of the 8" Residual Heat Removal' Circumferential Weld RHR-W10 was inaccessible due to the Valve Configuration and 3/4" Drain Line thus restricting Ultrasonic Examination.

1. 0% of the 8"-Residual Heat Removal Circumferential Weld RHR-W10 was inaccessible due to 3/4" Drain Line thus restricting Surface-Liquid Penetrant Examination.

5. Burden Caused by Compliance: To provide for access to the 63.0% and 1%

of the 8" Residual Heat Removal Circumferential Weld RHR-W10 would require modification of the original design of the Residual Heat Removal Piping.

PAGE 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-45

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic or Liquid Penetrant examination is available due to the limited access. VT-2 Examinations'were performed during the 3 rd Interval as i-required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.50 each Refueling Outage for evidence of leakage.'

rd

7. Duration of Proposed Alternative: 3 Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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WISCONSIN PUBLIC SERVICE.CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: RHA - eOm AC LOOPS A is8orLa658ro -Irmr PEN. '1 cTO cwrSuMp .

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RHR-WI 0 KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-46 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 3" Pressurizer Spray Circumferential Weld PS-W4

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.21

4. Impracticality of Compliance: 8.8% of the 3" Pressurizer Spray Circumferential Weld PS-W4 was' inaccessible due to a 3/4" Line thus restricting Surface Liquid Penetrant Examination.

5. Burden Caused by Compliance: -To provide for access to'the 8.8% of-the 3" Pressurizer Spray Circumferential Weld 'PS-W4 would require modification of the original design of the Pressurizer Spray Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-46

6. Proposed Alternative and Basis for Use: No alternative Code required Liquid Penetrant examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.50 each Refueling Outage for evidence of leakage.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 _-

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE-AND ViSUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: 3" R.C. TO -PUSSURIZUR DRAWINGNO.: I5f a.

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ULTRASONIC: _ LIQUID PENETRANT: X MAGNETIC PARTICLE: __VISUAL:

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POWER PLANT REVIEW: C.-. 77Jj-xw DATE: 30, I'9 so AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: _ DATE: ____/__

PS-W4 KEWAUNEE x 2 NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-47 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected:.10" Residual Heat Removal Circumferential Weld RHR-W188

2. Applicable Code Edition and Addenda: '1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-F-i; Item No. C5.11

4. Impracticality of Compliance: 49.8% of the 10" Residual Heat Removal Circumferential Weld RHR-W188 was inaccessible due 10" x 10" x 6" Tee Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 49.8% of the 10" Residual Heat Removal Relief Circumferential Weld RHR-W188 would require modification of the original design of the Residual Heat Removal Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-47

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 rd Examinations were performed'during the 3 Interval as required by ASME Boiler and Pressure Vessel CodeSection- XI 1989 Edition: Table IWC-2500-1;' Examination Category C-H; Item C7.30 each 3 1/3 Year Period for evidence of leakage. Surface Liquid Penetrant Examination was performed on 10" Residual Heat Removal Circumferential Weld RHR-W188 during the 3 rd Interval -asrequired by ASME Boiler and Pressure' Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-F-1 and Item No. C5.11.

i) 7. Duration of Proposed Alternative: 3rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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47

HR-W KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-48 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 10" Residuaal Het Removal Circumferential Weld RHR-W414

2. Applicable Code Edition and Addenda: 1989, No Addenda K 3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-F-1; Item No. C5.11

4. Impracticality of Compliance: 59.0% of the 10" Residual Heat Removal Circumferential Weld RHR-W414 was inaccessible due to Valve Configuration and 2- 3/4" Line Weldolets thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 59.0% of the 10" Residual Heat Removal Relief Circumferential Weld RHR-W414 would require modification of the original design of the Residual Heat Removal Piping.

K) Page 1 of 2

IKEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-48

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval 'as required by ASME Boiler and Pressure'Vessel Code'Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-H; Item C7.30 each 3 1/3 Year Period for evidence of leakage. Surface Liquid -Penetrant Examination was performed on 10" Residual Heat Removal Circumferential Weld RHR-W414 during --the' 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-F-1 and Item No. C5.11.

K> 7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-49 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 3" Safety Injection Circumferential Weld SI-W234

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-F-i; Item No. C5.21

4. Impracticality of Compliance: 20.0 % of the 3" Safety Injection Circumferential Weld SI-W234 was inaccessible due to the Elbow Intradose Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the'20.0% of the 3" Safety Injection Circumferential WeldSI-W234 would require modification of the original design of the Safety Injection Piping.

Page of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-49

6. Proposed Alternative and Basis for Use: No alternative Code required..

Ultrasonic examination is available -due to the limited access. VT-2 Examinations were performed during the 3rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-H; Item C7.30 each 3 113 Year Period for evidence of leakage. Surface Liquid Penetrant Examination was performed on 3" Safety Injection Circumferential Weld SI-W234 during thethrd 3 Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-F-1 and Item No. C5.21.

rd

7. Duration of Proposed Alternative: 3 Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-50 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 3" Safety Injection Circumferential Weld SI-W262

2. Applicable Code Edition and Addenda: 1989, No Addenda K) -3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-F-1; Item No. C5.21

4. Impracticality of Compliance: 20.0%- of the 3" Safety Injection Circumferential Weld SI-W262 was inaccessible due to the Elbow Intradose Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 20.0% of the 3" Safety Injection Circumferential Weld SI-W262 would require modification of the original design of the Safety Injection Piping.

Page of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-50

6. Proposed Alternative and Basis for Use:' No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed du'ring the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code'Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-H; Item C7.30 each 3 1/3 Year Period for evidence of leakage. Surface Liquid Penetrant Examination was performed on 3" Safety Injection 'Circumferential Weld SI-W262 during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-F-1 and Item No. C5.21.

7. Duration of Proposed Alternative: 3rd- Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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3" Safety:Injecton Wl XSI7-W262->

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994- JUNE 16,-2004 RELIEF REQUEST NO: RR-G-7-51 PROPOSED ALTERNATIVE IN ACCORDANCE WITH-10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 371 Safety Injection Circumferential Weld SI-W249

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-F-,; Item No. C5.21

4. Impracticality of Compliance: 15.5% of the 3" Safety Injection Circumferential Weld SI-W249 was inaccessible due to 4" x 4" x 3" Reducing Tee Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 15.5% of the 3" Safety Injection Circumferential Weld SI-W249 would require modification of the original designiof the Safety Injection Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-51

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table -

IWC-2500-1; Examination Category C-H; Item C7.30 each 3 1/3 Year Period for evidence of leakage. Surface Liquid Penetrant Examination was performed on3" Safety Injection Circumferential Weld SI-W249 during-the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-F-i and Item No. C5.21.

d.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-52 PROPOSED ALTERNATIVE IN ACCORDANCE WITH-10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 3" Safety Injection Circumferential Weld SI-W307

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-F-1; Item No. C5.21

4. Impracticality of Compliance: 47.5%-of the 3" Safety Injection Circumferential Weld SI-W307 was inaccessible due to 3" x 3" x 3" Tee Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 47.5% 'of the 3" Safety Injection Circumferential Weld SI-W307 would require-modification of the original design of the Safety Injection Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,`2004 RELIEF REQUEST NO: RR-G-7-52

6. Proposed Alternative and Basis for 'Use: No alternative Code required, Ultrasonic examination is available due to -the limited access.,VT-2 Examinations were performed during the 3 rd Interval as required by ASME' Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-H; Item C7.30 each 3 1/3 Year X Period for evidence of leakage.-Surface Liquid Penetrant Examination was performed on 3" Safety Injection 'Circumferential Weld SI-W307 during:'

the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-F-i' and Item No. C5.21.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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WISCONSIN PUBLIC SERVICE CORPORATION REV. ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT:SIt FROM cw'tiT Pw. 2SEF TO " oFm Ojv to HOPJO REACOR 4BASC1 COi DRAWING NO.: 15i - q37 -.A5H;s COMPONENT IDENTIFICATION: 5l-,3O7 PROCEDURE: NEP I.W- REVISION: A ULTRASONIC: 2 LIQUID PENETRANT:  : MAGNETIC PARTICLE:.- VISUAL:

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SI-W307

1 '

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-53 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 10" Residual Heat Removal Circumferential Weld RHR-W48

2. Applicable Code Edition and Addenda: 1989, No Addenda K) 3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-F-1; Item No. C5.13

4. Impracticality of Compliance: 7.0% of the 10" Residual Heat Removal Circumferential Weld RHR-W48 was -inaccessible due to the Box Rigid; Restraint RR225 Configuration'thus restricting Surface Liquid Penetrant Examination.

5. Burden Caused by Compliance': To provide for access to the 7.0%0of the 8" Residual Heat Removal Circumferential Weld RHR-W48 would require removal of the Box Rigid Restraint RR225.'

K) Page 1of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-53

6. Proposed Alternative and Basis for Use: No alternative Code required Liquid Penetrant examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-H; Item C7.30 each 3 1/3 Year Period for evidence of leakage.

rd

7. Duration of Proposed Alternative: 3 Ten Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD RH& - FROMI RC LOOPS A .B NioT L.EGS Ja; SYSTEM OR COMPONENT: fWTh7T PE1g 9 Tro CA24!T17 SVM'P A DRAWING NO.: SISMl- q-s - /SH-COMPONENT IDENTIFICATION: RHR- W48. _ PROCEDURE:NepA1 /56 REVISION: ORiG ULTRASONIC: LIQUID PENETRANT: X MAGNETIC PARTICLE:.. VISUAL:_

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-54 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 30" Main Steam Circumferential Weld MS-W3

2. Applicable Code Edition and Addenda:' 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-F-2; Item No. C5.51

4. Impracticality of Compliance: 37.0% ,(Calculated by Kewaunee Nuclear Power Plant) of the 30" Main Steam Circumferential Weld MS-W3 was inaccessible due to the Reducing Elbow O.D. Taper and thickness change configuration thus restricting Ultras'onic Examination.

5. Burden Caused by Compliance: To provide'for access'to the 37.0% of the 30" Main Steam Circumferential Weld MS-W3 would require modification of the original design of the Main Steam Piping.'

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10- YEAR INTERVAL JUNE 16, 1994- JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-54

6. Proposed Alternative and Basis -for Use: No alternative Code required Ultrasonic examination is available'due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category. C-H; Item C7.30 each 3 1/3 Year Period for evidence of leakage. Surface Magnetic Particle Examination was performed on the 30"' Main Steam Circumferential Weld MS-W3 during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-F-2 and Item No. C5.51.

rd

7. Duration of Proposed Alternative: 3rTen Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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6'

KEWAUNEE XJ NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-55 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected:-3" Pressurizer Spray Circumferential Weld PS-W3

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category

1) Item No. B9.21 B-J;

4. Impracticality of Compliance: 27.0% of the 3" Pressurizer Spray Circumferential Weld PS-W3 was inaccessible due to a Branch Connection thus restricting Surface Liquid Penetrant Examination.

5. Burden Caused by Compliance: To proyide for access to the 27.0% of the 3" Pressurizer Spray Circumferential Weld PS-W3 would require modification of the original design of the Pressurizer Spray Piping.

K Page I of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-55

6. Proposed Alternative and Basis for Use: No alternative Code required Liquid Penetrant examination is available due to'the limited access.'VT-2 Examinations were performed during'the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section-XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.50 each Refueling Outage for evidence of leakage.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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AUTHORIZED NUCLEAR - / 7 z INSERVICE INSPECTOR REVIEW: i :DATE: b e{/8

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-56 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 3" Pressurizer Spray Circumferential Weld PS-W34

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J;-Item-No. B9.21

4. Impracticality of Compliance: 37.0% of the 3" Pressurizer Spray Circumferential Weld PS-W34 was inaccessible due to a Whip Restraint RRRC7A thus restricting Surface Liquid Penetrant Examination."

5. Burden Caused by Compliance: To provide for access to the 37.0% of the 3" Pressurizer Spray Circumferential Weld PS-W34 would require removal of the Whip Restraint RRRC7A.'-

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994- JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-56

6. Proposed Alternative and Basis for Use: No alternative Code required Liquid Penetrant examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.50'each Refueling Outage for evidence of leakage.

7. Duration-of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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SYSTEMORCOMPONENT: 3 RC. To ?res-ue;u2. DRAWINGNO.:ISIM- 87Y-J :

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POWER PLANT REVIEW:

A D DATE:

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10- YEAR INTERVAL JUNE 16,1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-57 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

-INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 3" Pressurizer Spray Circumferential Weld PS-W10

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.21

4. Impracticality of Compliance: 36.0% of the 3" Pressurizer Spray Circumferential Weld PS-W10 was inaccessible due to a Hanger Support RRRC19 thus restricting Surface Liquid Penetrant Examination.

5. Burden Caused by Compliance: To provide for access to the 36.0% of the 3" Pressurizer Spray Circumferential Weld PS-W10 would require removal of the Hanger Support RRRC19.-

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10- YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-57

6. Proposed Alternative and Basis for Use: No alternative Code required Liquid Penetrant'examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME-Boiler and Pressure Vessel Code Sectio nXI 1989 Edition: Table IWB-2500-1; Examination Category'B-P; Item B15.50 each Refueling Outage for evidence of leakage.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June -16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable ffi . .

- .,:,0 ,. . .

t; .

Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST-NO: RR-G-7-58 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTIONIMPRACTICALITY

1. ASME Code Component Affected: 30'-' Main Steam Circumferential Weld MS-W50

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination'Category C-F-2; Item No. C5.51

4. Impracticality of Compliance: 8.0% the`30" Main Steam Circumferential Weld MS-W50 was inaccessible 'duetto theO.D. Configuration thus restricting Ultrasonic Examination.-

5. Burden Caused by Compliance: To provide for access to the 8.0% of the 30" Main Steam Circumferential Weld MS-W50 would require modification of the original design of the Main Steam Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-58 Code required

6. Proposed Alternative and Basis for Use:e No . alternative

-'h .. i e. .T 2 Ultrasonic examination is available due tothe limited access. VT-2 d

Examinations were performed during the-3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category'C-H; Item C7.30 each 3 1/3 Year' -

Period for evidence of leakage. Surface Magnetic Particle Examination was performed on the 30" Main Steam Circumferential Weld MS-W50 during the3rd Interval as required by ASME Boiler-and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1;'Examination Category C-F-2 and Item No. C5.51.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

-June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD, SYSTEMORCOMPONENT: 'MAoM CSTzE STEAVA &EtEa@TOe . 16 DRAWING NO.: IS= t - 7 22 COMPONENT IDENTIFICATION: -MkS - Li So PROCEDURE: N EP -ISa oREVISION: e ULTRASONIC: X LIQUID PENETRANT:  : MAGNETIC PARTICLE: - VISUAL:

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KEWAUNEE NUCLEAR POWER PLANT REVIEW:/7 oe&W -_ DATE: lu) I-?o I AUTHORIZED NUCLEAR 9 ivj0 DATE:____ _

INSERVICE INSPECTOR REVIEW: /K

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-59 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 32" Main Steam Longitudinal Weld MS-W9OL

2. Applicable Code Edition and Addenda:' 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-F-2;'Item No. C5.52

4. Impracticality of Compliance: 22.0% the 32" Main Steam Longitudinal...

Weld MS-W9OL was inaccessible due'to the 1" Elbow Taper Configuration thus restricting Ultrasonic Examination..

5. Burden Caused by Compliance: To provide for access to the 22.0% of the 32" Main Steam LongitudinalWeld MS-W9OL would require modification of the original design of the Main Steam Piping. X Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-59

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during'the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-H; Item C7.30 each 3 1/3 Year Period for evidence of leakage. Surface Magnetic Particle Examination was performed on the 32" Main Steam Longitudinal Weld MS-W90L during the' 3d Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination C-F-2 and Item:No.;

C5.52.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June' 16,'-2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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'I DATE: 1_A_/_

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KEWAUNEE NUCLEAR -"4-I POWER PLANT REVIEW: XX& C. /3&& DATE: *IQŽ,b0d]

AUTHORIZED NUCLEAR I.NSERVICE INSPECTOR REVIEW: . DATE: "D /S-/

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-60 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 32" Main Steam Longitudinal Weld MS-W91L

2. Applicable Code Edition and Addenda': 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-F-2;' Item No. C5.52

4. Impracticality of Compliance: 63.0% the 32" Main Steam Longitudinal' Weld MS-W91L was inaccessible due to a 1" Vent Line thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 63.0% of the 32" Main Steam Longitudinal Weld MS-W91L would require modification of the original design of the Main Steam Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994- JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-60

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 -

Examinations were performed during the 3 rd Interval as required by ASME:

Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1; Examination Category C-H; Item C7.30 each 3 1/3 Year Period for evidence of leakage.

7. Duration of Proposed Alternative: 3rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

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-NKEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-61 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected- 32" Main Steam Longitudinal Weld MS-W91L

2. Applicable Code Edition and Addenda: 1989, No Addenda kJ 3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-F-2; Item No. C5.52

4. Impracticality of Compliance: 50.0% the 32" Main Steam Longitudinal Weld MS-W91L was inaccessible due to-a 1" Vent Line thus restricting Surface Magnetic Particle Examination.- -' '

5. Burden Caused by Compliance: To provide for access to the 50.0% of the 32" Main Steam Longitudinal Weld MS-W91L would require'modification of the original design of the Main Steam Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-61

6. Proposed Alternative and Basis for Use: No alternative Code required Surface Magnetic Particle Examination is available due to the limited.

rd access. VT-2 Examinations were performed during the 3 Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table'IWC-2500-1; Examination Category C-H; Item C7.30 each 3 1/3 Year Period for evidence of leakage.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: AAIAJ Sm4M STEAM GQNERATMR 1B DRAWING NO.: XSIUK -`8 COMPONENT IDENTIFICATION: FR-.& ILL PROCEDURE: EPko.f 5-!REVISION: CRIA ULTRASONIC:__ LIQUID PENETRANT:___ MAGNETIC PARTICLE: X VISUAL:

EXAMIINE R A/ X:;7,7- TC _DATE: 10/11/1

LEVEL.

EXAMINER:_ IDATE: L/111i LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

I VENTr LseJf LIMITEb FROM t'4 L+D{

MS_ q L- - AO% RFDaCED COVERACIE.

~.

I :w I ,. . +

KEWAUNEE NUCLEAR 0J POWER PLANT REVIEW: (

A _ __o_ _DATE: _

AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: ., _ ____amp DATE: A

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-62 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 16" Feedwater Circumferential Weld FW-W24

2. Applicable Code Edition and Addenda: 1989, No Addenda K) 3. Applicable Code Requirement: Table IWC-2500-4; Examination Category C-F-2; Item No. C5.51

4. Impracticality of Compliance: 8.0% the 16" Feedwater Circumferential Weld FW-W24 was inaccessible due to the Valve Configuration thus, restricting'Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 8.0 % of the 16" Feedwater Circumferential Weld FW-W24 would require modification of the original design of the Feedwater Piping.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994- JUNE 16, 2004.

RELIEF REQUEST NO: RR-G-7-62

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access'. VT-2::

Exa'minations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table-IWC-2500-1; Examination Category C-H; Item C7.30 each 3 1/3 Year Period for evidence of leakage. Surface Magnetic Particle Examination was performed on 16" Feedwater Circumferential Weld FW-W24'during the 3 rd Interval as required by ASME Boileraind Pressure Vessel Code Section XI-1989 Edition: Table IWC-2500-1; Examination Category C-F-2Xand Item No. C5.51.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

-June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable

'Page 2 of 2

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WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM ORCOMPONENT: FbAr=- FRozt qct4 iqobE, L 70 ST- &1. i6 DRAWING NO.: I5IA - -7 i COMPONENT IDENTIFICATION: FW - Li SZ PROCEDURE: f4EP- 15T.HCREVISION: -I ULTRASONIC: X LIQUID PENETRANT: _ MAGNETIC PARTICLE:.. VISUAL:

EXAMINER: Tv-t Coa Qtq 1 DATE: ID/2 i/ t EXAMINER: AJA P/A DATE: MAA LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATiON COVERAGE.

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KEWAUNEE NUCLEAR 0&_

POWER PLANT REVIEW: DATE: _9_____7___

AUTHORIZED NUCLEAR ii INSERVICE INSPECTOR REVIEW: t - . DATE:_________

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004' RELIEF REQUEST NO: RR-G-7-64 PROPOSED ALTERNATIVE IN ACCORDANCE WITHJ10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Regenerative Heat Exchanger',

Tubesheet to Shell Circumferential Weld

'ARG-W11

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWC-2500-1; Examination Category C-A; 'Item No. C1.30

4. Impracticality of Compliance: 41.4% of the Regenerative Heat Exchanger Tubesheet to' Shell Circumferential Weld ARG-W11 was inaccessible due to Pipe Clamp Connected to Rigid Support Bracket Assembly thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 414% of the Tubesheet to Shell Circumferential Weld ARG-W11 would-require removal and modification of the Rigid Support Bracket Assembly in a 1R -M2Rper, hour Radiation Field of the'Regenerative Heat Exchanger.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-64

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access caused by the Rigid Support'Bracket and the High Radiation Fields. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler' and' Pressure Vessel Code Section XI 1989 Edition: Table IWC-2500-1;'

Examination Category C-H; Item C7.10 each 3 1/3 Year Period for evidence of leakage.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

CI (: (7 80Z -Iw I I RG.' 1. ARGR-2 Ei AOOED REv IS ION PVR0175 ARG-S3I 54 lTUBE ShEET 36. CHA,*ELlrCNI BY: JhS 06-06-00

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SEEREV.0-1 3). CRAVING APPLICABLE FOR 3,d Ef2)lsI FPL3E0 WS 8-3-S9 INTERVAL 2). MIS ROILER AM PPESSUREVESSEL COtE MOC-% I - l O AAC-LE SECtION Xi CLASS 2 T OTt E I2 [ TLE J

rF WISCONSIN PUBLIC SERVICE CORPORATION KEWAUNEENUCLEAR POWERPLANt CARLTON. KEWAUNEECOUNTY. WISCONSIN CALIBRATION BLOCK CTWOWNTwvo OATA OlvIER I S4EKOE I 1. . I I _ASpb4 I REGENERATIVE HEAT EXCHANGER ARG OESIGNED BY WISCONSIN PUBLIC:SERVICE CORP.

135-031 GREEN BAY. WISCONSIN I REV.

LOCATION: CONTAINMENT 593 ELEVATION R. w^c DVG, NO.

CODE I208M-1208 I G

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC) LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: RrE/,J R A TXIC liiE EcAN&5 R

£~ p4R6 DRAWING NO.: Al' Izc, COMPONENT IDENTIFICATION: AR6- w ii PROCEDURE: Nfb?/4. 1517 REVISION: o RI G, ULTRASONIC: DC LIQUID PENETRANT: MAGNETIC PARTICLE: I___IVISUAL:

EXAMINER: 1Xf C7-, 1i aF LEVEL DATE:

EXAMINER: DATE: A-44 LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND

- PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

No scan 5, scan 7 & 8 limited to weld and downstream base metal only, due to pipe clamp connected to rigid support bracket assembly. Scan 2, 7 & 8, also limited to 90% of length due to welded lugs around circumference of vessel.

Reduced procedural coverage: 62.8% / Reduced codecoverage: 41A%

-ARG-W11 4 j~QD;'

. ... .._. C. N 2 KEWAUNEE NUCLEAR " dA POWER PLANT REVIEW: 7 (Q i f DATE: 0 0A9O3 AUTHORIZED NUCLEAR 7' INSERVICE INSPECTOR REVIEW: t DATE: _/__ __ _3

No scan 5, scan 7 & 8 limited to weld and downstream base metal only,cdue to pipe clamp connected to rigid support bracket assemblty. Scan 2, 7& 6, also limited to 90% of length due to welded lugs around cirumference of vessel.

Reduced procedural coverage -62B% I Reduced code coverage: 41A%

, - I m a -A

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,-1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-65 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 12" Reactor Coolant Pipe Branch Connection Weld RC-W50BC

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.31

4. Impracticality of Compliance: 53.0% of Reactor Coolant Pipe 12" Branch Connection Weld RC-W50BC was inaccessible for Ultrasonic Examination' due to the Branch Nozzle Configuration thus restricting Ultrasonic-Examination.

5. Burden Caused by Compliance: To provide for access to perform Ultrasonic Examination for Reactor Coolant Pipe 12"Branch Connection Weld RC-W50BC would require modification of the original design of the Reactor Coolant Pipe.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-65

6. Propos'ed Alternative and Basis for Use: No alternative Code required Ultrasonic Examination is available forReactor Coolant Pipe 12" Branch

-Connection RC-W50BC due to the Branch Nozzle Configuration. VT-2 Examinations were performed during -the 3 rd Interval as required by'ASME Boiler and Pressure Vessel Code SectionlXI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item No. B15.-50 each Refueling Outage for evidence of leakage. Surface Liquid Penetriant Examination was performed on Reactor Coolant Pipe 12" Branch Connection Weld RC-W5OBC during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code-Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-J and Item No. B9.31.

7. Duration of Proposed Alternative:' 3rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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WISCONSIN PUBLIC SERVICE CORPORATION IREV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND, VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: 2RCA-roe doovy Ak ij4r LooP Q DRAWING NO.: IS1h -170O COMPONENTIDENTIFICATION: eC -l 6C PROCEDURE: t1tP 4a. 1S.39 REVISION:. ort ULTRASONIC: X LIQUID PENETRANT: MAGNETIC PARTICLE:.. VISUAL:

EXAMINER: _ __ -__._LEVE DATE: -_ __7____

/ / LEVEL*

EXAMINER: Au: z ( ti- DATE: L-17-03 LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

No scan 2, scan 7 &8 limrbd IDweld and upstream base metal only, due to branch comecUon contiguration.

Reduced procedural coverage: 53%

KEWAUNEE NUCLEAR Az POWER PLANT REVIEW: tj______ go _ ____ DATE: Wa 2OLT3 AUTHORIZED NUCLEAR I,4SERVICE INSPECTOR REVIEW: _ DATE:___________

No scan 2, scan 7 & 8 limited to Weld and upstream base metal only, due to branch connection configuration.

Reduced procedural coverage: 53%

.. . ............t.

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, -1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-66 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION-IMPRACTICALITY

1. ASME Code Component Affected: 12" Safety Injection Circumferential Weld SI-W75

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category

< LIQUID PENETRANT: MAGNETIC PARTICLE:.. VISUAL:

EXAMINER:E  :

/ I

_ _ _ _ _E____ DATE: _

LEVEL EXAMINER: A.W 5 sSF A6LeL DATE: H-Io8-03, 6' LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

No scan 5, scan 7 & 8 limited to weld and downstream base metal only, due to valve to elbow configuration.

Reduced code coveras lee: 50% - \ : .- : - .

KEWAUNEE NUCLEAR POWER PLANT REVIEW: ,? e:.xi~ DATE: d, o 3 AUTHORIZED NUCLEAR 74H4 INSERVICE INSPECTOR REVIEW: DATE: q-2-0 3

( 0

No scan 5, scan 7 & B limited to weld and downstream base metal only, due to valve to elbow configuration.

Reduced code cavmraae 50% .I

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-67 PROPOSED ALTERNATIVE IN ACCORDANCE WITH41OCFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 12" Safety Injection Circumferential Weld SI-W119

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.11

4. Impracticality of Compliance: 50.0% of the 12" Safety Injection Circumferential Weld SI-W119 'was inaccessible due to the Elbow to Valve Configuration thus restricting Ultrasonic Examination.

5. Burden'Caused by Compliance: To provide for access to the 50.0% of the 12" Safety Injection Circumferential Weld SI-W119 would require modification of the original design of Safety Injection Piping'.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 ;

RELIEF REQUEST NO: RR-G-7-67

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.50 each Refueling Outage for' evidence of leakage. Surface Liquid Penetrant Examination was performed on 12" Safety Injection CircumferentialWWeld SI-W119 during the' 3rd Interval as required by ASME Boilerr and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-J and Item No.

B9.11.

7. Duration of Proposed Alternative:' 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

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REFERENCE OWGS.

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WISCONSIN PUBLIC SERVICE CORPORATION IEV. ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: LI - xiOm A eCjAW/A-r /A 7n LooP -A ! aCZ Le-&

DRAWING NO.: /SIm- 93S7 COMPONENT IDENTIFICATION: 5'- wil ' PROCEDURE: 3P -1rc'if REVISION: A ULTRASONIC: Y -- LIQUID PENETRANT: _ MAGNETIC PARTICLE:.. VISUAL:

EXAMINER: _ DATE: q.21f- o

. LEVEL :J-EXAMINER: _ DATE:

LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

No scan 2, scan 7 & 8 limited to weld and upstream base metal only, due to elbow to valve configuration.

Reduced code coverage: 50%

i Iii KEWAUNEE NUCLEAR zz POWER PLANT REVIEW: C eI

& 4AZ DATE: baJ ,aaa AUTHORIZED NUCLEAR $ y INSERVICE INSPECTOR REVIEW: 4

/- -' DATE:_______

No scan 2, scan 7 & 8 limited to weld and upstream base metal only, due to elbow to valve configuration.

Reduced code coverage: 50%.

-X I:

Mt S ,

m4 '* -,

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 JUNE 16,'2004 RELIEF REQUEST NO: RR-G-7-68 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 6" Safety Injection Circumferential Weld SI-W47

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item'No. B9.11

4. Impracticality of Compliance: 50.0% 'of the 6" Safety Injection Circumferential Weld SI-W47 was inaccessible due to the Pipe to Valve Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 50.0% of the 6" Safety Injection Circumferential Weld SI-W47 would require modification of the original design of Safety Injection Piping.

Pag 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994'- JUNE 16,--2004 RELIEF REQUEST NO: RR-G-7-68

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and -Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item B15.50 each Refueling',

Outage for evidence of leakage. 'Surface Liquid Penetrant Examination was performed on 6" Safety Injection Circumferential Weld SI-W47 during the 3 rd Interval as required by ASME Boile'r and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1;:Examination Category B-J and Item No. B9.11.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

C ( (i, AN CONAIgeNf SSW t'DCATIOP4CONTAiNPElNl I - -I II.

M. ' I1 - o I r,- 0; '

.. hmmsmilt I -

A 1*11

- go 1 *2 Wo RE____ rE____ NOTES.

A-I, - a KAP01-001639 ' mre " " "*

^

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEMORCOMPONENT: 5PiFETY iNL)J6cria^g F1cri cCNrtqr PA&. q9 7Do A,4c-ra DRAWING NO.: ISIe- '7315h.1 COMPONENT IDENTIFICATION: -5L-aoq7 _PROCEDURE: IqEP - IS-q, REVISION: A ULTRASONIC: X LIQUID PENETRANT: MAGNETIC PARTICLE: VISUAL:

EXAMINEF I. /&-A/

7 LEVEL DATEF Y21 /0 EXAMINER: 'IHd DATE:  : IAS LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

No scan 2, scan 7 & 8 limited to weld and upstream base metal onl due to pipe to valve configuration REDUCED CODE COVERAGE: 50%

SCAN 8

• . .E .j I

A 2 SCAN

- -; _SCA*~

N AIL O':

KEWAUNEE NUCLEAR POWER PLANT REVIEW: Zf4-4 7 ° ), ( AJea'&.-) DATE: A a 3 AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: / DATE: -°3

No scan 2, scan 7 & 8 limited to weld and upstream base metal only, due to pipe to valve configuration REDUCED CODE COVERAGE: 50k 0*' __<:A

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-69 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY,

1. ASME Code Component Affected: 6" Reactor Coolant Circumferential Weld !RC-W29

2. Applicable Code Edition and Addenda-:1989, No Addenda' A

3. Applicable Code Requirement: Table IWB-2500-1;' Examination Category B-J; Item No. B9.11

4. Impracticality of Compliance: 50.0 % of the 6" Reactor Coolant Circumferential Weld RC-W29 was inaccessible due to the Pipe to Nozzle Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 50.0% of the 6" Reactor Coolant Circumferential Weld RC-W29 would require modification of the original design of

.;9 .

Reactor Coolant Piping.'

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE'16,2004 RELIEF REQUEST NO: RR-G-7-69

6. Proposed Alternative and Basis for 'Use: No alternative Code required Ultrasonic examination is available due to the limited access. VT-2 Examinations were performed during'the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition:' Table -

IWB-2500-1; Examination Category.B-P; Item7B15.50 each Refueling-'

Outage for evidence of leakage. Surface Liquid Penetrant Examination was' performed on 6" Reactor Coolant Circu'ihferential Weld RC-W29 during.,

the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-14 Examination Category B-J and Item No. B9.11.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

C C 0

• 135 WI13W304 I *I55*to0

• W6 SI-W44GS iUAof "M XK H

- n SI-W4G~s DETAL B UETIL C S-was DETAL OCTALD VT SI-WS42S LOCATIOh.CONTA*JCNI CAVITYA ELEY.106'

-4e~ COUCTAPe4TBLSEI0NT WA 40 45j \kA4 W4 l.W4 ROM~i~

'M I M i la MWE .* _ I KU13 -4 ll.."A pRI 1-. - Y'SINI'sIrl...

___ 02 i ff 1-I.--

• 4y ERENTM D WM RM A . A_

I m La" Mggm nriI

.

• I.I .

WISCONSIN PUBLIC SERVICE CORPORATION REV.: ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: $1 - rgoN cjlregr EN, 2-8N no flqt-r95g w6 Cc44 1Lt- tXScC DRAWING NO.: IS te -?F2 -

COMPONENT IDENTIFICATION: AC! - W29q -' ' PROCEDURE: NEP-r/.jL REVISION: oA ULTRASONIC: X LIQUID PENETRANT: -- _ MAGNETIC PARTICLE: VISUAL:

EXAMINER: DATE: W1/21 /,02

. / A LEVEL EXAMINER: DATE: / //

- xLEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

No scan 2, scan 7 & 8 limited to weld and upstream base metal only, due to pipe to nozzle configuration.

REDUCED CODE COVERAGE:-60%-  ; :. - .

KEWAUNEE NUCLEAR B POWER PLANT REVIEW: ha DATE:

AUTHORIZED NUCLEAR INSERVICE INSPECTOR REVIEW: 4I . . DATE:, _

j*-g. -o3

No scan 2, scan 7& 8 limlted to weld and upstream base metal only, due to pipe to valve configuration

REDUCED CODE COVERAGE: .50%

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-70 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: 27.5"' I.D. Reactor Coolant Pipe,

'Circumferential Weld RC-W19

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-J; Item No. B9.11

4. Impracticality of Compliance: 54.0%'of Reactor Coolant Pipe 27.5" L.D.

Circumferential Weld RC-W19.was inaccessible for Ultrasonic Examination due to the Reactor Coolant Pump To Pipe Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to perform Ultrasonic Examination'for Reactor Coolant Pipe 27.5" I.D. Circumferential Weld RC-W19 would require modification of the original design of the Reactor Coolant Pump and Reactor Coolant Pipe.-'

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1 994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-70

6. Proposed Alternative and Basis for Use: No alternative Code'required Ultrasonic Examination is available-for Reactor Coolant Pipe 27.5" I.D.

Circumferential Weld RC-W19 due to the Reactor Coolant Pump To Reactor Coolant Pipe Configuration. VT-2 Examinations were performed during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination Category B-P; Item No. B15.50 each Refueling Outage for evidence of leakage.

Surface Liquid Penetrant Examination was performed on Reactor Coolant Pipe 27.5" I.D. Circumferential Weld RC-W19 during the 3 rd Interval as required by ASME Boiler and Pressure Vessel Code Section XI 1989 Edition: Table IWB-2500-1; Examination 'Category B-J and Item-No. B9.11.

7. Duration of Proposed Alternative: 3 rd-Ten Year Interval June 16, 1994 -

June 16,-2004

8. Precedents: Not Applicable 9.

References:

NotApplicable Page 2 of 2

( C(

A I

---

CODECLASSI

• Si U Sn

.tC, XK H LOCATIONSCONTAINMENT ELEV. 606'-0r SANDPLUG. 010 SHIELD, CAVITY A

.j --- SA

.1'*

DCR KAP 01-00632 DETIL IA-34OI DETAIL A VIE116.00KIN vaTWne

~ ram.Sttl~ln-2AS-

• wto-~ AVISI ADC0 PLU KAPft01-O mCV R~EFERENCE DRAWINGS Ili SIC S 3C *t E. 61-5*

MI! ISOPETRIC I~

NOTESs REACTORCOLANT PIPINES

. - LOP A OA-Uo WPLICMLI FOR 31d A ELK DETAIL a f~t JLRISUICTIOOF ASK SECTION St. w. ~~ P- li S6 VtE winlto scfiu~litm 26 tLUSSI PIPIW. ) I)25'110 he LESS IS [,.1 Pa."

IO

WISCONSIN PUBLIC SERVICE CORPORATION ORIG.

KEWAUNEE NUCLEAR POWER PLANT ULTRASONIC, LIQUID PENETRANT, MAGNETIC PARTICLE AND VISUAL EXAMINATION LIMITATION TO EXAMINATION RECORD SYSTEM OR COMPONENT: ReAsCaTO tLow-A-t PtiG L-oop A DRAWING NO.: 161M - I'l 0 3 COMPONENT IDENTIFICATION: 1 QC- WlA _ PROCEDURE: MeP MJo. ig- 13 REVISION: A ULTRASONIC: X LIQUID PENETRANT: MAGNETIC PARTICLE: VISUAL:

EXAMINER: A.w'. ST/ aL(L- .. LEVEL DATE: q-21-03 0

EXAMINER: -F DATE: C /12t/03 6// / 4LEVEL SKETCH TO PROVIDE: APPROXIMATE SIZE, LOCATION, ORIENTATION, TYPE OF LIMITATION AND PERCENTAGE OF REDUCED EXAMINATION COVERAGE.

No scan 5, scan 7 & 8 limited to weld and downstream base metal only, due to pump to pipe configuration.

Reduced procedural coverage: 54%

I I

':;-M I

f i I

• . .f . . F I

KEWAUNEE NUCLEAR POWER PLANT REVIEW: C..734[CO' , DATE: are J ° AUTHORIZED NUCLEAR ) '

INSERVICE INSPECTOR REVIEW: -v , /'/104,.2 DATE: I-22 -c 3

No scan 5, scan 7 & 8 limited to weld and downstream base metal only, due to pump to pipe corfiguration.

Reduced procedural coverage: 54%

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-71 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Reactor Vessel Shell To Flange Weld RV-W1

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination'Category B-A; Item No. B1.30

4. Impracticality of Compliance: 25.56%'(Single Side Coverage) and 46.98%

(Two Direction Coverage) of the Remote Ultrasonic Examination 'of the Reactor Vessel Shell To Flange Weld RV-W1 was inaccessible due to the Flange To Shell Configuration thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 25.56% (Single Side Coverage) and 46.98% (Two Direction Coverage) of the Reactor Vessel Shell To Flange Weld RV-Wi would require modification of the original design of Reactor Vessel.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-71

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic exami nation is available due to the limited access.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16, 2004

8. Precedents: Not Applicable

9.

References:

Not Applicable

. S Page 2 of 2

C C 1:.CZ Y REVISION HIILLW POO CotI COWVL SEE REV 0- I APPO, OsCAT 10/23/89 AY 34B F ILM' DoIwPSI, iI /7/89 PE S 2-I177 VA-54 I MINP AS DVI. E. SAXTON 4/3/93 DWIDB. TROTTER 9112/13 I-VA P A L APP 0j CAT7-23-13 ,

_gj ES9-1T77COW SEEREV. A-I tIUIEO. IWS) 08-03-93

17. L. AA' C 7 Iv - . ASASOA4 I NVl-El RV-CS$ REFERENCE W1144 PERESR92-177

.I By, 1-NI 10-1-73 -

C14'T. RJS t0-4-93

-!1 APP'Di CAT10-07-13 OVILET NOZZLES - KINEYNPA2ZfES d REFERENCE 13194 -9 REFERENCE 11944 SEEREV. B-I l0. TV TOTO FIL'EO,I WPS)10-19-93 REACTORVESSEL I 1 ADDEDITEMA.

NOZZLSPADs BY: BJD 7-Il-Il fl-tS2 MGDAl-CS APP'Oa OAK7-26-n I A PCFERENCE W1134

• H REFERENCE*-13194 NOZZLE1-PADS .DJREFUR029ZII f4 IPA S / BY-tW aRl CII SEEREV.C-I . ..

• . . . . 4.. . BY-Ic FILCOiIIP#S) 8+99"

/

/ REISE NOTE P41 .

BY:4 ABF06-03-0?

/ CIAJETER. 1W ID APP0:-

/ .wL ETE SEECREtOR-1

---

NOTES, . KAP01-001639 -

BY-Al / >1 I.DRAWINGAPPLICABLE FOR 3.-d CA- II NERA

/ / 2Z. ASKc BOILER ANsOPRESSUE VESSEL CODE

/ cow SuRpeR GUITS IA)- / SECTIONX'1CLASS IL.

/ REFERENCE *3195

/ 3). RV INSTRUECNT PENETRATION ID -So RI-Ril~

THRIURV-P30 7 /

• • WISCONSIN PUB8LIC SERVICE CORPORATION 1I KEWAUNEE NUCLEAR POWER PLANT LI

- 'CARLTON. KEWAAUNEE COUNTY, WISCONSIN _~~

I:t REACTOR .VESSEL~~.-:~:-,~'~..

DESIGNED By-HlEAD BOTTON WISCONSIN ,PUBLIC; SERVICE:CORP.

GREEN BAY., W SCONSI - -

1,I57 011, 04 6 E V F JECT APYOV o

- LOCAtION.' CCATAIN*EINA D $9 t NO.

wG. * - REV.

I I .I 11,I m

REATORVESEL ELDRESULTS

SUMMARY

PLANT NAME K w neUnti WELD NO. RV-Wl COMPONENT ':Shell -toFlange Weld LMTATIONS: NO [.Y S :74.44 % C6mpiete(Single Sided Coverage).~

See Coverage Breakdown Sheet RESULTS 'NO. OF INDICATIO'NS N/A NI X -STATUS .7 N/A'-

R I. _ _

K-)

-'EXAM DOCUMENTATION INDICATION DOCU'MENTATION EJPARAGON ANALYSIS LOG =ZASSESSMENTSHEET.-

LEK PARAGON ACQUISITION LOG LIPARAGON HARD' COPY:,

KI SCAN PRINTOUT E- OTHER (Specify)

Exl COVERAGE BREAKDOWN Comments: See figures 1 and 2 for limitation Anal-yst I' D ae

C ROV. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME I IKewaunee ..

.Wes' yvn e WELD NO. RV-WlI, Internatio'nal.

COMPONENT, Shellto Flange Weld; A A BEAM ANGLE BREAK~DOWN-,,

77 AASING II LE SIDE COVERAGE"'

BEAM DIRECTIONi AjWELD 45 Shear-,

jIVOLUME j J 4LSige45 EDIOUWELDELD L D"ual.

VOLUME I ,WELD.VLM

.romSea'I Surf.!, ft W

, , :; 1' -

I . I :,. C.

I . . I. I , I

,~Perpendlicular: 100.00 .-100.00 88.93""

A54 55, 0.0 2.5 100.00! 491.00 Parallel' 1I00.00 l'57.64'~1 00.00,~57.64 100.00 57.64: A

[A ERAGE 189.41 1 75.28. 45.92 I Cme t :C v ra ge e t m te o t e, s e l PI Ex ma e ba e n si g es de co vera g e.

Combined Pep  :'~,70.07 -A~, -" Comnbined'Para.- 78.82 .:t:- Combined Average'-i A :74*44t-1 An'alyst. /,; . A.?/A Date.

RECTRVESSEL WELD RESULTS

SUMMARY

PLANT NAME .Kewaunee. Unit __ _ _ _ _ _ _ _ _ _ _ _

WELD NO. RV-W1 COMPONENT Shell to Flang'e" Weld, LIMITATIONS: '~~NO f- tYES fx :53.02 % omple~te (Tw~o Directions)

See Coveraige Breakdow'n Sheet RESULTS NO. OF INDICATIONS ~N/A' NI X STATUS N/A RI _ _ _

'EXAM DOCUMENTATION-., INDICATION DOCUMENTATION:

EIPARAGON ANALYSIS LOG - EASSESSMENTSHEET:~~,:

WIPARAGON ACQUISITION LOG EIPAIRAGON HARD:COPY E]ISCAN PRINT OUT]' fL7I] OTHER (Specify)

WCOVE RAGE BR EAKDOW Cmments:. Sefurs1ad 2 for limitations '

Analysi tN;Dt:/ )

. I , . c yl N- c -

R.V. COVERAGE ESTIMATE BREAKDOWNS WROMENMENNOMM 1 PLANT NAME Kewaunee i i,

. ,,i, .

..E,, .

, i g

WesDyne.

WELD NO.

RV-WI * . .

s , ]e N

• r w' P r ,,*z -

International ..

jiSE

' 2 * ? tsiS w

'de,}'x' r _, ' L .;S' ",,1;-,

COMPONENT

' l . .  ! .  :,

Shell to Flan'ge Weld I I Ii

.. : .. - ,:. . ' i' .:,  !::',' ,: w , ?:1:, ... :

.'. ,','-' 0 0'.' ", . '- a}'. ., ' . ',',.

- 1 ; I I .

._.1: " I I c I i-i:; :0 XBEAMANGLEBREAKDOWN: i -:-; N-.:

.; I TWonlIPFrCTIONIAI:OVFRA(EP :-  :.^  ;  :

BEAM DIRECTION. 45 Shear'.- 45 L ige45

_______jWELD: VOLUME WED VOLUMEJ WELD Loua romSan uf . 111;1. I I II

~]VOLUME WELD] VOLUME

[ Perpendicular: 0.00- :0' 0.00 .3.78 ...,..0.00; .f22.92 :100.002 91.00 Parallel - 100.001 57.64 100.00 57.64 100.00 57.64 _

AVERAGE- 3.41- 4035, 45 14  ; 95.50

Comments: Coverage estimates'for the shell PDI xamare ased o 2 direta

,' -m e; n

erage

_, ' _e' tr ,t"e's a e f r , ,. i@ .Wf. b e re'zo I:W Crpm i e P 272 Com bine P r.7 82Co'mbinied Average ,53.02 ,

. Analyst  ;,

. ,, . /

Date

.I 19.3 21.44 25,3 . =25.31- Top PParallel 27,65 Top Perp 31.26- /32.755Bott. Poaratel

/

-.37.92 Bott--Perp I:I P 65.91 -

.25-

-4

, =

- X

- - F-lgure 1-

.f .

i j :

Vit eI- ,

19 ,7:

I-251 F

Figu~re c .

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVALIJUNE 16, 1994 - JUNE 16,2004' RELIEF REQUEST NO: RR-G-7-72 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION IMPRACTICALITY

1. ASME Code Component Affected: Reactor Vessel Safety Injection Nozzle To Vessel Weld RV-W11

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table' IWB-2500-1; Examination Category B-D; Item No. B3.90

4. Impracticality of Compliance: 11.69% (Two Sided Coverage) of the Remote Ultrasonic Examination of the Reactor Vessel Safety Injection Nozzle to Vessel Weld RV-W11 was inaccessible due to the Safety Injection Nozzle Protrusion thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 11.69-% (Two Sided Coverage) of the Reactor Vessel Safety Injection Nozzle to Vessel Weld RV-W11 would require modification of the original design of Reactor Vessel Safety Injection Nozzle.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE'16, 2004 RELIEF REQUEST NO: RR-G-7-72

6. Proposed Alternative and Basis for Use:'No alternative Code required Ultrasonic examination is available due to-the limited access.' However, 90.04% coverage of the Reactor Vessel Safety Injection Nozzle to Vessel Weld RV-W11 was achieved performing Remote Ultrasonic Examination with personnel qualified for performing Single'Sided Examination of the Reactor Vessel Safety Injection Nozzle To Vessel Weld RV-W11.

7. Duration of Proposed Alternative:' 3 d Ten Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

C C 0IIC .

REVISION

) .. r:  : . ,. . , I . 1. .. II I CC 1GI1-H Poo 0011 COWLi SEE REV 0-I .

APP'Dt CAT 10/23/39 PILWD:IWPSI 11/7/69 FtlAt.OS t I. Aaa mv-S: nHg AV-IS4 mErzvvCz Pn-11i Is---

co.neiY wtu d

i.O.

OAT.

I M-iO44Cl- 2S -I-I PER (SR 922177 Ovie E. SAOTCN 4/I/93 CHr Os L. TROTTER 5/1 2/53 Aer Di CAT7-23-91 7S72-l COWL IBRATIRS4ON CALI LI AIA& SEEREV.'A-I FILWODII.PSI 08-0n-9i mKPERENCCE WIt54 PER ESR 92-Ill RY-CSS I mV-CS6 AEEREENCEW*114 /-* BY: NL~t 10-1-713 OCwDt BJS 10-4-9fl APro, CAT10-07-23'

• 75.Sr- TOTOP tgsT NOZZ~LE ESR 92-177 COMs..

OF REACTORVESSEL1 OUUTN11 LS.171 . SEE B-REV REFERENCE NittY4 .JEFEAEICE n-1I94 T0DEDITEMNO.

• P. t OAK7-26-fl iiB 25COMPL_

U SEEREVCE-t

'IL"ICDWS) 5_3-flq WE0SEO NOTEI-21 AICBOLE At PEVESSELSL OD IT AOFOG-03-02 7*? Di IISONSN UCLAR OW N~i ' ._r "" ' ".. t  : ;L , .CARLYON.1~ KE AU E C UN ECORPORATION. I

• R PLANT. I ri. wiscONSIN ,'l.'

I" r . ' :' , . I ,I . I

'REACTORIVESSEL WISCONSIN PUBLIC tSERVICE CORP.

INSUT MI OPENI CS GREEN BAY.'WISCONSIN 7 ic ..ov%0 . --

04Cd(0 I 1 57- 011I -C. C 0 L U.M I I. I I . -

,-- ==I-RE _ =V I OR. , CWG.. NO.

CONTAIT#CNT f CADO, Gg ,; '--'. kI - 11 93 :  :, I E :!

LOCATIOM

. I 1. , , " 1, , I . . I

C C I REVISION V61I4I tlP0-00163S I

IPXLETE

.,. o.-I-K SEEREV.' t1.l FI MN~ I WDS) o, R'. L  ! -. tWts , oTR C-I I REoRAFTED TOCAD 44 4i PERESR92-177 RV .1 44 -a-64 w EL. C Ls DNA E. SAXION 4/I/tg HI.IR6 I<t,25 u stco ^5 05C t.

• c kw*0, S. TROTTER 5S/2/91 APPD CAT7-ZI-S1 PJESR 92-Ill CatL.

s. E 90-t ar suirc l SEEREV. A-l FILfO.IWS) 04-03-93 1.tV..OJ1'Thf#NUPI !RStTFR4 PER[SR 92- 1" 10 If Q LlT' 6 -V 9t )F64tCL 2t Sy, Lt. 10 1-,

C' D, RJS.10-4-"

"w.S1Km4

.6 ^s i R 49 lirDs CAT10-07-93 UESR 92-177 CWL SEEREV.9-1 FILI(OD.Wg 10B1--3 CE:lJ PDtR0149 TEVISED WELDATTCE.

OATA. ADDEDIhLET AO I OUTLETNOZZELWELODATA 81 .LSPICE 2-21-97 I iplli I.  ;: .

V I'*w we-.

.M4: ICi tLO ZI ts. APPftPCU 02-21-97 2J PDR 0149 COWPL SEEREV.C-

- - - - - -.SW fILWOVPS) 02 2541 Sr-WI. 20 l 0-I RE PLR 0295 IprE. 2SI N9ti-lI aCCO lD11(1 O BYg 9JD 7-9-9S AVIV0.OAK7-256s9 E-1 _EJE PtR 0295 COIAPL KAP 01-001639 SEEREV.0-D fIL0lfW9 8-3-29 NOTES, ElKAP 01 I0163 It. DRAWINGAPLICADLE FR de dISI INTERVAL RUISED OTE 1.

TYsA8F 06-03-02

21. ASpe BOILER ANOPRESSURE VESSEL CODE 1W Di SECTION XI CLASS I l-WISCONSIN PUBLIC SERVICE CORPORATION KEWAUNEENUCLEAR POWERPLANT CARLTON. KEWAUNEECOUNTY. WISCONSIN REACTOR VESSEL NOZZLES AND INTEGRALLY WELDED ATTACHMENTS DESIGNED BY WISCONSIN PUBLIC SERVICE CORP.

1tw GREEN BAY. WISCONSIN

_I PHILL

• ICE 157-011 U.m,,, C.O_ a _ .I 0 I I REV.

LOCAlIDk CONTAIM-ENT FI ADD ~ -Nn lIM- t194 IF

- I ,  :-  :: I 1, , - ,

REACTOR VESSEL-WELD RESULTS

SUMMARY

PLANT NAME, K eauinee Unit __

WELD NO. 'RV-Wl - COMPONENT Safety Injection Noz-Shell '@288.5° LIMITATIONS:' NO'Li YES 83Clete (two sided cover ge)

'. - . See Coverage Breakdown'Sheet-RESULTS 'NO. OF INDICATIONS:

NI ' STATUS 'Code Allowable R IX EXAM DOCUMENTATiON'. INDICATION DOCUMENTATION F- PARAGON ANALYSIS LOG I'MASSESSMENT SHEET

-PARAGON ACQUISITION LOG, ' .-, :' W- Ll PARAGON HARD COPY WESCAN PRINT'OUT EZ-OTHER (Specify)

' COVERAGE BREAKDOWN

]E I

Comments:

Coverage calculation is based on the Bore and and the Tan Scan (parallel).'Figure-1 depicts the limitation.-.`iw-'

- ~F;

- -t, Star scan (combined) as perpendicular.'.

- = : r- . _ . I Analyst -Datia:.1A4

- 1 . ,

I - .. v - ,  : , : :- , - II .I .

.II I p - m I I ..

.: 1 - , ,:

1, I. . . , . o . I I II i I . 11 I  ;

. w, 1. I . I II . I RN. COVERAGE~ ESTIMATE BREAKDOWNS*

I . I I I.

PLANT NAME Kewaunees I I " ', -.. : , I, '!

I , : i ,,,I , .

We'sD I

WELD NO. RV-Wll -

ne rnal tionals . I4 .

COMPONENT ,,'.',~SafetyIInjecion' Noz-Shel @ED288.50 . . .

. . q

. 1 7,

- I '. I . I I .

[, ,

, I , ': :BEAM.'ANGLESREAKDOWW t , . 1

-- I ." , II

, -,, I- .. I i,

. I , , , : : , ." . , , e-

.:- , 1' ' ,I I .,

. m I I

~, ~-; >TWO SIDED COVERAGE~ t-1  :

D RMC I N BE 1 j[EL 4 5Shear VOLUME

[

WELD 45LL ingle VOUME j 45 L D ualJ E D jVOLUMVEJ

]Co mbined B ore/Sta ED(V L M

,T AN S ca n _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

"Parallel, 100.,00 5000 100.00, 65.36 100.0 64 .11 _ __ _ _ _ _

Co mbin6 e d B or-e &Star _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Perpendicula-r,'" __ _ _ _ _ _ _ _ _ _ _100.00 :93.09 AVERAGE. -75.5 82.68 . 82.06 96.54, Commen n hts: Co6vercag calculation- is,based on the Bore and Star. scain' (comnbined) as perpendicular,~~],..

and the Tan:Scan (pralle) F g r 1 de icts the limitation Combined Perp.- 96.54 Combined Para' 80.08 Combined Average 881 Anal St _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _D a te ' 3'

RECTR ESELWEDRESULTS

SUMMARY

---~",.

PLANT NAME KwueUn it WEDN.RVWI . CMPNENT, ~Safety Injiection Noz-ShelI @P288.501 LIMITATIONS::- ..NO Li -YES ]j 90.04'% Comet (ingl'ie coverage)

.See Coverage Breakdown Sheet-RESULTS N.OF INDICATIONS 1 NI ____.STTSCode Allowable RIX EXAM DOCUMENTATION -INDICATION DOCUMENTATION:,

W:PARAGON ANALYSIS LOG. EKJASSESSMENT SHEET, LflPARAGON ACQUISITION LOG~ WPARAGON HARD: COPY FTI SCAN PRINT OUT ZIOTHER'(Specify)

.: xCOVERAGE BREAKDOWN,-~~-~.

Comments:,.:,,

Coverage calcula6tioii is based on the-Bore and Star scan-(colmbined) as perpendicular, and the Tan Scan'(parallel). Figurel1 epicts the limitation. -,

Analyst/ Date:,/

-- RN.. COVERAGE ESTIMATE BREAKDOWNS C`

PLANT, NAME Kewau-nee WELD NO RV-W I n-ternatna COMPONENTI'`.~ Safety linjection" Noz-Shell @a-288.50 BEAM ANGLE BREAK DOWN BEA

__________I________

DIETO ~ 5Sear SINGLE SIDED COVERAGE 45LSnge4 L Da Cobine~d.Bore/Star,

____________jWELD. ~.VOLUME -WELD~. IVOLUME 1,WELD VOLUME].WELD VLM J TAN Sca n _ __ _ __ ___ __`_ _ _

Parale . 100.00 51 .00 100.00 65.36 100.00 64.1 1___

C om bi e B r & tar _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Perpendicular-___ _______ 10 0.00 100.00 AVE RAGE 75.50 8682.6100.0 Comments Coeaecluainiae Nth Bore and Sar sca'n-(c'om!fbined) "as perpendicular, and the'Ta Scn(arle). Figure1 depicts te lmiaon Comnbined Perp. 1_j00.00 Combined Para. 80.08 Combined Average,,, 90.04 Analst

_ _ _ _ __ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ D ate f /

p. I. L I . . . .

LL I; r , . II I : . - ,L I, I: . I; .L - , . . L

. I L  : f :, , , , L, .Lr I I

- :: C

/

r I.

Tn\/St Cverage cilItl ustration i

s -a e00-

-~h U -Tu n--St ar C-o . v~ eige-of- the -Safetyinjection- Nzzle

-Protrusion-Limitation.

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16,1994 - JUNE 16,2004 RELIEF REQUEST NO: RR-G-7-73 PROPOSED ALTERNATIVE IN ACCORDANCE WITH 10CFR 50.55a(g)(5)(iii).

INSERVICE INSPECTION -IMPRACTICALITY

1. ASME Code Component Affected: Reactor Vessel Lower Head Circumferential Weld RV-W4

2. Applicable Code Edition and Addenda: 1989, No Addenda

3. Applicable Code Requirement: Table IWB-2500-1; Examination Category B-A; Item No. B1.21

4. Impracticality of Compliance: 13.86%- (Two Direction Coverage) of the Remote Ultrasonic Examination of the Reactor Vessel Lower Head Circumferential Weld RV-W4 was inaccessible due to the 4 Lower Core Supports thus restricting Ultrasonic Examination.

5. Burden Caused by Compliance: To provide for access to the 13.86% (Two Direction Coverage of the Reactor Vessel Lower Head Circumferential Weld RV-W4 would require modification of the original design of Reactor Vessel.

Page 1 of 2

KEWAUNEE NUCLEAR POWER PLANT THIRD 10 - YEAR INTERVAL JUNE 16, 1994 - JUNE 16, 2004 RELIEF REQUEST NO: RR-G-7-73

6. Proposed Alternative and Basis for Use: No alternative Code required Ultrasonic examination is available due to the limited access. However, 90.82% coverage of the Reactor Vessel Lower Head Circumferential

Weld RV-W4 was achieved performing Remote Ultrasonic Examination with personnel qualified for Single Sided Examination' of the Reactor Vessel Lower Head Circumferential Weld RV-W4.

7. Duration of Proposed Alternative: 3 rd Ten Year Interval June 16, 1994 -

June 16,2004

8. Precedents: Not Applicable

9.

References:

Not Applicable Page 2 of 2

C . C C).

i, I l..".,"p,., 7, . . I I, . : ,

. q T

I 4tH I) ALAfl I E PDO CO1l COWLt SEE REV 0-I APP' 0: CAT 10/23/89 IN Fa41t nV-t 111flMCS meu RV- FILW 0' ( W*SIhAI M783 q, A-1I ' '

PERESR92-177 fl-C'S &~ ,~ R)FC RENCRE.CM*11 3 DI-%. SA tITON 4/1/13 IR4-N I TeF. 14E5XL 4-T.E I 2 ( C),wOuL, TROTTER 51/22/12 APr Os CAT7-23-13 ,

• j-j ESR 92-Ill cOaft.

SEEREV. A-I~ ~*

FItJEO.I1.PSI 08-03-13 IW- H-A '2  ; S A.~

PERESR92-I 2

, 1 I. I  : L BY: LII.1i093" RVCSa"CSRUEFRECE *41114 . , : i m, ., oro0 RJS I0;4-9V APMDI CATI100733 a O~1LZT cisis ' REACTOI VESSEL ErJESR ~92-177Ca.

SEEREV.B-I RFRNE114 FILfOIWPS) ID-1-931

' RFEYERO4ICt W1114 IOE.WTOR VESSE EUITEMN 11 Bri 840 7-19-15 I  : : i APP0, OAKt7-26-fi' I REEPEREICE *1I34 REPUR0255 COWL.

SEEREV. C-1 FILWIOIAPSI 8-3-n>'

KAP1-001o3 SE55 NOTE I.,

BY: ASP06-03-St cAP I-1 ETE --

REREFERENCE 4IIl4S D-1 SEEREV.B-I.

FILMED,I WPS)

NOTES, . KAP 01-;001639'-

II. DRAWING APPLICABLEFO .d4 ItI. INTERVAL, El. ASKEBOILERtIC PRESSURE VESSELCOOS fl ORATE, t SECTIONXIICLASS I K 3I- RV INSTRUPENT PEICKTRATION ID *S. RA-PI *'

TI-tRURV-P384 WISCONSIN PUBLIC SERVICE CORPORATION -

w III IKEWAUNEE NUCLEAR POWER PLANT -L,',

-" , CARLTON. KEWAUNEE COUNTY. WISCONSIN.

REACTOR, VESSEL,.

~,RV DESIGNED BY C WISCONSIN PUBLIC:SERVICMt CORP.s

-I NSTRIUJKN I0'ENIIS- -GREEN BAY. WISCONSIN'~

-1 57- 01 1'

,I LOCATlOet CG4TAIMNENT J

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I -11I 7 '

K) REACTOR VESSEL WELD RESULTS ~

SUMMARY

'.~,~~::~-.'

PLANT NAMI E au ne Ke~~w u n it _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

WELD NO. RV-W4 ~~'COMPONENT' Lower Shell to Lower. Head LIMITATIONS:' -NO flY S ee90.82 % Complete (one Direction)

SeCoverage Breakdowni Sheet LTSNO.'OF -RES INDICATIO N N/A NI X ST T SN/A

'R I _ _ _

EXAM DOCUMENTATION. - ~INDICATION DOCUMENTATION; LKIPARAGON ANALYSIS LOG' EIASSESSMENT SHEET EliPARAGON ACQUISITION LOG []PARAGON'HARDCOPY.

W ANPIT OUT -OTHER.(Speiy WCOVERAGEBRAD W Com mens':Se figuel or limitatio ns

- .Analyst El 'Date: Z Y L/

0V iC; CL R.V. COVERAGE ESTIMATE BREAKDOWNS PLANT NAME, Kewaunee.:~,

i We'sDyn WE LD NO.; RV-W4:'

Inernatina COMPONEN Lowei ,Shell to Lower Head

,,,:~BEAM ANGLE BREAK DOWN'.:

ONE'DIRECTIONAL COVERAGE BEAM DIRECTO T7,45 Shaea 4LSingle 4 ul ___

______WELD. VOLUME ' WELD jVOLUME[,WELD- JVOLUME WELD- VOLUME Perpendicular 100.00~ ~100.00~ 83.56 88.35 ,79.451, 86.04 _____

Paralel .100.00, ['92.55 100.00 92.55 :79.45: 87.86 ___

~,AVERAGE i:.98.14~ 11 83:20 ______

Commrents: Coverage esti m'ates for the shell PDI e-xa:marebasdoIdietnacvrg.

Comhbined Perp. 895 ~ Combined Para. 92.07: Combined Average.', 90.82:I;-

Anays ADate' NI) ~

I I . .

1. t, . I . I 11 . . . . . I II , . - I i, I I

. I q11, - . I, I I I I .02 I1. I- , " I  : - , !- ` .

REACTOR VESSEL WELD RESULTS

SUMMARY

PLANT NAME. kewaunee UnitI WELD NO.. RV-W4 COMPONENT Lower Shel to Lowe Head LIMITATIONS: NO rj1 ~ YES Li _86.14 % Complete (Two Directions):

See Coverage Breakdown Sheet REUL'NO. OF INDICATIONS N/A NI X -'STATUS NA-RI _ _ _

EXAM DOCUMENTATION NDCTODCUMENTATION

[LX ARAGON ANALYSIS LOG EASSMN HE

[K] PARAGON ACQUISITIONLOG II PARAGON HARD Copy-rISCAN PRINT'OUT EIOHE (Specify)'

[KUCOERAGE BREAKDOWN Comments:, See figure 1fo lmtatos .

It

(c I I , 11 , 1, ' t . I 1:

C R.V. COVERAGE ESTIMATE BREAKDOWNS 7 , . , I I I I II il I I .1 . .f, PLANT

' . - t .w INAME'.' 111.., Kewaunee

- : : 1: 71 I'- I WeDynel,.

WELD NO.t" RV-W4 Anternational COMPONENT Lowe Shell to Loer Head

-. ;BEAM ANGLE, BREAK~ DOWN

, tI~~, '. 1~ ; ,-!_, ~TWO DIRECTIONAL COVERAGE,. ,

_______ WL' ___WELD, OLM WELD',: [VOLUME ~WELD' IVOLUME Perpend icular 79.45 80.,58 79.45, 79.53 79.45 82 .74 ___

Paral lel1 100.00 92.55 1A00.00 92 .55 79 .45 87.86 ___

AVRGE ~ 88.15-, 87.88 82.38 t C tio I I'o Co mnm ents Coverage esti mnate :for the shell PDI exa ar based on2 dcire to a o e a e CombinedlPlerp. , ';--80.20 ~. Combined Para. 20 Combined Average861 An a ly st _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Date L I 6,, ' . .w .

I ,, :. ' , :7 , . ,

I I I

-' I ;

- TOP PERP 80.5' BOTT PARALLEL Figure 1