ET 06-0010, Inservice Inspection Program Plan for the Third Ten-Year Interval and 10 CFR 50.55a Requests I3R-01, I3R-02, and I3R-04

Inservice Inspection Program Plan for the Third Ten-Year Interval and 10 CFR 50.55a Requests I3R-01, I3R-02, and I3R-04

ML060720142
Person / Time
Site:	Wolf Creek
Issue date:	03/02/2006
From:	Garrett T Wolf Creek
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ET 06-0010, RG-1.147, TAC M93381, TAC MB1206, TAC MC6437, TAC MC6438
Download: ML060720142 (210)

Text

I I X I W&OLF: CREEK

'NUCLEAR OPERATING CORPORATION Terry J. Garrett Vice President Engineering March 2, 2006 ET 06-0010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Reference:

Letter ET 05-0014, dated September 28, 2005, from T.J. Garrett, WCNOC, to USNRC

Subject:

Docket 50-482: Inservice Inspection Program Plan for the Third Ten-Year Interval and 10 CFR 50.55a Requests 13R-01, 13R-02, and 13R-04 Gentlemen:

Pursuant to ASME Section XI, IWA-1400(c), enclosed is the Inservice Inspection (ISI) Program Plan for the third ten-year ISI interval at Wolf Creek Generating Station (WCGS).

Letter ET 05-014, referenced above, submitted 10 CFR 50.55a Request Number 13R-03 for the third ten-year ISI interval separate and prior to the program plan and relief requests being submitted at this time to help expedite its review.

Pursuant to 10 CFR 50.55a(a)(3)(i), Wolf Creek Nuclear Operating Corporation (WCNOC) hereby requests NRC approval of the following two (2) 10 CFR 50.55a Requests (Attachments 1 and 2) for the Third Ten-Year Interval of WCNOC's ISI Program, which began on September 3, 2005.

Attachment 1 provides 10 CFR 50.55a Request Number 13R-01, which requests an alternative to the requirements of ASME Section Xl, Tables IWB-2500-1 and IWC-2500-1 (Examination Categories B-F, B-J, C-F-1 and C-F-2), which stipulate the selection and examination requirements for Class 1 and 2 piping welds. This alternative provides an acceptable level of quality and safety as required by 10 CFR 50.55a(a)(3)(i). The proposed alternative in this 10 CFR 50.55a request was previously approved by the NRC for Wolf Creek's second ten-year ISI interval in letter dated December 13, 2001 (TAC No. MB1206), from USNRC to 0. L. Maynard, WCNOC.

RO. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Oppor-unity Employer M/F/HCNET

ET 06-001 0 Page 2 of 2 provides 10 CFR 50.55a Request Number 13R-02, which requests an alternative to the ISI requirements of ASME Section Xl, Tables IWB-2500-1, IWC-2500-1, and IWD-2500-1, for Class 1, 2, and 3 Vessel Welded Attachments. This alternative provides an acceptable level of quality and safety. The proposed alternative in this 10 CFR 50.55a Request was previously approved by the NRC for the Tennessee Valley Authority in NRC letter dated July 18, 2005 (TAC Nos. MC6437 and MC6438) for the remainder of their current interval or until such time that Code Case N-700 is approved for use in Regulatory Guide 1.147.

Pursuant to 10 CFR 50.55a(g)(5)(iii), Wolf Creek Nuclear Operating Corporation (WCNOC) hereby requests NRC approval of the following 10 CFR 50.55a Request (Attachment 3) for the Third Ten-Year Interval of WCNOC's ISI Program, which began on September 3, 2005. provides 10 CFR 50.55a Request Number 13R-04, which requests relief from the requirements of ASME Section Xl, Table IWF-2500-1, Category F-A, Item Number F1.40 which requires that 100% of Class 1 supports, other than piping supports, be subject to a visual, VT-3 examination once every inspection interval. This relief is requested on the basis that compliance with the specified requirements is impractical.

The proposed alternative in this 10 CFR 50.55a request was previously approved in NRC letter dated 10/24/1997 (TAC No. M93381), from USNRC to 0. L. Maynard, WCNOC, for Wolf Creek's second ten-year ISI interval as Relief Request 12R-14.

WCNOC requests approval of the three (3) 10 CFR 50.55a requests included as attachments to this submittal by February 1, 2007.

There are no commitments contained within this letter. If you have any questions, please contact me at (620) 364-4084 or Mr. Kevin Moles at (620) 364-4126.

Sincere, Terry J. Garrett TJG/rIt : 10 CFR 50.55a Request Number 13R-01 : 10 CFR 50.55a Request Number 13R-02 : 10 CFR 50.55a Request Number 13R-04 Enclosure cc: J. N. Donohew (NRC), w/a, w/e W. B. Jones (NRC), w/a, w/e B. S. Mallett (NRC), w/a, w/e Senior Resident Inspector (NRC), vila, w/e

- 10 CFR 50.55a Request No. 13R-01 to ET 06-0010 Page 1 of 7 10 CFR 50.55a Request Number 13R-01 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

Alternative Provides Acceptable Level of Quality and Safety

1. ASME Code Components Affected All Code Class 1 and 2 piping welds previously subject to the requirements of ASME Section Xl, Table IWB-2500-1 (Examination Categories B-F and B-J) and Table IWC-2500-1 (Examination Categories C-F-1 and C-F-2).

2. Applicable Code Edition and Addenda ASME Boiler and Pressure Vessel Code,Section XI 1998 Edition through 2000 Addenda

3. Applicable Code Requirement ASME Section XI, Tables IWB-2500-1 and IWC-2500-1 for Examination Categories B-F, B-J, C-F-1 and C-F-2 stipulate the selection and examination requirements for Class 1 and 2 piping welds.

4. Reason for Request ASME Section XI Examination Categories B-F, B-J, C-F-1, and C-F-2 originally contained the requirements for the nondestructive examination of Class 1 and 2 piping welds. In 2001, a risk-informed (RI) methodology for the inservice inspection (ISI) of Class 1 and 2 piping welds was applied at the Wolf Creek Generating Station. The RI ISI process used in this application is described in Electric Power Research Institute (EPRI) Topical Report (TR) 112657, Rev. B-A, "Revised Risk-informed Inservice Inspection Evaluation Procedure." The RI-ISI application was also conducted in a manner consistent with ASME Code Case N-578-1, "Risk-informed Requirements for Class 1, 2, and 3 Piping, Method B."

This risk-informed application met the intent and principles of Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-informed Decisions On Plant-Specific Changes to the Licensing Basis" and Regulatory Guide 1.178, "An Approach for Plant-Specific Risk-Informed Decisionmaking Inservice Inspection of Piping."

The original RI-ISI template, "Risk-Informed Inservice Inspection Program Plan - Wolf Creek Generating Station (Revision 1)" was submitted to the NRC for approval per 10 CFR 50.55a(a)(3)(i) in Wolf Creek Nuclear Operating Corporation (WCNOC) Letter No.

ET 01-0009, dated February 15, 2001, from R. A. Muench, WCNOC, to USNRC. Based upon the information provided in the RI-ISI template, the request to implement the RI-ISI methodology on Class 1 and 2 piping welds was approved by the NRC for Wolf Creek's second ten-year ISI interval in letter dated December 13, 2001 (TAC No. MB13206), from USNRC to 0. L. Maynard, WCNOC. The purpose of this current request is for the continued application of the RI-ISI methodology on Class 1 and 2 piping welds during to ET 06-0010 Page 2 of 7 the third ISI interval based on the alternative providing an acceptable level of quality and safety.

5. Proposed Alternative and Basis for Use The proposed alternative is to continue applying the Risk-Informed ISI criteria of EPRI TR-1 12657 during the third ISI interval in lieu of the requirements of ASME Section Xl, Table IWB-2500-1 (Examination Categories B-F and B-J) and Table IWC-2500-1 (Examination Categories C-F-1 and C-F-2).

When Wolf Creek submitted their initial RI-ISI application to the NRC for approval, the following standard clause was included in the template submittal:

'The RI-ISI program is a living program requiring feedback of new relevant information to ensure the appropriate identification of high safety significant piping locations. As a minimum, risk ranking of piping segments will be reviewed and adjusted on an ASME period basis. In addition, significant changes may require more frequent adjustment as directed by NRC Bulletin or Generic Letter requirements, or by industry and plant specific feedback."

Most U.S. nuclear power plants have implemented RI-ISI Programs with this standard clause to perform periodic reviews and updates. To address this issue, NEI 04-05, "Living Program Guidance To Maintain Risk-Informed Inservice Inspection Programs For Nuclear Plant Piping Systems" has been developed. As part of the ISI Program Update for the third ISI interval at Wolf Creek, a RI-ISI Living Program Evaluation was performed in accordance with NEI 04-05. The objective of this evaluation was to review plant and industry activities that could impact the bases of the Wolf Creek RI-ISI application as it enters the third ISI interval.

In accordance with NEI 04-05, the following aspects were considered during the evaluation:

• Plant Examination Results

• Piping Failures

- Plant Specific Failures

- Industry Failures

• PRA Updates

• Plant Design Changes

- Physical Changes

- Programmatic Changes

- Procedural Changes

• Changes in Postulated Conditions

- Physical Conditions

- Programmatic Conditions to ET 06-0010 Page 3 of 7 The RI-ISI Living Program evaluation resulted in the following three issues being addressed in the RI-ISI application:

• The Class 2, 4" NPS (nominal pipe size) auxiliary feedwater lines from the outboard isolation valve to the connection to the main feedwater piping in all four trains were added to the RI-ISI Program. This resulted from a change in ASME Section Xl Code criteria wherein Class 2, 4" NPS and smaller auxiliary feedwater piping is no longer exempt.

• The Conditional Core Damage Probability (CCDP) and Conditional Large Early Release Probability (CLERP) values for the Class 2, 4" auxiliary feedwater piping addressed above were higher than the upper bound values previously used in the risk impact analysis. New upper bound values of 1.44E-2 and 1.44E-3 were used in the updated risk impact analysis for CCDP and CLERP, respectively.

• Based on ongoing industry experience with Primary Water Stress Corrosion Cracking (PWSCC), Assumption No. 7 in the Degradation Mechanism Evaluation was deleted. This assumption had stated the following:

"Bi-metallic welds with Inconel buttering are not considered susceptible to the PWSCC degradation mechanism."

For the third interval, Wolf Creek will volumetrically examine all of the piping welds that are potentially susceptible to PWSCC. At Wolf Creek, this consists of 14 Examination Category B-F welds where piping attaches to the reactor pressure vessel and pressurizer.

During the update of the Wolf Creek ISI Program in preparation for their third ISI interval, other minor corrections were identified (e.g., correction of weld numbers) and were evaluated as part of the RI-ISI Living Program Update. These had no impact on the RI-ISI Program beyond requiring minor editorial corrections to the RI-ISI Program documents.

The RI-ISI Program was reevaluated for the three issues and other minor corrections using the applicable portions of the same risk-informed process that originally established the risk-informed inspection program. The reevaluation was performed by inserting the new information at the appropriate levels of the analysis. All of the cases that were evaluated in the risk impact analysis during the original RI-ISI application were reevaluated using the new information that was determined for the current application. Results of the risk impact reanalysis were that the overall plant risk as measured as a change in Core Damage Frequency and Large Early Release Frequency was further decreased as a result of the application of the new information. As such, the RI-ISI application on Class 1 and 2 piping welds still maintains an acceptable level of quality and safety.

A summary table of the welds in the RI-ISI Program along with any changes resulting from the issues addressed above is provided in Attachment 1.

to ET 06-0010 Page 4 of 7

6. Duration of Proposed Alternative This 10 CFR 50.55a Request is being proposed for use during the third inspection interval that begins on September 3, 2005 and ends on September 2, 2015.

7. Precedents The proposed alternative in this 10 CFR 50.55a Request was included in a second interval Relief Request for Wolf Creek. This Relief Request was submitted to the NRC for approval per 10 CFR 50.55a(a)(3)(i) in WCNOC Letter No. ET 01-0009, dated February 15, 2001, from R. A. Muench, WCNOC, to USNRC. Based upon the information provided in the RI-ISI template, the request to implement the RI-ISI methodology on Class 1 and 2 piping welds was approved by the NRC for Wolf Creek's second ten-year ISI interval in letter dated December 13, 2001 (TAC No. MB1206), from USNRC to 0. L. Maynard, WCNOC.

Resubmittal of a RI-ISI application on Class 1 and 2 piping welds has been conducted by the V.C. Summer Nuclear Station for their third ISI interval in SCE&G Letter No. RC-04-0148, dated September 8, 2004. The NRC review of this V.C. Summer 10 CFR 50.55a Request is currently ongoing.

Attachment 1 to ET 06-0010 Page 5 of 7 Attachment 1 Inspection Location Selection Comparison Between ASME Section XI Code and EPRI TR-112657 by Risk Category Risk Failure Potential 1It Approved RI-ISI Interval New RI-ISI Interval System"') Consequence Code Category WlI Category Rank Rank DMs Rank Coeunt Wo_______d_

RI-ISI Othert 2 ) Weld RI-ISI lOther(2)

AB 6 Low Medium None Low C-F-2 154 0 155 0 AE 2 High High TASCS Medium C-F-2 0T ° 0T 9(3) 60)

AE 2 High High TT Medium C-F-2 o0) _ __) 8(3) _ 2(3 _

AE 4 Medium High None Low C-F-2 0'3) 0) . 4(3) 1(3 AE 5 (3) Medium (High) Medium TASCS, (FAC) Medium (High) C-F-2 16 2 16 2 AE 6 (3) Low (High) Medium None (FAC) Low (High) C-F-2 108 0 104 0 AL 6 Low Medium None Low C-F-2 ) 0W) 12603) o0 BB 2 High High TASCS, TT Medium B-J II 3 11 3 BB 2 High High TASCS Medium B-J 6 2 6 2 BB 2 (2) High (High) High IT, (PWSCC) Medium (Medium) B-F o(4) 0(4) 1(4) o(4 B-F 1(4) 0(4) 04) o0)

BB. 2 High High TT Medium B-i 20 6 20 6 BB 4 (2) Medium (High) High None, (PWSCC) Low (Medium) B-F o(4) 0(4) 13(4) 5(4 BB B-F 13(4) 5(4) o'0 o0) 4 Medium High None Low B-J 268 21 268 24 BB 6 Low Medium None Low B-J 18 0 18 0 BG 2 High High TASCS Medium B-J 9 2 9 2 BG 2 High High TT Medium B-J 9 3 9 3 BG .B-i 26 3 263 4 Medium High None Low C-F 2 2 C-F-I 72 9 72 9 BG 5 Medium Medium TT Medium B-J 7 2 7 2 BG 6 B-J 12 0 12 0 Low Medium None Low .

C-F-I 39 0 39 0 BG 7 Low Low None Low C-F-I 18 0 18 0

Attachment 1 to ET 06-0010 Page 6 of 7 Attachment 1 Inspection Location Selection Comparison Between ASME Section XI Code and EPRI TR-112657 by Risk Category Risk Failure Potential I 1" Approved RI-ISI Interval New RI-ISI Interval System~1l) ConsequenceIoeCaeoy Wl R-SI1ter 2 T

Category Rank anks Rank [ Count RIISI Other Count l RI-ISI Other(2 "

BN 4 Medium High None Low C-F-I 3 0 3 0 BN 6 Low Medium None Low C-F-I 122 0 121 0 EF 6 Low Medium None Low C-F-2 26 0 26 0 EJ 2 High High TASCS, TT Medium B-J 2 0 2 0 El 2 High High TASCS Medium B-J 8 2 8 2 B-l 4 I 4 1 EJ 2 High High TT Medium C-F-I 4 3 4 3 B-i 22 3 22 3 EJ 4 Medium High None Low B-J2 1 22 l 3

.C-F- I 434 l 44 ll434 44 B-J 2 0 2 0 EJ 6 Low Medium None Low C-F-I I 0 1 0 EJ 7 Low Low None Low C-F-I 47 0 47 0 EM 2 High High TT Medium B-i 8 0 8 0 B-J 20 3 20 3 EM 4 Medium High None Low I 2 0 I C-F-I 2 0 2 0 EM 5 Medium Medium IGSCC Medium B-i 20 2 20 2 B-i 104 0 104 0 EM 6 Low Medium None Low

. C-F-I 205 0 205 0 EM 7 Low Low None Low C-F-I 38 0 38 0 EN 6 Low. Medium None Low C-F-I 93 0 93 0 EP 4 Medium High None Low B-J 20 2 20 2 EP 5 Medium Medium IGSCC Medium B-J 12 2 12 2 EP 6 Low Medium None Low B-i 83 0 83 0

Attachment 1 to ET 06-0010 Page 7 of 7 Attachment 1 Inspection Location Selection Comparison Between ASME Section XI Code and EPRI TR-112657 by Risk Category Risk l Failure Potential 1' Approved RI-ISI Interval New RI-ISI Interval System"'

egjor L R Rank Consequence None DlIs Low Rank 1 Code Category Weld Count lRI-ISI 2 l CW RI l 2)

GS71 1 Lo, I ~LowNoe I LW I C12 2 112 10 1 a Notes

1. System designations are as follows:

AB - Main Steam System AE - Main Feedwater System AL - Auxiliary Feedwater System BB - Reactor Coolant System BG - Chemical and Volume Control System BN - Borated Refueling Water Storage System EF - Essential Service Water System EJ - Residual Heat Removal System EM - High Pressure Coolant Injection System EN - Containment Spray System EP - Accumulator Safety Injection System GS - Containment Hydrogen Control System

2. The column labeled "Other" is generally used to identify augmented inspection program locations that are credited beyond those locations selected per the RI-ISI process, as addressed in Section 3.6.5 of EPRI TR-I 12657. This option was not applicable for the Wolf Creek Generating Station RI-ISI application. The "Other" column has been retained in this table solely for uniformity purposes with other RI-ISI application submittals.

3. Due to a change in ASME Section XI Code criteria, 4" NPS Class 2 auxiliary feedwater piping was added to the ISI Program, and therefore the RI-ISI Program, for the first time during the third ISI interval. This consisted of Class 2 piping from the outboard isolation valve to the first check valve (i.e., system "AL") and piping from the first check valve to the branch connection to feedwater (i.e., system "AE") in all four trains. This piping and its associated weldments were outside the scope of the original RI-ISI application.

4. Changes to the information shown for former Code Category B-F welds reflect the implementation of MRP-139 as an augmented examination and mitigation program.

- 10 CFR 50.55a Request No. 13R-02 to ET 06-0010 Page 1 of 3 10 CFR 50.55a Request Number 13R-02 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)

Alternative Provides Acceptable Level of Quality and Safety

1. ASME Code Components Affected All ASME Section Xl Code Class 1, 2, and 3 Vessel Welded Attachments

2. Applicable Code Edition and Addenda ASME Boiler and Pressure Vessel Code, Section Xl 1998 Edition through 2000 Addenda.

3. Applicable Code Requirement Relief is requested from the requirements of:

Table IWB-2500-1, Examination Category B-K, Footnote 4; Table IWC-2500-1, Examination Category C-C, Footnote 4; and Table IWD-2500-1, Examination Category D-A, Footnote 3.

4. Reason for Request This 10 CFR 50.55a Request addresses two issues. First, ASME Section Xl, 1998 Edition through 2000 Addenda, Table IWB-2500-1, Examination Category B-K, Footnote 4; Table IWC-2500-1, Examination Category C-C, Footnote 4; and Table IWD-2500-1, Examination Category D-A, Footnote 3; do not include specific criteria for the selection of welded attachments in situations where a plant has multiple vessels of similar design, function and service. The requirements in these Footnotes do specify that "only one welded attachment of only one of the multiple vessels shall be selected for examination,"

but no additional criteria are provided for the selection of the appropriate welded attachment.

Second, these Footnotes do not provide any specific criteria for the selection of welded attachments on single vessels. The current wording under the "Extent of Examination" in Tables IWX-2500-1, Categories B-K, C-C and D-A can be interpreted to require that all welded attachments on a single vessel be examined. This wording has since been reconsidered by ASME Section Xl and Code Case N-700 has been published to clarify the requirements for examining welded attachments on both multiple and single vessels.

One of the bases for Code Case N-700 was previously published Code Case N-509, "Alternative Rules for the Selection and Examination of Class 1, 2, and 3 Integrally Welded Attachments," which was incorporated into ASME Section Xl in the 1995 Addenda. The technical basis of Code Case N-509 concluded that there have been very few welded attachment failures identified during normal Section Xl examinations.

Instead, failures have been identified when the connected support member has been found to be deformed due to operational transients or water hammer events. For this reason, Code Case N-509 and Section Xl versions that include the 1995 and later to ET 06-0010 Page 2 of 3 Addenda require welded attachments to be examined whenever component support deformation is identified. In addition, a sampling plan for welded attachments was maintained.

Although Code Case N-509 and ASME Section Xl, beginning with the 1995 Addenda, represent an improvement to previously stated Code criteria for the examination of welded attachments, neither address the examination of welded attachments on a single vessel nor which welded attachment should be selected for examination. Code Case N-700 provides clarification for the selection of Class 1, 2, and 3 vessel welded attachments for examination, and was developed to address the selection criteria currently not included in Code Case N-509 and ASME Section Xl, 1998 Edition through 2000 Addenda.

Code Case N-700 clarifies the requirements for the examination of welded attachment on vessels by stating the following criteria:

1) For multiple vessels of similar design, function and service, only one welded attachment of only one of the multiple vessels shall be selected for examination.

2) For single vessels, only one welded attachment shall be selected for examination.

3) The attachment selected for examination on one of the multiple vessels or the single vessel, as applicable, shall be an attachment under continuous load during normal system operation, or an attachment subject to a potential intermittent load (seismic, water hammer, etc.) during normal system operation if an attachment under continuous load does not exist.

Because the selection criteria provided by Code Case N-700 is supported by the same failure data that forms the basis for Code Case N-509 and also addresses scenarios in which Section Xl is silent, the alternative requirements of N-700 are deemed to be a more complete and detailed set of rules for the selection of welded attachments on vessels. Accordingly, pursuant to 10CFR50.55a(a)(3)(i), relief is requested on the basis that the proposed alternative provides an acceptable level of quality and safety.

5. Proposed Alternative and Basis for Use In lieu of implementing the requirements of Table IWB-2500-1, Examination Category B-K, Footnote 4; Table IWC-2500-1, Examination Category C-C, Footnote 4; and Table IWD-2500-1, Examination Category D-A, Footnote 3; it is proposed that the alternative requirements of Code Case N-700) be implemented at the Wolf Creek Generating Station.

to ET 06-0010 Page 3 of 3

6. Duration of Proposed Alternative Selection of ASME Section Xl Code Class 1, 2, and 3 Vessel Welded Attachments will be performed in accordance with Code Case N-700 during the third inspection interval that begins on September 3, 2005 and ends on September 2, 2015, or until such time that Code Case N-700 is approved for use by reference in Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section Xl, Division 1". Once accepted in Regulatory Guide 1.147 any conditions specified in Regulatory Guide 1.147 will be followed.

7. Precedents By a letter dated March 11, 2005, the Tennessee Valley Authority requested relief from the ASME Section Xl inservice inspection requirements on vessel welded attachments for Browns Ferry Units 2 and 3. In accordance with 10 CFR 50.55a(a)(3)(i), TVA requested the use of Code Case N-700 as an alternative. In a letter dated July 18, 2005 (TAC Nos. MC6437 and MC6438), the NRC authorized this 10 CFR 50.55a request for use for the remainder of the interval or until such time that Code Case N-700 is approved for use in Regulatory Guide 1.147.

- 10 CFR 50.55a Request No. 13R-04 Attachment 3 to ET 06-0010 Page 1 of 4 10 CFR 50.55a Request Number 13R-04 Relief Request In Accordance with 10 CFR 50.55a(g)(5)(iii)

Inservice Inspection Impracticality

1. ASME Code Components Affected Reactor Vessel Supports, Component Numbers RBB01 -01, RBB01 -02, RBBO1-03 and RBB01-04

2. Applicable Code Edition and Addenda ASME Boiler and Pressure Vessel Code, Section Xl, 1998 Edition through 2000 Addenda

3. Applicable Code Requirement Relief is requested from the requirements of ASME Section Xl, Table IWF-2500-1, Category F-A, Item Number F1.40 which requires that 100% of Class 1 supports, other than piping supports, be subject to a visual, VT-3 examination once every inspection interval.

4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested on the basis that compliance with the specified requirements is impractical. Conformance with the applicable inservice inspection requirements would necessitate a design modification to the Reactor Pressure Vessel supports and associated insulation/walkplate to allow 100%

visual examination of the subject supports.

In addition, limited accessibility and high radiation levels in the area where these supports are located further reduces the percentage of the supports available for visual examination.

The Wolf Creek Reactor Vessel is supported by two cold leg nozzles and two hot leg nozzles. There is a support assembly at each of these nozzles that consists of a nozzle weld build up, shoe plate, air cooled box, and steel support structure embedded in the primary shield wall. Figures 1 and 2 depict these support assemblies. As shown in the Figures, only the nozzle weld build-up and shoe plate are completely accessible for a visual VT-3 examination. The majority of the air-cooled box and the entire steel support structure are located beneath a steel walk plate and only the top of the air-cooled box is directly accessible. An additional 20 to 30 percent of the air-cooled box and a very small percentage of the steel support structure would be made accessible if the steel walk plate and insulation were removed.

to ET 06-0010 Page 2 of 4 The Reactor Vessel supports are located in a confined space below the refueling pool permanent seal ring. The area can only be accessed through four seal ring hatches. In addition to difficult access, the radiation level in the area is between 1.5 and 2.0 man-rem per hour.

5. Burden Caused by Compliance The large cost of a design modification to the Reactor Pressure Vessel supports and associated insulation/walkplate to allDw 100% visual examination of the subject supports is deemed an undue burden. Further, it is estimated that the removal and re-installation of the walk plate and insulation in this confined space, combined with the performance of the visual VT-3 examination, would result in an exposure of approximately 36 man-rem.

Removal of the walk plate and insulation, under these conditions, in order to increase the examination coverage of the air cooled box by approximately 20 to 30 percent and a very small percentage of the steel support structure is considered impractical without a commensurate increase in quality or safety.

6. Proposed Alternative and Basis for Use In lieu of implementing the requirements of Table IWF-2500-1, Category F-A, Item No.

F1.40, Wolf Creek Nuclear Operating Corporation (WCNOC) proposes to perform a limited VT-3 visual examination, with the walk plate and insulation installed, on the accessible NF portions of the Reactor Vessel support assemblies. If conditions are discovered during this limited VT-3 examination that do not meet the acceptance standards of IWF-3400, the walk plate or insulation will, if necessary, be removed in order to meet the requirements of IWF-3122.2 or IWF-3122.3, as applicable.

7. Duration of Proposed Alternative This 10 CFR 50.55a request is being proposed for use during the third inspection interval that begins on September 3, 2005 and ends on September 2, 2015.

8. Precedents The proposed alternative in this 10 CFR 50.55a request was included in second interval Relief Request 12R-14. This Relief Request was submitted to the NRC in an Attachment to WCNOC Letter Number WM 97-0006, dated 01/23/1997, from 0. L. Maynard, WCNOC, to USNRC, and granted for use per letter from William H. Bateman, USNRC to Otto L. Maynard, WCNOC dated 10/24/1997 (TAC No. M93381).

to ET 06-0010 Page 3 of 4 (SEE FIGURE 2)

-WALKWAY OVER HONEYCOMB INSILATION STEEL SLPPORT STRUCTURE EMfEDDED IN COCRETE FIGURE 1 to ET 06-0010 Page 4 of 4 L, -1 WALKWAY OVER HOEYCOMB INSLDEATION RV SHOE -`

i1 RV SUPPORT-,

AIR BOX

.REACTOR VESSEL WALL STEEL SUOPORT STRLCTL5RE 11 EMBEDDED IN CONCRETE SECTION A-A FIGURE 2

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WC(RE-16 REVISION 0 INSERVICE INSPECTION PROGRAM PLAN WOLF CREEK GENERATING STATION INTERVAL 3 Prepared B as Sale - Inservice Engineering Date Technical Review By: f /

'15ennis E. Tougaw - ISI Coordinator Date Technical Review By: 22 Aai /I Zoo &

P4.

Don G. Naylor - Pressure T6st Coordinator Date ANtI Review: _

Date Approval By: /

Supervisor  :/ODate LY bC V/a2/b L

I WOLF CREEK GENERATING STATION THIRD INTERVAL IS) PROGRAM PLAN A

G E REVISION STATUS SHEET 0

1 REVISION AFFECTED PAGES DESCRIPTION/COMMENTS

/ 0 All Issued For Interval 3 2

0 0

6 WCRE-16 ii Revision 0

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN A

Li TABLE OF CONTENTS E

Effective Number 0 Section Description of Pares in Section REVISION STATUS SHEET.................................................................................................................I TABLE OF CONTENTS 2

1.0 INTRODUCTION AND BACKGROUND

.2 1.1 Introduction O 1.2 Background 2.0 BASIS FOR INSERVICE INSPECTION PROGRAM PLAN .......................................... 15 2.1 Code of Federal Regulations Requirements 2.2 Augmented ISI Requirements 2.3 Risk-Informed ISI Program Plan 2.4 Examination Methods and Examination Procedures 2.5 Personnel Qualification Requirements 2.6 Inspection Intervals and Inspection Scheduling 2.7 Component and Component Support Selection Criteria 2.8 Examination Evaluation Criteria 2.9 Repair/Replacement Activities 2.10 Records and Reports Tables Table 2.3-1 Degradation Mechanism Categories Table 2.3-2 RI-ISI Risk Matrix Table 2.4-1 Examination Procedures Table 2.6-1 Inspection Program B Component/Component Support Scheduling 3.0 INSERVICE INSPECTION PROGRAM l)ESCRIPTION ....................................... 19 3.1 ASME Section XI Requirements 3.2 Augmented ISI Requirements 3.3 ASME Section Xl Code Cases Incorporated Into The WCGS ISI Program 3.4 Requests For Relief and Requests For Alternatives from ASME Section XI Requirements 3.5 WCGS Systems and Components Subject to Examination 3.6 WCGS Nonexempt Components and Component Supports 3.7 ISI Isometrics and ISI Equipment Drawings 3.8 Exempt ASME Class Components and Component Supports 3.9 System Pressure Testing 3.10 Calibration Blocks 3.11 Inservice Inspection Drawing Index Tables Table 3.3-1 Code Cases Incorporated Into The ISI Program Table 3.4-1 Requests For Relief and Requests For Alternatives from ASME Section XI Requirements Table 3.10-1 WCGS Calibration Blocks WCRE-1 6 iii Revision 0

I WOLF CREEK GENERATING STATION A1 THIRD INTERVAL 1SI PROGRAM PLAN A

E TABLE O' CONTENTS (Cont'd)

0) Effective Number 1 Section Description of Pages in Section 1 4.0 WCGS SYSTEM INSERVICE INSPECTION PROGRAM PLANS.....................................................I 4.1 WCGS Systems Subject To Section XI NDE or Augmented NDE .

U 4.1.1 Main Steam System (AB) .6 o 4.1.2 Feedwater System (AE) .7 4.1.3 Auxiliary Feedwater System (AL) .6 4.1.4 Reactor Coolant System (BB) .41 4.1.5 Chemical and Volume Control System (BG) .6 4.1.6 Steam Generator Blowdown System (BM) .3 4.1.7 Borated Refueling Water System (BN) .6 4.1.8 Essential Service Water System (EF) .6 4.1.9 Component Cooling Water System (EG) .6 4.1.10 Residual Heat Removal System (EJ) .15 4.1.11 High Pressure Coolant Injection System (EM) .12 4.1.12 Containment Spray System (EN) .6 4.1.13 Accumulator Safety Injection System (EP) .7 4.1.14 Auxiliary Feedwater Pump Turbine System (FC) .6 4.1.15 Containment Cooling System (GN) .6 4.1.16 Standby Diesel Generator Systems (KJ) .6 4.2 WCGS Systems Subject To Section XI Pressure Testing Only .3 4.3 WCGS Systems Excluded From Section XI Pressure Testing Per IWA-51 10(c) . 2 Tables Table 4.2-1 System Pressure Tcsting Procedures WCRE-16 iv Revision 0

I WOLF CREEK GENERATING STATION Mi THIRD INTERVAL 1SPROGRAM PLAN A

6

1.0 INTRODUCTION AND BACKGROUND

E I)

1.1 INTRODUCTION

1 This Inservice Inspection (ISI) Program Plan details the requirements for the examination and

/ testing of ASME Class 1, 2, and 3 components and component supports at the Wolf Creek Generating Station (WCGS). The ISI Program Plan addresses those examinations and tests 5 required by ASME Section XI and Augmented ISI commitments included in the WCGS Updated

/ Safety Analysis Report (USAR), as well as other licensing commitments detailed in Section 3.2.

U The 1SI Program Plan was developed and controlled by Wolf Creek Administrative Procedure AP O3 29A-002 and is effective from September 3, 2005 through September 2, 2015, which represents Wolf Creek's Third ISI Interval.

This Inservice Inspection Program Plan does not include the requirements for the examination and testing of ASME Class CC and MC components and component supports. These requirements are included in WCRE-I 1, Containment Inservice Inspection Program, which was developed in accordance with Wolf Creek Administrative Procedure AP 29A-005.

1.2 BACKGROUND

A Construction Permit was obtained to build the Wolf Creek Generating Station on May 17, 1977. After satisfactory plant construction and pre-operational testing was completed, a full power operating license, NPF42, was issued on June 4, 1985, and WCGS subsequently commenced commercial operation on September 3, 1985. The Docket Number assigned to WCGS is 050-482.

1.2.1 First Interval ISI Program Pursuant to the Code of Federal Regulations, Title 10, Part 50, Section 55a, Codes and standards, (10 CFR 50.55a), WCGS was required to meet the requirements of paragraph (g), Inservice inspection requirements,of that section.

Specifically, paragraph (g)(4)(i) called for the inservice inspection requirements of the initial 120 month inspection intenral to comply with the requirements of the latest edition and addenda of ASME Section XI referenced in paragraph (b) of 10 CFR 50.55a on the date 12 months prior the date of issuance of the operating license, subject to the limitations and modifications listed in paragraph (b) of 10 CFR 50.55a.

The version of IOCFR 50.55a in effect at that time referenced ASME Section XI, 1980 Edition with Addenda through the Winter 1981 Addenda (Section Xl 801W81) in paragraph (b)(2). The extent of the application of Section XI 801W81 was limited by paragraph (2)(iv)(A) such that Section XI, 1974 Edition with Addenda through Summer 1975 Addenda (Section XI 74/S75) was required for ASME Code Class 2 pressure retaining welds in Residual Heat Removal Systems, Emergency Core Cooling Systems, and Containment Heat Removal Systems. Optionally, per paragraph (2)(iv)(B), plants with Construction Permits docketed prior to July 1, 1978, such as WCGS, were allowed to use Section Xl 74/S75 to examine ASME Code Class 2 pressure retaining welds in systems other than those in paragraph (2)(iv)(A). WCGS elected to utilize this option.

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WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN Based on these 10 CFR 50.55a mandatory and optional requirements, the WCGS Section XI IS] Program Plan for the initial ten year interval was developed by Nuclear Energy Services (NES) in WCRE-07, Wolf Creek Generating Station ISI Program Plan Document.

1.2.2 Second Interval ISI Program Pursuant to the Code of Federal Regulations, Title 10, Part 50, Section 55a, Codes and standards, (10CFR 50.55a), WCG3S was required to meet the requirements of paragraph (g)(4), Inservice inspection requirements,of that section.

Specifically, paragraph (g&4)(ii) called for the inservice inspection requirements of the successive 120 month inspection interval to comply with the requirements of the latest edition and addenda of ASME Section XI referenced in paragraph (b) of 10 CFR 50.55a on the date 12 months prior to the start of the 120 month interval subject to the limitations and modifications listed in paragraph (b) of 10 CFR 50.55a.

The version of 10 CFR 50.55a in effect on September 3, 1994 referenced ASME Section Xl, 1989 Edition in paragraph (b)(2). Optionally, per paragraph (b)(2)(ii), plants with Construction Permits docketed prior to July 1, 1978, such as WCGS, were allowed to use Section XI 74/S75 to examine ASME Code Class I pressure retaining welds. However, WCGS elected not to utilize this option.

Based on these 10 CFR 50.55a mandatory and optional requirements, the WCGS Section XI ISI Program Plan for the second ten year interval was developed by Vectra Technologies in WCRE-l 0, Wolf Creek Generating Station Second Interval ISI Program Plan.

During the second interval, WCGS implemented a Risk Informed ISI (Ri-ISI) Program Plan for ASME Code Class I and 2 piping welds. The RI-ISI template submittal was approved by the NRC in the safety evaluation contained in a letter dated 12/13/01 from the USNRC to Otto Maynard (incoming correspondence 01 -00965).

The scope of the RI-ISI program is limited to ASME Code Class I and 2 piping welds (i.e., Examination Categories B-F, B-J, C-F-I and C-F-2 only). The RI-ISI program was developed in accordance with the methodology contained in the Electric Power Research Institute (EPRI) Topical Report (TR) EPRI TR-1 12657, Revision B-A. Application of the RI-ISI methodology is addressed in WCGS Basis Document No. WCRE-12.

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WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 2.0 BASIS FOR INSERVICE INSPECTION PROGRAM PLAN The following text provides a listing and overview of the documents (Code of Federal Regulations, ASME Boiler and Pressure Vessel Codes, and WCGS Procedures) that form the basis of the Third Interval ISI Program Plan. Specific implementation of the requirements in these documents is included in Sections 3 and 4 of this Program Plan.

2.1 Code of Federal Regulations Requirements Code of Federal Regulations Final Rules that affect the WCGS Third Interval ISI Program Update include the Final Rule published September 26, 2002 (67FR1 87), the Final Rule published October 1, 2004 (69FR190) and the Final Rule published September 29,2005 (70FR188). 67FRI87 incorporated by reference ASME Section XI, 1998 Edition through 2000 Addenda in paragraph (b)(2) and was effrctive October 28, 2002. 69FR1 90 incorporated by reference ASME Section Xl, 2001 Edition with 2003 Addenda in paragraph (b)(2) and was effective November 1,2004. 70FRI88 removed the mandatory modification in I OCFR50.55a(b)(2)(xxi)(C) and was effective October 31, 2005. Twenty seven (27) limitations and modifications are included in I OCFR50.55a(b)(2) and are numbered (i) to (xxvii). In addition, one (1) limitation and modification is included in IOCFR50.55a(b)(3)(v) and in I OCFR50.55a(g)(4)(iii), each. Each of th se limitations and modifications was reviewed by WCGS personnel and implemented as discussed in Section 3.1.1.

2.1.1 Scope of ASME Section XI Program Per 10 CFR 50.55a(g)(4), the specific components required to be included in an ISI Program per ASME Section Xl are those components and component supports which are classified as ASME Code Class 1,2, and 3. This requirement is reflected in WCGS Technical Requirement Manual 5.5.6. A detailed explanation of the components which are included the WCGS ASME Section XI Program is included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

2.1.2 ASME Section XI Edition and Addenda In accordance with 10 CFR 50.55a(g) WCNOC is required to update the ASME Section XI (the Code) IS) program for WCGS once every ten year interval. The 1SI program is required to comply with the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a one year prior to the start of the interval per 10 CFR 50.55a(g)(4)(ii). The Third ISI Interval is defined to be from September 3, 2005 to September 2,2015. Accordingly, based on a "lock in" date of September 3,2004, the 1998 Edition through 2000 Addenda of ASME Section Xl is the version of Section XI that WCGS must meet for Third Interval.

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I1 WOLF CREEK GENERATING STATION THIRD INTERVAL IS1 PROGRAM PLAN 2.13 ASME Section XI Code Cases

[) Per 10 CFR 50.55a(g), ASME Code Cases that have been determined to be suitable for U use in ISI Program Plans by the NRC are listed in Regulatory Guide 1.147 "Inservice 1 Inspection Code Case Acceptabi lity-ASME Section XI, Division 1". The use of other

,) Code cases (than those listed in Regulatory Guide 1.147) may be authorized by the Director of the Office of Nuclear Reactor Regulation upon request pursuant to 10 CFR 50.55a(a)(3). The ASME Section XI Code Cases incorporated into the WCGS ISI

/J Program Plan are listed and discussed in Section 3.3.

O 2.1.4 Requests For Relief and Requests For Alternatives 6, In cases where WCNOC has determined that ASME Section XI requirements are impractical to implement or has determined an alternative inspection approach to that specified in ASME Section XI would offer an acceptable (or equivalent) level of quality and safety, a 10 CFR 50.55a Request will be prepared and submitted to the NRC in accordance with 10 CFR 50.55a(g)(5), 10 CFR 50.55a(a)(3)(i) or 10 CFR 50.55a(aX3)(ii), as applicable.

Guidance for the preparation of 10 CFR 50.55a Requests was taken from Nuclear Energy Institute (NEI) White Paper "StandardFormatforRequestsfrom Commercial Reactor Licensees Pursuantto 10 CFR SO.55a", Revision I dated June 2004. This document provides comprehensive information for the content, format and submittal of these requests to the NRC, and is utilized by WCNOC.

As detailed in the NEI White Paper, when ASME Section XI requirements for inservice inspection are considered impractical, the licensee shall notify the NRC and submit information to support the determination, as required by 10 CFR 50.55a(g)(5)(iii). The submittal of this information will be referred to in this document as a Request for Relief.

The NEI White paper also provides guidance for cases where a licensee proposes alternatives to the ASME Section XI requirements that would provide an acceptable level of quality and safety or where the licensee proposes alternatives in cases where compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, as allowed by 10 CFR 50.55a(a)(3Xi) and 10 CFR 50.55a(a)(3)(ii), respectively. The submittal of this information will be referred to in this document as a Request for Alternative.

Per 10 CFR 50.55a paragraphs (a)(3) and (g)(6)(i), the Director of the Office of Nuclear Reactor Regulation will evaluate Requests for Relief and Requests for Alternatives per Paragraph (g)(5) and "..may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility".

Interval 3 Requests for Relief and Requests for Alternatives are included in Section 3.4.

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I WOLF CREEK GENERATING STATION l! THIRD INTERVAL IS] PROGRAM PLAN A

E 2.2 Augmented ISI Requirements D) Per 10 CFR 50.55a(g)(6)(ii), the NRC may require a licensee to follow an augmented inservice 1U inspection program for systems and components for which they deem an added assurance of 1 structural reliability is necessary.

9 Typically, the NRC imposes augmented ISI requirements on licensees by way of the Safety Analysis Report (SAR) approval process. Based on the particular design of a facility, SAR commitments are made to NRC Regulatory Guides and Branch Technical Positions which are in effect at the time of the SAR review. The Regulatory Guides and Branch Technical Positions, in 0j some cases, include inspection and testing requirements.

Another avenue by which the NRC imposes augmented ISI requirements is by way of periodically issued documents such as Generic Letters and Inspection and Enforcement (IE)

Bulletins or an NRC Order. These documents may require facilities holding a construction permit or operating license to perform inspections and tests as a result of problems or potential problems identified by the NRC Staff at other facilities.

Augmented examinations may also be performed as deemed necessary by the utility. This may be as a result of industry experience, a Performance Improvement Request (PIR) evaluation for special conditions, or similar situation in which Wolf Creek Generating Station believes there is a need for an augmented examination.

The augmented ISI requirements may include one-time or limited time period examinations, as well as examinations which are to be performed for the entire life of the plant. The augmented ISI examination requirements specific to WCGS are detailed in Section 3.2.

2.3 Risk-Informed ISI Program Plan Provided below is a general description of the Risk-Informed Inservice Inspection (RI-ISI)

Program at Wolf Creek and description of the RI-ISI "Living Program" update. The application of the RI-ISI Program for Interval 3 is addressed by Request for Alternative No.

IR3-01.

2.3.1 Initial RI-ISI Application ASME Section Xi Examination categories B-F, B-J, C-F-I, and C-F-2 originally contained the requirements for the nondestructive examination (NDE) of Class I and 2 piping welds. In 2001, a risk-informed methodology for the inservice inspection of Class I and 2 piping welds was applied at the Wolf Creek Generating Station. The risk-informed inservice inspection process used in this application is described in Electric Power Research Institute (EPRI) Topical Report (TR) 112657, Rev. B-A "Revised Risk-Informed Inservice Inspection Evaluation Procedure." The RI-ISI application was also conducted in a manner consistent with ASME Code Case N-578, "Risk-Informed Requirements for Class 1, 2, and 3 Piping, Method B."

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WOLF CREEK GENERATING STATION THIRD INTERVAL 15 PROGRAM PLAN This risk-informed application met the intent and principles of Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions On Plant-Specific Changes to the Licensing Basis" and Regulatory Guide 1.178, "An Approach for Plant-Specific Risk-Informcd Decisionmaking Inservice Inspection of Piping".

The original RI-ISI template, "Ris;k-Informcd Inservice Inspection Program Plan - Wolf Creek Generating Station (Revision 1)" was submitted to the NRC for approval per I OCFR50.55a(a)(3)(i) in Letter No. ET 01-0009, dated February 15, 2001. Based upon the information provided in the RM-ISI template, the request to implement the RI-ISI methodology on Class I and 2 piping welds was approved by the NRC in Letter No. 01-00965, dated December 13, 2001 (TAC No. MB1206). Approval was based on the alternative providing an acceptable level of quality and safety.

Other non-related portions of the ASME Section XI Code were unaffected by the RI-ISI application. EPRI TR-1 12657 provides the requirements for defining the relationship between the RI-ISI program and the remaining unaffected portions of ASME Section Xl.

This Section (2.3.1) of the ISI Program Plan provides an overview of the EPRI RI-ISI methodology and explains the application.

The tasks involved in the RI-ISI application were as follows:

Task 1: Scope and Exemption Determination Task 2: Consequence Evaluation Task 3: Degradation Mechanism Assessment Task 4: Service History Review Task 5: Segment Risk Ranking Task 6: Element Selection Task 7: Risk Impact Evaluation Task 8: Program Submittal/ Risk-Informed Template Details on performance of these RI-IS! tasks are provided in the following paragraphs.

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I WOLF CREEK GENERATING STATION A THIRD INTERVAL IS] PROGRAM PLAN 13 Task I: Scope and Exemption D)etermination Per EPRI TR-l 12657 and ASME Code Case N-578, the EPRI risk-informed 0 methodology may be applied to piping welds in Class 1, 2, 3, and non-classed systems, to individual Classes or combination of Classes, or to individual systems. For the Wolf Creek Generating Station, the RI-ISI methodology was applied to piping welds in Class 1 2 and 2 systems. This corresponded to ASME Section XI Examination Categories B-F, B-5I J, C-F-I, and C-F-2. Classification boundaries were not changed or otherwise affected by

/ the RI-ISI application. In addition, the ASME Section XI exemption criteria, as 21 addressed in IWB-1220 and IWC-1220, were not affected. Therefore, piping that was oj previously exempted per ASME Section Xl remained exempt in the RI-ISI application.

6 Task 2: Consequence Evaluation Calculations were prepared documenting the pipe rupture consequence evaluation, and indicating the consequence category assigned to each piping segment, as well as the technical basis for those assignments. The consequence evaluation used insights from the plant's Individual Plant Examination (IPE) and Individual Plant Examination External Events (IPEEE) submittals. Pipe breaks at various locations were postulated to cause an initiating event, reduce or disable plant mitigating ability, effect containment performance, or any combination of the above effects. Potential spatial effects (e.g.,

steam spray, flooding, etc.) were also evaluated for the postulated pipe breaks. The consequence rank was based on these effects and on their impact on the plant core damage frequency (CDF) or large early release frequency (LERF).

Results of the consequence evaluation were ultimately summarized in the risk ranking tables that are discussed in Task 5.

Task 3: Degradation Mechanism Assessment Detailed calculations were prepared documenting the evaluation of each piping segment with respect to the EPRI criteria for susceptibility to the various potential degradation mechanisms, and identifying specifically which degradation mechanisms are or are not applicable to each piping segment. The degradation mechanisms identified in the EPRI methodology as being applicable to nuclear plant piping are shown in Table 2.3-1.

Specific criteria for susceptibility to these degradation mechanisms are spelled out in EPRI TR-4 12657. Once the degradation mechanisms were assigned to each piping segment in accordance with the EPRI criteria, the pipe rupture potential was established using the criteria shown in Table 2.3-1. The degradation mechanism evaluation was conducted in the form of a checkli tt for each system or portion of system included in the scope of the program. The results were documented in an engineering calculation.

Results of the degradation mechanism assessment were ultimately summarized in the risk ranking tables that are discussed in Task 5.

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I WOLF CREEK GENERATING STATION 1 THIRD INTERVAL IS] PROGRAM PLAN A

G E TABLE 2.3-1

[i) DEGRADATION MECHANISM CATEGORIES 0

1 Pipe Expected Degradation Mechanisms To 6 Rupture Potential Leak Conditions Which The Segment is Susceptible

)/

Flow Accelerated Corrosion (FAC)

HIGH Large Water Hammer(')

0

'3 Thermal Fatigue (TASCS, Thermal Transients)

Stress Corrosion Cracking (IGSCC, TGSCC, PWSCC, MEDIUM Small ECSCC Localized Corrosion (MIC, Crevice Corrosion and Pitting)

Erosion-Cavitation LOW NoneNo Degradation Mechanisms LOW NonerPresent (1) Water hammer in concert with any of the degradation mechanisms listed under "Medium" Pipe Rupture Potential.

Task 4: Service History Review To supplement the degradation mechanism assessment performed under Task 3, a service history and susceptibility review was performed. This entailed a review of databases (plant and industry) and station documents to characterize operating experience with respect to piping pressure boundary degradation. This review also included an appraisal of previous water hammer events. Various plant documents were reviewed as part of this effort including Outage Summary Reports, Licensee Event Reports (LERs), and corrective action documents.

Task 5: Segment Risk Ranking Once the degradation mechanism assessment and consequence evaluation were completed, the results were used to perform a risk ranking of the piping segments within the scope of the RI-ISI effort. The piping segments were classified in accordance with the RI-ISI Risk Matrix (see Table 2.3-2), with the highest risk elements in the upper right hand corner of the matrix, and the lowest risk elements in the lower left hand corner.

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I WOLF CREEK GENERATING STATION M THIRD INTERVAL ISI PROGRAM PLAN A

G E TABLE 2.3-2 RI-ISI RISK MATRIX D

[:1 0

1 Consequence Assessment CONSEQUENCE CATEGORY Ky CCDP and CLERP Potential 1.

~1) Failure Potential LOW HIGI-I Assessment 0

CI 6 o 'a HIGH o/MEIM___

I~.

___/~7,(Cat. 5) ______ m IDEH!9!!EHIaH= MEIU

____ MEDIUM X G9 o _ MEDIUM/*v////

CC 9 )L <~/e/ (cat. 5)

'ow ~W%/41O~V4 MEDIUM

~(Ca6)/(Cat. 4)

The resulting risk ranking, along with the applicable input from the consequence evaluation and degradation mechanism assessment, were documented in risk ranking tables that included a summary table, matrix table, and report table.

Task 6: Element Selection Once the above tasks were completed, the project team convened an element selection meeting during which specific piping elements (generally welds) were selected for Ri-ISI examination. The objective of this meeting was to select inspection locations in a way that minimized risk, cost, and radiation exposures. Examination element selections were conducted such that:

• 25% of the elements in the high risk region (i.e., risk categories 1, 2 and 3) were chosen for inspection.

• 10% of the elements in the medium risk region (i.e., risk categories 4 and 5) were chosen for inspection,

• No elements are required to be selected in the low risk region (i.e., risk categories 6 and 7), but all locations regardless of risk category will continue to receive pressure/leakage testing.

Important considerations in the element selection process were inspectability, distribution of inspections among systems and segments, plant-specific inspection results, and radiation exposure. Elements that were selected for examination were indicated as such by underlining them in the risk ranking report table.

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I WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN A

Task 7: Risk ImDact Evaluation E_

f) Once the element selection under Task 6 was completed, the new set of locations that will (I be inspected under the RI-ISI program were compared to the locations that were 1 inspected per ASME Section XI prior to the application of the RI-ISI methodology. A

,f risk comparison was performed to ensure that the changes due to the new program

) resulted in either a reduction in risk, or at worst a negligible increase in risk, in 5 accordance with applicable regulatory guidelines (Regulatory Guides 1.174 and 1.178).

/ This was achieved by verifying that the cumulative impacts of all changes due to the 2 inspection program result in either negligible increases in Core Damage Frequency and 0 Large Early Release Frequency or actual decreases in the risk measurements. The risk impact evaluation was performed using a simplified risk quantification method as 6 described in EPRI TR-4 12657, which has been accepted by the NRC. Results of the evaluation, which indicated a decrease in total risk, were documented in a risk impact analysis.

Task 8: Proeram SubmittaVRi*k-Informed Template Utilizing the results of the foregoing tasks, a plant-specific request for acceptable alternative inspection was generated in accordance with regulatory requirements. The request provided the background, justification and inspection recommendations as determined by the RI-ISI application, and was prepared in accordance with a template for risk-informed inservicc inspection program submittals. This template was developed by industry, NEI and the NRC to streamline the RI-ISI submittal and NRC review process.

The risk-informed inservice inspection template was submitted to and approved by the NRC.

2.3.2 Nondestructive Examination Requirements For the risk-informed process, examination requirements shall be in accordance with EPRI Topical Report No. TR-I 12657. In some cases, the examination volumes required in the Topical Report are different than those required by ASME Section XI. For example, the examination volume required to look for thermal fatigue is expanded per the Topical Report to ensure that the potential degradation mechanism is detected, if it exists.

The Wolf Creek Generating Station will perform RI-ISI examinations in accordance with the Topical Report for Class I and 2 piping welds.

2.3.3 Examination Categories and Code Item Numbers As previously discussed, the requirements of EPRI Topical Report No. TR-I 12657 supersede those of ASME Section Xl for Class I and 2 piping welds in the risk-informed ISI application. Accordingly, the Examination Categories and Item Numbers provided by ASME Section XI (i.e., Examination Categories B-F, B-J, C-F-I, and C.F-2) have been superseded. Since TR-I 12657 does not provide new Examination Category and Code Item Numbers, the format from ASME Section XI Code Case N-578-1 is utilized for the assignment of these new numbers. As such, Class I and 2 piping welds have been reassigned to Examination Categoty R-A and Code Item Nos. RI.IO through RI.20, as applicable WCRE-16 2.0 Basis For Inservice Inspection Program Plan Revision 0 Page 8 of 15

Is WOLF CREEK GENERATING STATION A THIRD INTERVAL ISI PROGRAM PLAN E 2.3.4 Risk-Informed Inservice Inspection "Living Program" Evaluation

[) When Wolf Creek submitted their initial RI-ISI application to the NRC for approval, the 13 following standard clause was included in the template submittal:

1 "The RI-ISI program is a living program requiring feedback of new relevant information to ensure the appropriate identification of high safety significant 5- piping locations. As a minimum, risk ranking of piping segments will be

/ reviewed and adjusted on an ASME period basis. In addition, significant 9 changes may require more frequent adjustment as directed by NRC Bulletin 0 or Gencric Letter requirements, or by industry and plant specific feedback."

6 Most U.S. nuclear power plants have implemented RI-ISI Programs with this standard clause to perform periodic reviews and updates. To address this issue, NEI 04-05, "Living Program Guidance To Maintain Risk-Informed Inservice Inspection Programs For Nuclear Plant Piping Systems" was developed. As part of the ISI Program Update for Interval 3 at Wolf Creek, a RI-ISI Living Program Evaluation was performed in accordance with NEI 04-OS. The objective of this evaluation was to review plant and industry activities that could impact the bases of the Wolf Creek RI-ISI application as it enters Interval 3. Any changes to the original RI-4SI parameters were evaluated to determine their impact on the RI-ISI application.

In accordance with NEI 04-05, the following aspects were considered during the evaluation:

• Plant Examination Results

• Piping Failures

- Plant Specific Failures

- Industry Failures

• PRA Updates

• Plant Design Changes

- Physical Changes

- Programmatic Changes

- Procedural Changes

• Changes in Postulated Conditions

- Physical Conditions

- Programmatic Conditions The RI-ISI Living Program evaluation resulted in the following three issues being addressed in the RI-ISI application:

• The Class 2, 4" NPS auxiliary feedwater lines from the outboard isolation valve to the connection to the main feedwater piping in all four trains were added to the RI-ISI Program. This resulted from a change in ASME Section XI Code criteria wherein Class 2, 4" NPS and smaller auxiliary feedwater piping is no longer exempt.

• The Conditional Core Damage Probability (CCDP) and Conditional Large Early Release Probability (CLERP) values for the Class 2, 4" auxiliary feedwater piping WCRE-16 2.0 Basis For Inservice Inspection Program Plan Revision 0 Page 9 of 15

If WOLF CREEK GENERATING STATION A THIRD INTERVAL ISI PROGRAM PLAN G addressed above were higher than the upper bound values previously used in the risk.

impact analysis. New upper bound values of 1.44E-2 and 1.44E-3 were used in the

[J updated risk impact analysis for CCDP and CLERP, respectively.

1

• Based on ongoing industry experience with Primary Water Stress Corrosion Cracking

./ (PWSCC), Assumption No. 7 in the Degradation Mechanism Evaluation was deleted.

2 This assumption had stated the following:

/ "Bi-metallic welds with Inconel buttering are not considered susceptible to the 2 PWSCC degradation mechanism."

O For the third interval, Wolf Creek will comply with the criteria of MRP-139 for 6, welds that are potentially susceptible to PWSCC. At Wolf Creek, this consists of 14 welds where piping attaches to the reactor pressure vessel and pressurizer. MRP-1 39 is independent from the RI-ISI Program, yet these 14 welds are in the scope of both programs. From both a technical and administrative standpoint, precedence for the examination of the 14 welds that are potentially susceptible to PWSCC will be taken from how RI-ISI Programs at BWRs interface with the NRC mandated program to examine welds that are potentially susceptible to Intergranular Stress Corrosion Cracking (IGSCC).

During the update of the Wolf Creek ISI Program in preparation for their third ISI interval, other minor corrections were identified (e.g., correction of weld numbers) and were evaluated as part of the RI-ISI Living Program Update. These had no impact on the RI-ISI Program beyond requiring minor editorial corrections to the RI-ISI Program documents.

The RI-ISI Program was reevaluated for the three issues and other minor corrections using the applicable portions of the same risk-informed process that originally established the risk-informed inspection program. The reevaluation was performed by inserting the new information at the appropriate levels of the analysis. All of the cases that were evaluated in the risk impact analysis during the original RI-ISI application were reevaluated using the new information that was determined for the current application. Results of the risk impact reanalysis were that the overall plant risk as mcasured as a change in Core Damage Frequency and Large Early Release Frequency was further decreased as a result of the application of the new information. As such, the RI-ISI application on Class I and 2 piping welds still maintains an acceptable level of quality and safety.

2.3.4.1 RI-ISI Program Ongoing Commitment In the response to an RAI to the initial RI-ISI application, Wolf Creek committed to resubmit the RI-ISI program to the NRC prior to the end of any 10-year interval if there is some deviation from the RI-ISI methodology described in the initial submittal or if industry experience determines that there is a need for significant revision to the program as described in the original submittal for that interval. The same commitment also stated that Wolf Creek would initiate tracking documents to ensure that risk ranking of piping segments would be reviewed and adjusted on an ASME period basis as a minimum. This is considered an ongoing commitment and is tracked in the Regulatory Commitment Management System (RCMS) as Commitment 2001-027.

WCRE-16 2.0 Basis For Inservice Inspection Program Plan Revision 0 Page 10 of 15

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 2.4 Examination Methods and Examination Procedures The three types of examination utilized for Inservice Inspection are visual, surface and volumetric. Within these types of examinations, different methods may be permitted. This allows the owner to select the most effective examination methodology based on factors such as component accessibility, radiation levels and component material of construction.

Visual Examination Visual examination is divided into three different methods: VT-I, VT-2, and VT-3.

The VT-4 examination is conducted to detect discontinuities and imperfections on the surfaces of components, including such conditions as cracks, wear, corrosion or erosion.

The VT-2 examination is conducted to detect evidence of leakage from pressure retaining components, with or without leakage detection systems, as required during the conduct of a system pressure test.

The VT-3 examination is conducted to determine the general mechanical and structural condition of components and their supports, by verifying parameters such as clearances, settings, physical displacements; and to detect discontinuities and imperfections such as loss of integrity at bolted or welded connections, loose or missing parts, debris, corrosion, wear, or erosion. VT-3 includes examinations for conditions that could affict operability or functional adequacy of snubbers and constant load and spring type supports.

All Visual examinations are conducted per Article 9 of ASME Section V and the additional requirements of IWA-2210.

Surface Examination A surface examination indicates the presence of surface discontinuities. It may be conducted by a magnetic particle (MT), liquid penetrant (PT) or eddy current method. For surface examinations of carbon steel components, either a PT or MT may be performed. The ISI Program Plan Tables indicate the preferred technique, but either is acceptable.

Magnetic particle examinations are conducted per Article 7 of ASME Section V, as required by ASME Section Xl, paragraph IWA-2221. The examination of coated materials is conducted in accordance with Appendix I of Article 7 oFASME Section V.

Liquid penetrant examinations are conducted per Article 6 of ASME Section V, as required by ASME Section Xl, paragraph IWA-2222.

Eddy current examinations are conducted per Appendix IV, as required by ASME Section Xl, paragraph IWA-2223.

WCRE-I 6 2.0 Basis For Inservice Inspection Program Plan Revision 0 Page II of 1S

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN Volumettic Examination A volumetric examination indicates the presence of discontinuities throughout the volume of material and may be conducted from either the inside or outside surface of a component.

The ultrasonic pulse echo examination is the volumetric examination method employed to determine the presence of subsurface discontinuities. The stipulated volume of metal beneath the surface is examined by this method. Ultrasonic examinations are conducted in accordance with ASME Section XI, Appendix I per paragraph IWA-2232.

For welds in the RI-ISI program, the volume inspected shall be per the recommendations of EPRI TR-1 12657 Rev. B-A for the degradation mechanism identified for that weld. For welds with no degradation mechanism identified, the default volume to be inspected is that for thermal fatigue.

Radiographic examination may be employed in cases where clearances make 100% weld examination impossible.

Examinalion Procedures The inservice inspection examination procedures employed at WCGS are listed in Table 2.4-1.

The Procedures with identifiers that begin with "QCP" indicate that these procedures are owned by the Manager, Quality, and as such, are used by the WCGS Quality Control NDE personnel.

Also listed are the generic PDI procedures for the examination of components subject to Appendix VII. Other procedures may be added to the list as contracts are awarded to specific vendors and WCGS has approved the vendor procedures.

TABLE 2.4-1 EXAMINATION PROCEDURES Procedure Number Procedure Title QCP 20-501 Solvent Removable Visible Dye Liquid Penetrant Examination QCP 20-502 Magnetic Particle Examination AC/DC Yoke and AC Coil Techniques QCP 20-504 Ultrasonic Exam For Flaw Detection QCP 20-508 Radiographic Exam of Welds and Components QCP 20-510 Ultrasonic Instrument Linearity Verification QCP 20-520 Pressure Test Examination QCP 20-522 Ultrasonic Examination of Ferritic Piping Welds QCP 20-523 Ultrasonic Examination of Austenitic Piping Welds QCP 20-540 VT-I Visual Examination WCRE-16 2.0 Basis For Inservice Inspection Program Plan Revision 0 Page 12 of 15

I WOLF CREEK GENERATING STATION III THIRD INTERVAL ISI PROGRAM PLAN A

Gi E TABLE 2.4-1 (Continued)

D) EXAMINATION PROCEDURES 0

1 Procedure Number Procedure Title J

J) QCP 20-541 VT-3 Visual Examination C

PDI-UT- I, Rev C PDI Generic Procedure for the Ultrasonic Examination of Ferritic Pipe

./ Welds I) PDI-UT-2, Rev C PDI Generic Procedure for the Ultrasonic Examination of Austenitic Pipe 0 Welds 0

6 PDI-UT-3, Rev C PDI Generic Procedure for Ultrasonic Through Wall Sizing in Pipe Welds PDI.UT4, Rev C PDI Generic Procedure for Ultrasonic Examination of Studs and Bolts From the Bore PDI-UT-5, Rev C PDI Generic Procedure for Straight Beam Ultrasonic Examination of Bolts and Studs PDI-UT-6, Rev F PDI Generic Procedure for the Ultrasonic Examination of Reactor Pressure Vessel Welds PDI-UT-7, Rev F PDI Generic Procedure for the Manual Ultrasonic Through Wall and Length Sizing of Ultrasonic Indications in Reactor Pressure Vesscl Welds PDI-UT-8, Rev D PDI Generic Procedure for the Ultrasonic Examination of Weld Overlaid Austenitic Piping Welds PDI-UT-I 0, Rev B PDI Generic Procedure for the Ultrasonic Examination of Dissimilar Metal Welds PDI-UT-I 1, Rev B PDI Generic Procedure for the Ultrasonic Detection and Sizing of Reactor Pressure Vessel Nozzle to Shell Welds and Nozzle Inner Radius 2.5 Personnel Qualification Requirements Personnel performing nondestructive (ND)E) examinations shall be qualified and certified using a written practice prepared in accordance with ANSI/ASNT CP-1 89, dated 1995, as required by IWA-2300 of Section Xl and as modified by 10 CFR50.55a(b)(2)(xviii).

Personnel performing Appendix VIII ultrasonic examinations per IOCFR5O.55a(g)(6)(iiXC), shall meet the qualification requirements of Appendix VIII, as modified by IOCFR50.55a(b)(2)(xiv).

Personnel performing visual examinations or using other NDE methods not addressed in ANSI/ASNT CP-I 89, shall be qualified as defined in ANSI/ASNT CP-I 89 or the ASNT Central Certification Program (ACCP) and the Employer's written practice.

WCRE-1 6 2.0 Basis For Inservice Inspection Program Plan Revision 0 Page 13 of 15

II WOLF CREEK GENERATING STATION A' THIRD INTERVAL ISI PROGRAM PLAN E 2.6 Inspection Intervals and Inspection Scheduling U Inspection Intervals

,/ Per IWA-2430 of ASME Section Xl, the inservice examinations and system pressure tests 2 required by IWB, ]WC, IWD and the examinations and tests of IWF shall be completed 5 during each of the inspection intervals fo:r the service lifetime of the power unit. The

,/ inspections shall be performed in accordance with the schedule of Inspection Program A of 9IWA-2431 or optionally, Inspection Program B of ]WA-2432. Because the Code of Federal O) Regulations, 10 CFR 50.55a(g)(4)(ii) specifies 120 month inspection intervals for inservice 0 inspections, Inspection Program B must be employed.

6 Per IWA-2430(d), for components inspected under Program B, each of the inspection intervals may be extended or decreased by as much as one year. Adjustments shall not cause successive intervals to be altered by more than one year from the original pattern of intervals.

Per IWA-2430(e), in addition to the interval adjustment allowed per IWA-2430(d), for power units that are out of service continuously for 6 months or more, the inspection interval during which the outage occurred may be extended for a period equivalent to the outage and the original pattern of intervals extended accordingly for successive intervals.

Inspection Schedule Per IWA-2420, inspection plans shall be prepared for the first inservice interval and subsequent inspection intervals. Per ]WA-2420(b), an implementation schedule for performance of examinations and tests shall be prepared for each inspection plan.

Subarticles IWB-2400, IWC-2400, IWD-2400, and IWF-2400, include the requirements for the scheduling of examination and tests for Class I components, Class 2 components, Class 3 components, and Class 1,2, and 3 component supports, respectively.

Per IWB-2410, inservice examinations and system pressure tests of Class I components may be performed during plant outages such as refueling shutdowns or maintenance shutdowns.

The term "may" allows the examinations and system pressure tests to be performed during system operation. Per IWC-2410, IWD-2410, and IWF-2410, inservice examinations and system pressure tests of Class 2, Class 3 and Class 1, 2, and 3 component supports, respectively may be performed during either system operation or plant outages.

Specific scheduling criteria is included in IWB-2412, IWC-2412, IWD-2412, and IWF-2410-2 for plants which are employing Inspection Program B. These paragraphs reference Tables IWB-2412-1, IWC-2412-1, IWD-.2412-1, and IWF-2410-2, which include minimum and maximum percentages of examinations required to be completed by inspection period.

Table 2.6-1 summarizes this information for Interval 3 at Wolf Creek.

Per IWB-2412, examinations listed in IWB-2412(a)(1) to (5) as specified in Table IWB-2500-1 are not required to meet the criteria in Table IWB-2412-1.

In the event that a Category includes less than three components or items, the components or items may be examined in any two periods; or if in any one period if there is only one item or component in lieu of the requirements of Table IWB-2412-1.

WCRE-16 2.0 Basis For Inservice Inspection Program Plan Revision 0 Page 14 of 15

I WOLF CREEK GENERATING STATION 1I THIRD INTERVAL ISI PROGRAM PLAN A

G E TABLE 2.6-1 I) INSPECTION PROGRAM B COMPONENT/COMPONENT SUPPORT SCHEDULING C*J 0 INSPECTION INSPECTION PERIOD, MINIMUM MAXIMUM

( INTERVAL CALENDAR YEARS OF EXAMINATIONS EXAMINATIONS PLANT SERVICE COMPLETED, % COMPLETED, %1 3 23 16 50 3 27 50' 75 3 30 100 100 l If the first period completion percentage for any examination category exceeds 34%, at least 16% of the required examinations shall be performed in the second period.

2.7 Component and Component Support Selection Criteria Class 1,2, and 3 components and component supports were selected for examination per the requirements of the 1998 Edition through 2000 Addenda of Section XI, Tables IWB-2500-1, IWC-2500-1, IWD-2500-1 and IWF-2500-1, respectively, except for Categories B-F, 13-, C-F-I, and C-F-2 welds which were selected per the RI-ISI Program. The basis for selection of RI-ISI welds is documented in 10 CFR 50.55a Request Number 13R-01.

2.8 Examination Evaluation Criteria Evaluation of reportable indications detected during the inservice inspection of WCGS components shall be in accordance with Article IWA-3000 of ASME Section XI, 1998 Edition through 2000 Addenda. Indications detected may be evaluated by other nondestructive methods, where practical, to assist in the determination of flaw characteristics (e.g. size, shape, location, orientation, etc.) before final disposition is made.

2.9 Repair/Replacement Activities Repair/Replacement activities will be performed in accordance with Article IWA4000 of ASME Section XI, 1998 Edition through 2000 Addenda and are implemented by WCGS Procedure AP ] 6A-003, "ASME Section XI Repair/Replacement Program".

2.10 Records and Reports The preparation and retention of records and reports detailing ISI plans and schedules, examinations, tests, replacements, and repairs will be in accordance with Article IWA-6000 of ASME Section XI, 1998 Edition through 2000 Addenda and Code Case N-532-1.

WCRE-16 2.0 Basis For Inservice Inspection Program Plan Revision 0 Page 15 of 15

I1 WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN A

G E 3.0 INSERVICE INSPECTION PROGRAM DESCRIPTION (0 The WCGS Inservice Inspection Program consists of those examination and testing requirements mandated by ASME Section XI and Augmented ISI requirements mandated by plant licensing commitments or other WCGS commitments.

2 The following text includes a detailed description of the ASME Section XI ISI Program in Section

/ 3.1 and the Augmented ISI Program in Section 3.2. These sections provide a comprehensive 2 summary of the ISI Program Plan. Sections 3.3 and 3.4 include supporting details for ASME Section U Xl Code Cases and Requests for Relief and Requests for Alternatives Requests From ASME Section o) XI Requirements, respectively. Sections 3.5 through 3.11 provide additional information that 6 describe and support this ISI Program Plan.

3.1 ASME Section XI Requiremenbi Based on an ASME Section XI Code of Record "lock-in" date of September 3, 2004 (one year prior to the 3rd Interval start date) and IOCFR50.55a requirements in effect at that time, this ISI Program Plan was developed in accordance with the requirements in the 1998 Edition through 2000 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, Subsections IWA, IWB, IWC, IWD, IWF, Mandatory Appendices, and Inspection Program B of IWA-2432, except as follows:

NOTE: As delineated in AP 29A-002, the requirements for implementation of ASME Section Xl, Subsections IWE and IWL in accordance with the amendment of 10 CFR 50.55a which became effective September 9, 1996, have been included in a separate inservice inspection program plan, WCRE-1 I, Containment Inservice Inspection Program Plan.

3.1.1 Code of Federal Regulations Modifications and Limitations The following mandatory and optional Code of Federal Regulations Limitations and Modifications are included in 10CFR50.55a as of September 29, 2005. Only those I OCFR50.55a Limitations and Modifications applicable to the 1998 Edition through 2000 Addenda of Section Xl are listed. Note that mandatory modification I OCFR50.55a(b)(2)(xxi)(C) was removed by the Final Rule dated September 29, 2005 (70FRI 88), cffcctive on October 31, 2005. These Limitations and Modifications were reviewed for inclusion in the ISI Program and dispositioned as follows:

3.1.1.1 WCGS will not utilize the option in IOCFR50.55a(b)(2)(ii) to examine Class I piping per ASME Section XI, 1974 Edition with the Summer 1975 Addenda.

3.1.1.2 As allowed by IOCFR50.55a(bX2Xiii), WCGS Steam Generator tubing will be examined in accordance with plant Technical Specifications and the plant Steam Generator Program in lieu of Article IWB-2000.

3.1.1.3 WCGS will not utilize the option in IOCFR50.55a(b)(2Xiv), to examine Class 2 piping per ASME Section Xl, 1974 Edition with the Summer 1975 Addenda and the 1983 Edition through the Summer 1983 Addenda.

3.1.1.4 As required by IOCFR50.55a(bX2Xx), WCGS will apply the station IOCFR50 Appendix B Quality Assurance Program to Section XI activities.

WCRE-1 6 3.0 - ISI Program Description Revision 0 Page 1 of 19

WOLF CREEK GENERATING STATION THIRD INTERVAL 1SI PROGRAM PLAN 3.1.1.5 As required by 10CFR50.55a(bX2Xxi), WCGS will apply the rules in IWB-1220, "Components Exempt from Examination," of Section XI, 1989 Edition in lieu of the IWB-1220 requirements in Section XI, 1998 Edition through 2000 Addenda.

3.1.1.6 The requirements of IOCFR5O.55a(bX2Xxii), are complied with by WCGS procedure AP 16A-003.

3.1.1.7 As allowed by I OCFR50.55a(b)(2Xxiv), WCGS will use the annual practice requirements in V11-4240 of Appendix VII of Section XI in place of the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of annual hands-on training discussed in the first sentence of I OCFR50.55a(b)(2)(xiv). The annual practice requirements at WCGS will be performed on material or velds that contain cracks, or by analyzing prerecorded data from material or welds that contain cracks. This training will be completed no earlier than 6 months prior to performing ultrasonic examinations.

3.1.1.8 As allowed by I OCFR5O.55a(b)(2Xxv), WCGS will implement the optional Appendix VIII specimen set and qualification provisions in paragraphs (bX2)(xv)(A) to (bX2)(xv)i(M).

3.1.1.9 As required by I OCFR5O.55a(b)(2XxviXA) and IOCFR50.55a(bX2)(xvi)(B), WCGS examinations performed from one side of a ferritic vessel weld and examinations performed from one side of a ferritic or stainless steel pipe will be conducted with equipment, procedures, and personnel that have demonstrated proficiency with single side examinations.

3.1.1.10 As required by 10CFR50.55a(b)(2)(xviii)(A), Level I and II nondestructive examination personnel at WCGS will be recertified on a 3-year interval in lieu of the 5-year interval specified in IWA-2314(a) and IWA-2314(b) of the 1998 Edition through 2000 Addenda.

3.1.1.11 The requirements of 10CFR50.55a(bX2XxviiiXB) specify that paragraph IWA-2316 of the 1998 Edi tion through 2000 Addenda will only be used to qualify personnel that observe for leakage during system leakage and hydrostatic tests conducted in accordance with IWA-521 1(a) and (b). WCGS does not utilize these alternatives qualifications.

3.1.1.12 The requirements of 10CFRS0.55a(b)(2)(xviiiXC), specify that when qualifying visual examination personnel for VT-3 visual examinations under paragraph IWA-2317 of the 1998 Edition through 2000 Addenda the proficiency of the training will be demonstrated by administering an initial qualification examination and administering subsequent examinations on a 3-year interval.

WCGS does not utilize thes.e alternatives qualifications.

3.1.1.13 As required by IOCFR50.55a(bX2Xxix), the provisions in IWA-2240 and IWA-4520(c) of the 1998 Edition through 2000 Addenda will not be used by WCGS.

3.1.1.14 As required by 10CFR50.55a(bX2)(xx), when performing system leakage tests in accordance IWA-5213(a), per the 1998 Edition through 2000 Addenda, a 10-minute hold time after attaining test pressure is required for Class 2 and Class 3 WCRE-16 3.0 - ISI Program Description Revision 0 Page 2 of 19

I WOLF CREEK GENERATING STATION A THIRD INTERVAL ISI PROGRAM PLAN G components that arc not in use during normal operating conditions, and no hold time E is required for the remaining Class 2 and Class 3 components provided that the system has been in operation for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated components or 10 U minutes for uninsulated components.

/ 3.1.1.15 As required by 10CFR50.55a(b)(2XxxiXA), the provisions of Table 2 IWB-2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, Items Nos. B3.120, Pressurizer Nozzle Inside Radius Section, and B3.140,

/f Steam Generator Nozzle Inside Radius Section, of Inspection Program B in the 2 1998 Edition will be applied by WCGS. As allowed by Cl IOCFR50.55a(b)(2)(xxi)(A), a visual examination with enhanced magnification that U) has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the 6 allowable flaw length criteria in Table IWB-3512-1, 1998 Edition through 2000 Addenda may be performed in place of an ultrasonic examination.

3.1.1.16 The requirements of 10CFR50.55a(b)(2)(xxiXB) for Table IWB-2500-1, Examination Category B-G-2, Item B7.80, Pressure Retaining CRD Housing Bolting are not applicable to the WCGS. This type of bolting is not included in the plant design.

3.1.1.17 WCGS will not utilize the option in 10CFR50.55a(bX3Xv) to implement Subsection ISTD, "Inservice Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Power Plants," ASME OM Code, 1995 Edition through the latest edition and addenda incorporated by reference in paragraph (bX3), in place of the requirements for snubbers in Section Xl, IWF-5200(a) and (b) and IWF-5300(a) and (b). Snubbers will be examined and tested at WCGS in accordance with the Technical Requirements Manual (TRM), see Relief Request 13R-03 for details.

3.1.1.18 WCGS will not implement the option in I0CFR50.55a(g)(4)(iii) to perform surface examination of High Pressure Safety Injection System welds specified in Table IWB-2500-1, Examination Category B-J, Item Numbers B9.20, B9.21, and B9.22. Examination of these welds is being performed in accordance with the Risk-Informcd ISI Program described in Section 2.3 of this Program Plan.

WCRE-16 3.0 - IS] Program Description Revision 0 Page 3 of 19

II WOLF CREEK GENERATING STATION A THIRD INTERVAL ISI PROGRAM PLAN E 3.1.2 ASME Section XI Code Cases Incorporated

[) Alternatives to ASME Section XI that are provided in Code Cases may be incorporated into the SI Program as described below.

/ 3.1.2.1 Section XI Code Cases Approved and Conditionally Approved in 2 Regulatory Guide 1.147

/ Code Cases that have been approved or conditionally approved by the NRC in Regulatory Guide 1.147 may be incorporated into the ISI Program via reference

(: in this ISI Program Plan. Those Code Cases being directly incorporated by o WCGS during the third interval are listed in Section 3.3.

3.1.2.2 Section XI Code Cases Pending Approval or Conditional Approval Code Cases that have not been approved or conditionally approved by the NRC in Regulatory Guide 1.147 may be incorporated into the ISI Program via a Request for Alternative submitted to the NRC in accordance with I OCFR50.55a(a)(3). Code Cases being incorporated by WCGS during the third interval via Request for Alternatives are addressed in Section 3.4.

3.1.3 Requests For Relief and Requests For Alternatives Alternatives to ASME Section Xl may be incorporated into the ISI Program via a Request for Alternative or Request for Re ief submitted to the NRC in accordance with IOCFR50.55a(aX3) or IOCFR50.55a(g)(5), respectively. Those alternatives being incorporated by WCGS during the third interval via a I OCFR50.55a Request are addressed in Section 3.4.

3.2 Augmented ISI Requirements Augmented inscrvice inspection programs address examinations that go beyond what is required by ASME Section Xl. In some instances. augmented programs may require examinations on components that are not normally subject to ISI per ASME Section XI. In other instances, the augmented programs may stipulate supplemental examination criteria on components that are already addressed by ASME Section Xl. Described below are the augmented ISI commitments at WCGS for the third interval.

3.2.1 USAR Augmented ISI Requirements The following augmented inservice inspection requirements, which are specified by the WCGS Updated Safety Analysis Report (USAR) are also included in the WCGS ISI Program Plan.

WCRE-16 3.0 - ISI Program Description Revision 0 Page 4 of 19

I1 WOLF CREEK GENERATING STATION AAI THIRD INTERVAL ISI PROGRAM PLAN G 3.2.1.1 WCGS USAR Sections 3.6.1, Postulated Pining Failures In Fluid E Systems Inside and Outside Containment and 3.6.2, Determination Of Break D) Locations and Dynamic Effects Associated With The Postulated Rupture Of 1 PiPin2

/' These USAR Sections describe that WCGS complies with either USNRC Branch Technical Position MEB 3-1, or as required per the Risk-Informed 5 process for piping as outlined in EPRI Report 1006937, for welds within the "no

/ break zone" associated with high energy piping in containment penetration areas.

2 The "no break zone" is an area where pipe breaks were not postulated due to the Cl stress levels being within limits specified in USAR Section 3.6.2. The applicable o63 welds are shown on the Main Steam (AB), Feedwater (AE), Reactor Coolant (BB), Chemical and Vol ume Control (BG), Steam Generator Blowdown (BM),

and Auxiliary Feedwater Pump Turbine (FC) System Isometrics listed in Sections 4.1.1, 4.1.2, 4.1.4, 4.1.5, 4.1.6, and 4.1.14, respectively, within the "No Break Zone" and included in the respective Component and Component Support Selected/Scheduled for Examination Tables with Category "USAR" and Item No.

"3.6.2".

Wolf Creek has implemented a Risk-Informed High Energy Line Break Program.

This program is maintained in WCRE-14, Risk Informed High Energy Line Break (RI-HELB) Basis Document.

3.2.1.2 USNRC Regulatory Guide 1.14, Revision 1-Reactor Coolant Pump Flywheel Inteyrity This Regulatory Guide includes inspection requirements for Reactor Coolant Pump flywheels in Section 4. WCGS has committed to these inspections per USAR Appendix 3A. The Reactor Coolant Pump flywheels are included in the Reactor Coolant (BB) System Component and Component Support Selected/Scheduled for Examination Tables BB-1, BB-2 and BB-3 with Category "USAR" and Jhem No. "RG 1.14". The requirements of Reactor Coolant Pump Flywheel inspection are reflected in Technical Specification 5.5.7.

3.2.1.3 USNRC Regulatory Guide 1.65, Revision O-Materials and Inspections for Reactor Vessel Closure Studs This Regulatory Guide includes inspection requirements for the Reactor Vessel Closure Studs in Section C.4. WCGS addresses Regulatory Guide 1.65 in USAR Appendix 3A which focuses on design criteria rather than specifically committing to the inspection requirements of Section C.4 of the Regulatory Guide. Alternatively, it references Section 5.2.4 of the USAR which in turn references the inservice inspection requirements of ASME Section Xl or an approved alternative (e.g., approved Code Case or Request for Alternative). For the third interval, examinations on the Reactor Vessel Closure Studs will be conducted in accordance with Code Case N-652, Examination Category B-G-1, Code Item No. B6.20. Individual components are included in the Reactor Coolant (BB) System Component and Component Support Selected/Scheduled for Examination Tables BB-], BB-2 and BB-3.

WCRE-16 3.0 - IS Program Description Revision 0 Page 5 of 19

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN b 3.2.1.4 USNRC Regulatory Guide 1.137, Revision 0 - Fuel-Oil Systems for E Standby Diesel Generators This Regulatory Guide includes pressure testing requirements for fuel oil systems of standby diesel generators. WCGS has committed to this testing per USAR

( Appendix 3A and Section 9.5.4. These requirements are satisfied by the 2 implementation of the testing and VT-2 examinations required by Articles IWD-5 2000 and IWD-5000 of ASME Section XI, 1998 Edition with 2000 Addenda.

2 3.2.1.5 USNRC Regul.tory Guide 1.150, Revision 1-Ultrasonic Testing of Reactor Vessel Welds Durine Preservice and Inservice Examinations 6 This Regulatory Guide includes inspection requirements for the ultrasonic examination of Reactor Vessel Welds during Preservice and Inservice Examinations. WCGS committed to these inspections per USAR Appendix 3A and Section 5.2.4. The examination criteria of Regulatory Guide 1.150 supplements the requirements of ASME Section Xl. However, 10 CFR 50.55a requires that, with the exception of the shell-to-flange weld and the head-to-flange weld, that examination of the Reactor Vessel Welds be conducted in accordance with Appendix VIII, 1998 Edition with 2000 Addenda. The prescriptive guidance in Regulatory Guide 1.150 is not in total agreement with the Appendix VIII requirements; therefore, Regulatory Guide 1.150 remains applicable only for the examination of the reactor components that are not examined in accordance with Appendix VIII per 10 CFR 50.55a.

3.2.2 WCGS Augmented ISI Requirements The following augmented inservice inspection requirements are those resulting from WCGS commitments other those in the USAR and may include commitments resulting from a plant specific problem or a generic issue identified in an NRC Order.

3.2.2.1 MRP-139 For the third interval, Wolf Creek will comply with the criteria ofMRP-I39, "Material Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guideline" for welds that are potentially susceptible to Primaiy Water Stress Corrosion ("racking (PWSCC). At Wolf Creek, this consists of 14 welds where piping attaches to the reactor pressure vessel and pressurizer.

MRP-139 is independent from the RI-ISI Program, yet these 14 welds are in the scope of both programs. From both a technical and administrative standpoint, precedence for the examination of the 14 welds that are potentially susceptible to PWSCC will be taken from how RI-ISI Programs at BWRs interface with the NRC mandated program to examine welds that are potentially susceptible to Intergranular Stress Corrosion Cracking (IGSCC).

3.2.2.2 NRC Order EA-03-009 The NRC issued Order EA-03-009 to mandate inspections of the RPV head.

Each refueling outage visual examinations are performed to identify potential boric acid leaks from pressure retaining components above the RPV head. . The actions of a Bare Metal Visual (BMV) of 100% of the RPV head surface and WCRE-16 3.0 - ISI Program Description Revision 0 Page6 of 19

1 WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN NDE of each RPV head penetration nozzle will be under the 1S1 program and are EF scheduled as follows:

0 1)BMV examination of 100% of the RPV head surface (including 3600 around each RPV head penetration nozzle) to be performed every third refueling outage or five years, whichever comes first. Wolf Creek performed its first BMV 2 examination in RF12, April 2002. Subsequent BMV examinations are scheduled accordingly.

3 2) NDE of each RPV head penetration nozzle, either O i)a UT from two inches above the J-groove weld to the bottom of the 6 nozzle and an assessment to determine if leakage has occurred into the interference fit zone, or ii) eddy current testing or dye penetrant testing of the wetted surface of the J-groove weld and RPV head penetration nozzle base material to at least 2 inches above the J-groove weld.

The first NDE exam is due within 5 years of the Order (Feb. 2008) and thereafter at least every fourth refueling outage or seven years, whichever comes first. The first NDE exam is scheduled for RF15, October 2006.

3.3 ASME Section XI Code Cases Incorporated Into The ISI Program The use of ASME Section Xl Code Cases; is in accordance with I OCFR50.55a. ASME Code Cases that have been determined to be suitable for use in 1SI Program Plans by the NRC are listed in Regulatory Guide 1.147, Revision 14 "Inservice Inspection Code Case Acceptability-ASME Section XI, Division 1".

Table 3.3-1 lists the ASME Section XI Code Cases which have been incorporated into the 1S1 Program Plan. Code Cases that are approved or conditionally approved in Regulatory Guide 1.147 are shown with a status of "Approved" or "Conditionally Approved" in the table.

Code Cases not endorsed in the current revision of Regulatory Guide 1.147 are shown with a status of either "Pending" or "Unapproved" and a corresponding Request For Alternative has been prepared to employ the Case (see Table 3.4-1 for status of the Request for Alternative). The use of Code Cases (other than those listed in Regulatory Guide 1.147) may be authorized by the Director of the Office of Nuclear Reactor Regulation upon request pursuant to 10 CFR 50.55a(a)(3) via acceptance of the associated Request for Alternative.

WCRE-16 3.0 - 1SI Program Description Revision 0 Page 7 of 19

I WOLF CREEK GENERATING STATION THIRD INTERVAL 1SI PROGRAM PLAN A

G EL' TABLE 3.3-1 D CODE CASES INCORPORATED INTO THE 1SI PROGRAM 0

1 Code Title Regulatory Extent of Use Case Guide 1.147 7 Status/ Request for Alternative

'- N-460 Alternative Examination Coverage Acceptable To be used on Class I and 2 I for Class I and Class 2 Welds welds as applicable and allowed in the Code Case N-498-4 Alternative Requirements for I 0-Year Conditionally Extent defined within the 6 System Hydrostatic Testing for Class Acceptable Program Plan 1, 2 and 3 Systems N-513-1 Evaluation Criteria For Temporary Conditionally To be used as needed for Acceptance of Flaws in Class 2 or 3 Acceptable temporary acceptance of Piping flaws on moderate energy Class 2 or Class 3 piping N-526 Alternative Requirements for Acceptable To be used as an alternative Successive Inspections of Class I and to the re-examination 2 Vessels requirements of IWB-2420(b) and IWC-2420(b) for vessel volumes containing subsurface flaws N-532-1 Alternative Requirements to Repair Conditionally Extent defined within the and Replacement Documentation Acceptable Program Plan Requirements and Inservice Summary Report Preparation and Submission N-533-1 Alternative Requirements for VT-2 Conditionally Extent defined within the Visual Examination of Class 1, 2, and Acceptable Program Plan 3 Insulated Pressure Retaining Bolted Connections N-552 Altemative Methods - Qualification Conditionally To be used as described in for Nozzle Inside Radius Section Acceptable PDI generic procedure PDI-from the Outside Surface UT-I I N-566-2 Corrective Action for Leakage Acceptable To be used when needed as Identified at Bolted Connections an alternative to the requirements of IWA-5250(a)(2)

N-586 Alternative Additional Examination Conditionally To be used as an alternative Requirements for Class 1,2, and 3 Acceptable to the requirements of Piping, Components, and Supports IWB-2430(a), IWC-2430(a),

IWD-2430(a), IWF-2430(a)

N-597-1 Requirements for Analytical Conditionally To be used if needed for the Evaluation of Pipe Wall Thinning Acceptable analytical evaluation of Class 1, 2, and 3 piping items subjected to internal or external wall thinning.

WCRE-16 3.0 - ISI Program Description Revision 0 Page 8 of 19

I WOLF CREEK GENERATING STATION H THIRD INTERVAL ISI PROGRAM PLAN A

G E

a) TABLE 3.3-1 (Continued) 0 CODE CASES INCORPORATED INTO THE ISI PROGRAM 1 Code Title Regulatory Extent of Use Case Guide 1.147 I5 Status/ Request for Alternative

1) N-613-1 Ultrasonic Examination of Full Acceptable Extent defined within the Penetration Nozzles in Vessels, Program Plan 0 Examination Category B-D, Item Cl No's B3.1 0 and B3.90, Reactor G Nozzle-to-Vessel Welds, Figures IWB-2500-7(a), (b), and (c)

N-616 Alternative Requirements for V/T-2 Conditionally Extent defined within the Visual Examination of Classes 1, 2, Acceptable Program Plan and 3 Insulated Pressurc-Retaining Bolted Connections N-623 Deferral of Inspections of Shell-to- Acceptable Extent defined within the Flange and Head-to-Flange Welds of Program Plan a Reactor Vessel N-624 Successive Inspections Acceptable To be used when needed as an alternative to the requirements of IWB-2420(a), IWC-2420(a),

._____ _ IWD-2420(a), IWF-2420(a)

N-639 Alternative Calibration Block Conditionally To be used if needed as an Material Acceptable alternative to the requirements of Appendix 1, Supplement I and Section V, Article 4 N-648-1 Alternative Requirements for Inner Conditionally Extent defined within the Radius Examinations of Class I Acceptable Program Plan Reactor Vessel Nozzles N-652 Alternative Requirements to Acceptable Extent defined within the Categories B-G-I, B-G-2, and C-D Program Plan Bolting Examination Methods and Selection Criteria N-695 Qualification Requirements for Acceptable To be used when needed as Dissimilar Metal Piping Welds an alternative to the qualification requirements of Appendix VIII, Supplement 10 for the qualification requirements of dissimilar metal piping welds N-700 Alternative Rules for Selection of Pending (Request For Alternative 13R-Classes 1, 2, and 3 Vessel Welded 02)

Attachments for Examination WCRE-16 3.0 - ]SI Program Description Revision 0 Page 9 of 19

I WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN E 3.4 Requests For Relief and Requests For Alternatives From ASME Section XI Requirements Table 3.4-1 contains an index of Requests For Alternatives and Requests For Relief written in I accordance with IOCFRSO.55a (a)(3) and (g)(5) when specific ASME Section Xl requirements

/ for inservice inspection are considered impractical or pose an undue burden on the licensee. If examination requirements are determined to be impractical, or result in hardship or unusual

-J difficulty without a compensating increase in the level of quality and safety during the course of the interval, additional or modified Requests For Alternatives and Requests For Relief will be submitted in accordance with I 0CFR5O.55a(a)(3) and (g)(5). The status of each Request For Alternatives and Request For Relief (Submitted, Granted, or Denied) is also included in Table o 3.4-1.

6i TABLE 3.4-1 REQUESTS FOR RELIEF AND REQUESTS FOR ALTERNATIVES FROM ASME SECTION XI REQUIREMENTS Relief Request Summary Status 13R-0I Request to Continue Implementation of the Risk- To be submitted with the Informed Inscrvice Inspection Application on ISI Program Plan Class I and 2 Piping Welds 13R-02 Request to Utilize The Alternative Requirements To be submitted with the of Code Case N-700, Alternative Rules for ISI Program Plan Selection of Classes 1, 2, and 3 Vessel Welded Attachments for Examination 13R-03 10 CFR 50.55a Request To Utilize The Submitted Alternative Requirements of The WCGS Technical Requirements Manual (TRM) for the Examination and Testing of Snubbers 13R-04 Request to Perform a Limited VT-3 Examination To be submitted with the of the Reactor Vessel Supports ISI Program Plan 3.5 WCGS Systems and Components Subject To Examination The systems and components included in the WCGS Inservice Inspection Program Plan are those designed per ASME Section III, Class 1, 2, and 3 and shown on the Piping and Instrumentation Diagrams (P&IDs), except those components which have been optionally upgraded to Code Class as discussed in IWA-1320(e) and those components which were designed per ASME Section III and are no longer required for safe plant operation, (i.e. retired in place). A detailed explanation of the scope of components which are included the WCGS ASME Section XI Program is included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

3.6 WCGS Nonexempt ASME Class Components and Component Supports The WCGS ASME Class 1, 2, and 3 components which are not exempt from the examination per Section Xl, IWB-1220, IWC-1220, and IWMD-1220 are listed in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3". This document WCRE-16 3.0 - IS] Program Description Revision 0 Page 10 of 19

I1 WOLF CREEK GENERATING STATION A THIRD INTERVAL ISI PROGRAM PLAN G provides a cross-reference to the applicable ISI Isometric or ISI Equipment Drawing. An index E of the WCGS [SI Isometrics and Equipment Drawings is included in Section 3.11. A list of P) applicable Isometrics and Equipment Drawings is also included in each of the System Program U Plans of Section 4.1.

1

/ The supports of nonexempt components are subject to examination per Section Xl, IWF-1200.

Nonexempt component supports are shown on the ISI Isometrics and ISI Equipment Drawings listed in Section 3.11.

2 3.7 IS! Isometrics and Equipment Drawings UI The ISI Isometrics and ISI Equipment Drawings were developed to detail the ASME Code Class 1, 2, and 3 components (welds, bolting, etc.) and component supports which are subject to examination per ASME Section Xl. An index of these isometrics and equipment drawings is included on Inservice Inspection Drawing Cross Reference, ISI-REF, Sheets I and 2. The identification system employed on these drawings for welds, hangers and valves is included on ISI-REF Sheets 3 and 4. Each component and component support shown on the ISI Isometrics and Equipment Drawings is included in the ISI Database. The ISI-REF Sheets, Isometrics and Equipment Drawings arc stand alone drawings. They are listed as M-l 89-50 series of drawings.

A list of these drawings is included in subsection 3.11. A list of the applicable Isometrics and Equipment Drawings is also included in each System Program Plan of Section 4.1. The current revision level will be maintained by the ISI Coordinator.

3.8 Exempt ASME Class Components and Component Supports The WCGS ASME Class 1,2, and 3 components which are exempt from examination are those which meet the criteria of Section XI, subarticles IWB-1220, IWC-1220, and IWD-1220.

Component supports which meet the criteria of IWF-1230 are also exempt from examination.

Exempt components arc listed in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3". This document details the specific exemption criteria applicable to each component.

3.9 System Pressure Testing System Pressurc Testing activities at WCGS are performed in accordance with Wolf Creek Administrative Procedure AP 29A.004.

System Pressure Testing of ASME Class 1, 2, and 3 components will be performed per the requirements of Section XI, IWA-5000, lWB-5000, IWC-5000, and IWD-5000, as modified by Code Case NA984 (applicable to IWD-5000 only), Code Case N-533-1 and Code Case N-616 (with the conditions specified in Regulatory Guide 1.147).

Specific implementation of System Pressure Testing is included in Sections 4.1,4.2, and 4.3 of this Program Plan. A listing of the System Pressure Testing procedures is included in Table 4.2-1.

WCRE-16 3.0 - IS[ Program Description Revision 0 Page II of 19

I WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN A

G E 3.10 Calibration Blocks 0 Table 3.10-1 lists the calibration blocks required for thc ultrasonic (Ul) examinations scheduled in 1 this program plan. The calibration block design and material selection is in accordance with ASME J Section XI.

5, S

TABLE 3.10-1 WCGS CALIBRATION BLOCKS 0

Li BLOCK DESCRIPTION/TITLE DRAWING l APPLICABLE NUMBER NUMBER SYSTEM(S)

SAP-01 31.0" ID SA351 CF8A - BB SAP-07 27.5" ID SA351 CF8A BB 101 WC-03-PS-03.000-SA533 -GR.A-CL- 80C4192 BB 2-CSCL-101 102 WC-03-SG-03.000-SA533-GR.A- 80C4193 BB CL-2-CS-1 02 104 WC-5.0-SG-05.035-SA2I6-WCCA- 80C4195 BB CSCL-104 105 WC-29-XXX-02.33-SA351-CF8A- 80D4896 BB CCSS-1 05 106 WC-27 1/2-XXX-02.21-SA351- 80D4895 BB CF8A-CCSS-106 112 WC 160-00.438-SA312-TP304- 80D4894 BG SS-112 114 WC-04-160-00.531-SA.312-TP304- 80C4891 BB SS-114 117 WC-06-160-00.719-SA.312-TP304- 80C4891 EJ,EP,EM,BB SS-117 122 WC-1 0-140-01.000-SA358-TP304- 80C4891 EJ,EP CL.1-SS-122 126 WC-1 2-140-01.125-SA376-TP304- 80D4892 EJ SS-126 127 WC- 14-120-01.094-SA508-CL.1 -CS- 80D4892 AE 127 128 WC-12-80S-00.500-SA312-TP304- 80C4891 EJ SS-128 WCRE-16 3.0 - ISI Program Description Revision 0 Page 12 of 19

IL WOLF CREEK GENERATING STATION III THIRD INTERVAL IS1 PROGRAM PLAN A

G TABLE1 3.10-1 (Continued) 0 WCGS CALIBRATION STANDARDS E

1 I

BLOCK DESCRIPTION/TITLE DRAWING APPLICABLE NUMBER NUMBER SYSTEM(S) 5 130 WC-14-160-01.406-5A376-TP316- 80D4892 BB SS-130 0 131 WC-16-080-00.844-SA 106-GR.B- 80C4891 AE 6 CS-131 132 WC-28-01.500-SA 106-GR.B-CS-132 80D4892 AB 140 WC-N-7.0-7.99-SA540-GR.B24- 80D4903 BB CL.3-CS-1 40 144 WC-2.0-HPCI-02.000-SA240-TP304- 80D4915 EM SS-144 156 WC-02-160-00.344-SA312-TP304- 80D4897 BB SS-156 159 WC-04-080-00.337-SA106-GR.B- 80D4893 AB, AE, FC CS-1 59 169 WC-NSE-04-160-SA508-CL.2 80E4918 BB 160-SAI 82-F316L-BI-1 69 170 WC-NSE-06-160-SA508-CL.2 80E4922 BB 160-SA 182-F316L-BI- 170 171 WC-NSE-14-160-SA508-CL.2 80E4923 BB 160-SA182-F316L-BI-171 172 WC-00.875-RHR-00.750-SA240- 80D4917 EJ TP304-SS- 172 175 WC-II-RPV-1I -SA533-GR.B-CL.1- 80D8410 BB ASCL-175 176 WC-9-RPV-9-SA533*GR.B-CL.1 - 80D8411 BB ASCL-176 177 WC-7-RPV-7-SA533-GR.B-CL.1- 80D8412 BB ASCL-177 178 WC-F-XX-33-SA533 -GR.B-CL. I- 80D8413 BB ASCL-178 179 WC-NSE-XXX-3-SA I 82-GR316- 5D64166 BB (Note 1) CL.XX-XXX-3-SA508-GR.XX-CL2-BI-179 WCRE-16 3.0 - ISI Program Description Revision 0 Page 13 of 19

I WOLF CREEK GENERATING STATION f1 THIRD INTERVAL IS1 PROGRAM PLAN A

G E

TABLE 3.10-1 (Continued)

WCGS CALIBRATION STANDARDS 1

I BLOCK DESCRIPTION/TITLE DRAWING 2 NUMBER NUMBER JAPPLICABLE SYSTEM(S) 183 WC-12-STD-00.375-SA312-TP304- 80C4891 EJ SS-183 Li 192 WC-14-40S-00.438-SA358-TP304- 80C4891 BN,EN CL.1-192 193 WC-S-2.5-14-SA 193-GR.B7-CS-193 80C8415 AB 194 WC-S-4.5-37.5-SA540-GR.B24- future use BB CL.4-CS-194 Note 2 195 WC-S-7.0-58-SA5404iR.B24-CL.3- future use BB CS-195 Note 3 203 WC-08-40S-00.322-SA3] 2-TP304- M-1 89- EJ SS-203 10203 204 WC-1 0-40S-00.365-SA312-TP304- M-1 89- EJ SS-204 10204 8747 Alternate ASME Calibration Block Note 4 Note 5 A516-70 Steel 8748 Alternate ASME Calibration Type Note 4 Note 6 316 Stainless Steel 8749 Alternate ASME Calibration Type Note 4 Note 7 304 Stainless Steel 8750 Alternate ASME Calibration Block Note 4 Note 5 A516-70 Steel 8751 Alternate ASME Calibration Type Note 4 Note 6 316 Stainless Steel 8752 Alternate ASME Calibration Type Note 4 Note 7 304 Stainless Steel NOTES:

Note 1: Block 179 was modified by Westinghouse in 1996. Thedrawing number referenced isthe Westinghouse document number.

Note 2: Previous examinations were conducted utilizing either block 141 or Callaway block 93. The Interval 3 examinations will utilize block 194, or an equivalent RCP stud cal block meeting Section Xl requirements.

Note 3: Previous examinations were conducted utilizing either block 155 or Callaway block 95. The Interval 3 examinations will utilize block 195, or an equivalent RV stud cal block meeting Section Xl requirements.

WCRE- 16 3.0 - ISI Program Description Revision 0 Page 14 of 19

I WOLF CREEK GENERATING STATION 1 THIRD INTERVAL ISI PROGRAM PLAN A

G Note 4: The Alternate ASME Calibration Block is depicted on Figure4 of PDI-UT-l, Rev. C and PDI-UT-E 2, Rev. C.

D Note 5: The Alternate Calibration Blocks numbered 8747 and 8750 may be utilized in lieu of carbon steel 0 calibration blocks after approval by VICNOC Level Ill QC, ISI Engineering, and review by the 1 ANII.

3.

2 Note 6: The Alternate Calibration Blocks numbered 8748 and 8751 may be utilized in lieu of Type 316

/ stainless steel calibration blocks after approval by WCNOC Level III QC, ISI Engineering, and review by the ANII.

1S Note 7: The Alternate Calibration Blocks numbered 8749 and 8752 may be utilized in lieu of Type 304 2 stainless steel calibration blocks after approval by WCNOC Level IlI QC, ISI Engineering, and review by the ANII.

0 6

WCRE-1 6 3.0 - ISI Program Description Revision 0 Page 15 of 19

WOLF CREEK GENERATING STATION A THIRD INTERVAL ISIPROGRAM PLAN 6

E 3.11 Inservice Inspection Drawing Index o M-189-50 Series List

/ Reference Drawings M-1 89-501SI-REF SHEET I of 4 M-189-SOISI-REF SHEET 2 of 4 S M-1 89-501SI-REF SHEET 3 of 4 M-1 89-SOISI-REF SHEET 4 of 4 o AB System M-189-5OAB-01-01 SHEET 1 of I M-1 89-50AB-02-0 I SHEET 1 of I 6 M-189-50AB-03-01 SHEET I of 1 M-189-5OAB-04-01 SHEET I of 1 AE System M-189-5OAE-01-04 SHEET I of I M-1 89-5OAE-02-04 SHEET I of I M-189-5OAE-03-05 SHEET I of 1 M-189-5OAE-04-05 SHEET I of I AL System M-189-5OAL-OI-O ISHEET I of 2 M-189-5OAL-0I-O ISHEET 2 of 2 M-189-5OAL-01-02 SHEET I of 1 M-189-5OAL-02-03 SHEET I of I M-1 89-5OAL-03-04 SHEET I of I M-1 89-SOAL-04-02 SHEET I of 1 M-189-5OAL-05-03 SHEET I of I M-189-SOAL-06-04 SHEET I of I BB System M-189-5OBB-0O-O1 SHEET I of 1 M-189-5OBB-01-OI SHEET I of 1 M-189-50BB-01-02 SHEET I of I M-189-5OBB-01-04 SHEET I of 2 M-189-50BB-01-04 SHEET 2 of 2 M-189-5OBB-01-08 SHEET I of I M-189-5OBB-02-01 SHEET 1 of 1 M-189-5OBB-02-02 SHEET I of 1 M-189-SOBB-02-11 SHEET I of I M-189-5OBB-03-01 SHEET I of 1 M-189-5OBB-03-09 SHEET I of I M-189-5OBB-04-01 SHEET I of I M-189-5OBB-04-07 SHEET I of I M-189-5OBB-05-01 SHEET I of I M-189-5OBB-06-01 SHEET I of I WCRE-16 3.0 - ISI Program Description Revision 0 Page 16 of 19

h A1 WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN BG System B M-189-5OBG-O1-01 SHEET I of I E M-189-50BG-01-21 SHEET I of 1 f M-189-SOBG-02-22 SHEET I of 2 o M-1 89-5OBG-02-22 SHEET 2of 2 1 M-189-5OBG-03-23 SHEET I of I J M-189-5OBG-04-09 SHEET I of I

_ M-189-50BG-05-24 SHEET I of I 5 M-189-5OBG-06.02 SHEET I of 2

/ M-189-50BG-06-02 SHEET 2 of 2 2 M-189-5OBG-06-10 SHEET I of 1 0 BM System M-189-5OBM-01-01 SHEET I of I M-189-5OBM-01-02 SHEET I of I BN System M-189-SOBN-0O-0I SHEET I of 3 M-189-SOBN-0I-0I SHEET 2 of 3 M-189-5OBN-O1-O1 SHEET 3 of 3 EF System M-189-50EF-01-O1 SHEET I of 2 M-189-50EF-01-0I SHEET 2 of 2 M-189-SOEF-01-02 SHEET I of 2 M-189-50EF-01-02 SHEET 2 of 2 M-189-5OEF-01-03 SHEET 1 of 2 M-1 89-50EF-01 -03SHEET 2 of 2 M- 189-5OEF-0 1-07 SHEET I of I M-189-50EF-01-08 SHEET I of I M-1 89-50EF-01-09 SHEET I of I M-189-50EF-01-10 SHEET 1 of I M-1 89-50EF-02-OlSHEET I of 3 M-1 89-50EF-02-01 SHEET 2 of 3 M-1 89-5OEF-02-OlSHEET 3 of 3 M-1 89-50EF-02-04 SHEET I of I M-189-50EF-02-05 SHEET I of 2 M-189-50EF-02-(15 SHEET 2 of 2 M-189-50EF-02-06 SHEET I of I M-189-50EF-02-(18 SHEET I of 2 M-1 89-50EF-02-C8 SHEET 2 of 2 M-1 89-50EF-02-C9 SHEET I of I M-189-50EF-02-10 SHEET I of 1 WCRE-16 3.0 - ISI Program Description Revision 0 Page 17 of 19

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN EG System M-189-5OEG-Ol-O1 SHEET I of I M-189-50EG-01-02 SHEET I of 2 M-I 89-50EG-01-02 SHEET 2 of 2 M-I89-50EG-02-03 SHEET I of 2 M-1 89-5OEG-02-03 SHEET 2 of 2 M-1 89-50EG-02-05 SHEET I of 2 M-189-5OEG-02-05 SHEET 2 of 2 M-189-50EG-03-06 SHEET I of I M-189-50EG-03-07 SHEET I of I M-189-50EG-04-01 SHEET I of 2 M-189-50EG-04-01 SHEET 2 of 2 M-189-50EG-05-06 SHEET I of 2 M-189-50EG-05-06 SHEET 2 of 2 M-1 89-5OEG-06-09 SHEET I of 2 M-I 89-50EG-06-09 SHEET 2 of 2 EJ System M-189-50EJ-O1-0I SHEET I of 5 M-189-50EJ-O1-C'1 SHEET 2 of 5 M-189-50EJ-OI-COI SHEET 3 of 5 M-189.50EJ-OI-CO] SHEET 4 of 5 M-189-50EJ-OI-OI SHEET5 of 5 M-189-50EJ-01-04 SHEET I of I M-189-50E1-02-02 SHEET I of 5 M-1 89-50EJ-02-02 SHEET 2 of 5 M-189-50EJ-02-02 SHEET 3 of 5 M-1 89-50EJ-02-02 SHEET 4 of 5 M-189-50EJ-02-02 SHEET 5of 5 M-189-50EJ-02-04 SHEET I of 3 M-189-50EJ-02-04 SHEET 2 of 3 M-1 89-50EJ-02-04 SHEET 3 of 3 EM System M-189-SOEM-O1-O1 SHEET I of 1 M-189-50EM-02-01 SHEET I of 1 M-189-50EM-03-05 SHEET I of I M-189-SOEM-04-03 SHEET I of I M-189-50EM-05-01 SHEET I of 2 M-189-SOEM-05-01 SHEET 2 of 2 M-189-5OEM-06-02 SHEET I of 2 M-1 89-SOEM-06-02 SHEET 2 of 2 M-189-SOEM-06-03 SHEET I of I EN System M-189-50EN-OI-(II SHEET I of 2 M-189-50EN-O1-O1 SHEET 2 of 2 M-189-50EN-02-02 SHEET I of 2 M-189-50EN-02-02 SHEET 2 of 2 WCRE-16 3.0 - ISI Proglram Description Revision 0 Page I8 of 19

I WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN A

G EP System M-189-50EP-OI-01 SHEET I of I E M-1 89-50EP-02-02 SHEET I of I D M-1 89-50EP-03-02 SHEET I of I M-189-50EP-04-01 SHEET I of I 0 M-189-50FC-O1-OI SHEET I of I FC System GN System M- I 89-SOGN-O I-0 I SHEET I of 4 M-189-50GN-O1-0I SHEET 2 of 4

() M-189-50GN-O1-0I SHEET 3 of 4 M-189-50GN-O1-O1 SHEET4of4 0 M-189-50GN-02-02 SHEET I of 4 6 M-1 89-50GN-02-02 SHEET 2 of 4 M-1 89-SOGN-02-02 SHEET 3 of 4 M-1 89-SOGN-02-02 SHEET 4 of 4 KJ System M-189-SOKJ-O1-O1 SHEET I of 4 M-189-50KJ-O1-O1 SHEET2of4 M-189-5OKJ-O1 01 SHEET 3 of 4 M-189-5OKJ-O1 -01 SHEET 4 of 4 M- 189-50KJ-02-04 SHEET I of 4 M-189-50KJ-02-04 SHEET 2 of 4 M- 89-50KJ-02-04 SIIEET 3 of 4 M-I 89-5OKJ-02-04 SHEET 4 of 4 Equipment Drawings M-189-501SI-RBBOI SHEET I of 3 M-1 89-501SI-R13BOI SHEET 2 of 3 M-189-501SI-RBBOI SHEET 3 of 3 M-189-501SI-TBB03 SHEET I of 2 M-1 89-501SI-TBB03 SHEET 2 of 2 M-189-501SI-EBBOIA SHEET I of I M-189-501SI-EBBOIB SHEET I of I M-189-501SI-EBBOIC SHEET I of I M-189-5OlSI-EBBOID SHEET I of I M-189-501SI-EEJOIA SHEET I of I M-189-501SI-EEJOIB SHEET I of I M-1 89-501SI-PUMPS SHEET I of I WCRE-16 3.0 - ISI Program Description Revision 0 Page 19 of 19

I WOLF CREEK GENERATING STATION I1 THIRD INTERVAL ISI PROGRAM PLAN A

G 4.0 WCGS SYSTEM INSERVICE INSPECTION PROGRAM PLANS E

This Section includes system specific ISI Program Plans which detail the examinations and tests scheduled for each WCGS 0

l system included in the ISI Program. Section 4.0 has been subdivided into three subsections:

I Subsection 4.1 includes systems which are subject to Section Xl NDE or Augmented NDE. NDE is defined as Volumetric, Surface, Visual VT-I, and Visual VT-3 examinations. The systems in subsection 4.1 are also subject to Visual VT-2 examinations during system pressure testing.

5 Subsection 4.2 includes systems which are subject to ASME Section XI System Pressure Testing only. These systems or 2 portions of these systems include exempt Class 1, Class 2, and Class 3 components (per IWB-1220, IWC-1220, or IWD-0 1220) only.

0 Subsection 4.3 includes Class 2 components which are exempt Section XI NDE and Augmented NDE and are also excluded 6 from periodic system pressure testing per IWA-5I 10(c): piping that penetrates a containment vessel where the piping and isolation valves perform a containment function and the balance of the piping system is outside the scope of Section Xi.

Note that Section 4.3 includes GS System piping across penetration P-65, line 25-HBB-6". As noted in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3", this line cannot be exempted per the criteria of IWC-1222. As a result, this line, which includes two (2) piping welds, was evaluated in the Risk Informed ISI Program and determined to be Low Risk with no Damage Mechanism. Because of this determination, no examinations were planned for this piping during Interval 3, and the GS System is not included in Section 4.1.

WCRE-I 6 4.0 System Inservice Inspection Program Plans Revision 0 Page I of I

I WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN A

G E

Cl 1

f I

5 0

6 4.1 WCGS SYSTEMS SUBJECT TO SECTION Xi NDE OR AUGMENTED NDE WCRE- 16 4.1 WCGS Systems Subject To Section XI NDE Revision 0 or Augmented NDE Page I of I

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.1 Main Steam System (AB)

A. Applicable System Piping and Instrument Drawings

1. M-12ABOI-Main Steam System

2. M-12AB02-Main Steam System B. Classification Of Components Details of the classification of the Main Steam System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

C. Nonexempt and Exempt ASME Class Components A listing of Nonexempt and Exempt ASME Class Components are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Main Steam System. These drawings are part of the M-189-50 series.

1. M-189-50AB-01-01 Sheet I Main Steam Loop 1

2. M-189-50AB-02-01 Sheet I Main Steam Loop 2

3. M-189-50AB.03-01 Sheet 1 MainSteamLoop3

4. M-189-50AB-04-01 Sheet I Main Steam Loop 4 WCRE-16 4.1 WCGS Systems Sutject To Section XI NDE Revision 0 or Augmented NDE Page I of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL IS[ PROGRAM PLAN 4.1.1 Main Steam System (AB)

E. Summary or Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table I is a summary of the components and items subject to NDE per ASME Scction XI or per Augmented requirements. A detailed listing of these components and items is maintained in the ISI Database.

TABLE I SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM Pi P2 P3 INTERVAL PIPING WELDED C-C C3.20 2 0 1 0 1 ATTACHMENTS PRESSURE RETAINING C-D C4.40 -4 1 0 0 O BOLTING Note 3 PIP.. C .MPAWFNT F-A FP.20 32 2 2 2 6 SUPPORTS PIPING WELDS NOT R-A RI.20 8I 0 0 0 0 SUBJECT TO A DAMAGE Note I Note I MECHANISM _ _ _ _ _ _ _ _ _

PIPING WELDS NOT SUBJECT TO A DAMAGE R-A RI.20 USAR 3.6.2 84 2 1 1 4 MECHANISM Note I Note I Note 2 AND SUBJECT TO HELB REQUIREMENTS __

PIPING WELDS NOT USAR 3.6.2 119 0000 SUBJECT TO HELB REQUIREMENTS._ -

Note 1: See Section H for an explanation of Category R-A and Item Rl.xx nomenclature.

Note 2: These welds selected for examination under RI-HELB requirements only.

Note 3: Examination of Pressure Retaining Bolting is performed in accordance with Code Case N-652. See Note 2 in Paragraph I for selection and scheduling criteria.

WCRE-16 4.1.1 Main Steam System (AB) Revision 0 Pare 2 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL SI PROGRAM PLAN 4.1.1 Main Steam System (AB)

F. Augmented ISI Requirements The following Augmented ISI requirements apply to the Main Steam System:

1. WCGS USAR Sections 3.6.1, Postulated Piping Failures In Fluid Systems Inside and Outside Containment and 3.6.2, Determination Of Break Locations and Dynamic Effects Associated With The Postulated Rupture Of Piping- WCGS has implemented a Risk Informed-High Energy Line Break program as an alternative to the examination methodology of USNRC Branch Technical Position MEB 3-1. This program is maintained in WCRE-14 and is applicable to the piping within the "no break zone" associated with high energy piping in containment penetration areas. The "no break zone" is an area where pipe breaks were not postulated due to the stress levels being within limits specified in USAR Section 3.6.2. The applicable welds are shown on the Main Steam Isometrics within the "No Break Zone" and included in Tables AB-3, AB-2, and AB-3 with Category "USAR" and Item No. "3.6.2".

When a specific degradation mechanism (DM) exists at a selected location, then the volume to be examined shall be as recommended in Section 4 of EPRI TR-I 12657 Rev. B-A. Welds subject to a DM are identified by a note in the Table. Welds selected that have no associated DM shall have the volume examined as shown in Figures 4.14 of TR-I 12657 Rev. B-A.

G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWC-S000, the Class 2 pressure retaining components within the Main Steam System will receive a system leakage test per IWC-5220 each inspection period.

Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Program A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class I and 2 piping welds at WCGS. This program is described in detail in Section 2.3. Since the EPRI methodology used for the RI-ISI Program does not prescribe Code Examination Category and Item Numbers, the assignment of these designators is the same as utilized in Code Case N-578-I. No welds in the Main Stearn System were selected for examination in the RI-IS! program.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table AB-1 (Period I Examinations), Table AB-2 (Period 2 Examinations), and Table AB-3 (Period 3 Examinations). The following Notes apply to the tables:

1. These welds have been selected per the RI-HELB Program. The requirements for examination of these welds are discussed in Paragraph F above.

2. Examination of Pressure Retaining Bolting is performed in accordance with Code Case N-652.

The examination may be performed on the bolting in place under load or upon disassembly of the connection. The examination of bolting for valves may be conducted on one valve among a group of valves that are similar in design, size, function, and service. See Code Case N-652, Category C-D, Note 3.

WCRE-16 4.1.1 Main Steam System (AB) Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE AB-1 l Period1 Examinations I I System: ABl Relief Request or Component Name Drawing Number Component Description Size Thidcness NDE Method Category Item Cal Bb ck Notes AB-O4--1 4-b AB-014-1 VALVE HV-14 BONNET BOLTING 2.5 NA UT C-D C4.40 193 2 AB4-1-C002 AB-014-1 PIPING SUPPORT 28 VT-3 F-A F1.20 AB-41-HOI AB402-01 PIPING SUPPORT 28 VT-3 F-A F1.20 AB-01-FW07 AB-01-01 28' MAIN STEAM HEADER TO FLUED HEAD (P-2) 28 1.5 UT USAR 3.6.2 132 1 AS-0I.F074 AB-04-01 28' MAIN STEAM HEADER TO FLUED HEAD (P-1) 28 1.5 UT USAR 3.6.2 132 1 WCRE-1 6 4.1.1 Main Steam System (AB) Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE AB.2 Perod 2 Examinations ISystem: AS Relief Request Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block or Notes AB-01-ROIO AB-02-01 PIPING INTEGRAL ATTACHMENTS 28 MT C-C C3.20 AB-01-RO01 AB-04-01 PIPING SUPPORT 28 VT-3 F-A F1.20 AB-O -R003 AB-03-01 PIPING SUPPORT 28 VT-3 F-A F1.20 AB-01-F026 AB-02-01 28' MAIN STEAM HEADER TO FLUED HEAD (P-3) 28 1.5 UT USAR 3.6.2 132 1 WCRE-16 4.1.1 Main Steam System (AB) Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE AB-3 Period 3 Examinations l System: AB Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes AB-1-COII AB-03-01 PIPING SUPPORT 10 VT-3 F.A F1.20 AB-01-H005 AB-03-01 PIPING SUPPORT 28 VT-3 F-A F1.20 AB-1-F050 AB-03-01 28" MAIN STEAM HEADER TO FLUED HEAD (P-4) 28 1.5 UT USAR 3.8.2 132 1 WCRE-I 6 4.1.1 Main Steam System (AB) Revision 0 Page 6 of 6

I WOLF CREEK GENERATING STATION M THIRD INTERVAL ISI PROGRAM PLAN A

G 4.1.2 Feedwater System (AE)

E 0 A. Applicable System Piping and Instrument Drawings 1 1. M-12AE02-Feedwater System B. Classification Of Components Details of the classification of the Feedwater System components for 1SI are included in "Inservice

1) Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

0 C. Nonexempt and Exempt ASME Class Components 6

A listing of Nonexempt and Exempt ASME Class Components are included in "Inservice Inspection Classification Basis Document Wolf-Creek Generating Station Interval 3".

D. Applicable IS Isometrics and IS1 Equipment Drawings The following isometrics and drawings detail the noncxempt components and items subject to NDE in the Feedwater System. These drawings are included in the M-1 89-50 series.

I. M-189-5OAE-01-04 Sheet I Main Feedwater Loop I

2. M-l 89-50AE-02-04 Sheet I Main Feedwater Loop 2

3. M-189-5OAE-03-05 Sheet I Main Feedwater Loop 3

4. M-l 89-50AE-04-OS Sheet I Main Feedwater Loop 4 WCRE-16 4.1.2 Feedwater System (AE) Revision 0 Page I of 7

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.2 Feedwater System (AE)

E. Summary or Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table I is a summary of the components and items subject to NDE per ASME Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the ISI Database.

TABLE I SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM PI P2 P3 INTERVAL PIPING INTEGRAL C-C C3.20 - 12 1 I 0 2 ATTACHMENTS PIPING WELDS SUBJECT R-A RI.11 - 16 2 0 2 TO THERMAL FATIGUE Note I Note I.

PIPING WELDS SUBJECT R-A R .1I USAR 3.6.2 17 4 3 2 9 TO THERMALFATIrGrEI AND HELB Note 1 Note I REQUIREMENTS PIPING WELDS NOT R-A RI.20 54 0 0 0 0 SUBJECT TO A DAMAGE Note I Note I MECHANISM PIPING WELDS NOT R-A RI.20 USAR 3.6.2 55 0 0 1 1 MECHANISM. Note I Note I AND SUBJECT TO HELB REQUIREMENTS PIPING COMPONENT F-A P1.20 - 44 3 3 3 9 SUPPORTS PIPING WELDS USAR 3.6.2 8 0 0 0 0 SUBJECT TO HELB REQUIREMENTS.

Note 1: See Section H for an explanation of Category R-A and Item RI .xx nomenclature.

WCRE-16 4.1.2 Feedwater System (AE) Revision 0 Page 2 of 7

WOLF CREEK GENERATING STATION A THIRD INTERVAL ISI PROGRAM PLAN A

E 4.1.2 Feedwater System (AE)

Cl F. Augmented ISI Requirements The following Augmented ISI requirements apply to the Feedwater System:

1. WCGS USAR Sections 3.6.1, Postulated Piping Failures In Fluid Systems Inside and E Outside Containment and 3.6.2, Determination Of Break Locations and Dynamic Effects Associated With The Postulated Rupture Of Pipin - WCGS has implemented a Risk Informed-High Energy Line Break program as an alternative to the examination methodology of USNRC Branch Technical Position MEB 3-1. This program is Q maintained in WCRE-14 and is applicable to the piping within the "no break zone"

J associated with high energy piping in containment penetration areas. The "no break zone" is an area where pipe breaks were not postulated due to the stress levels being within limits specified in USAR Section 3.6.2. The applicable welds are shown on the Feedwater System Isometrics within the "No Break Zone" and included in Tables AE-1, AE-2, and AE-3 with Category "USAR" and Item No. "3.6.2". For welds selected to be examined under the RI-HELB program, the examination volume shall be the same as described for RI-ISI, given in paragraph H below.

G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining components within the Feedwater System will receive a system leakage test per IWC-5220 each inspection period.

Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class I and 2 piping welds at WCGS. This program is described in detail in Section 2.3.

Feedwater System welds selected for examination per the RI-ISI program are listed in Tables AE-1, AE-2 and AE-3. Since the EPRI methodology used for the RI-ISI Program does not prescribe Code Examination Category and Item Numbers, guidance was taken from Code Case N-578-1 for the assignment of these designators.

Much of the AE system has flow accelerated corrosion (FAC) identified as a degradation mechanism. Because the WCNOC augmented inspection program for FAC is relied upon to manage this DM, no examination under the RI-ISI program is required.

When a specific degradation mechanism (DM) exists at a selected location, then the volume to be examined shall be as recommended in Section 4 of EPRI TR- 12657 Rev.

B-A. Welds subject to a DM are identified by a note in the Table. Welds selected that have no associated DM shall have the volume examined as shown in Figures 4.1-4 of TR-112657 Rev. B-A.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table AE-I (Period I Examinations), Table AE-2 (Period 2 Examinations),

and Table AE-3 (Period 3 Examinations). The following Notes apply to the tables:

1. These welds have been selected for examination per the RI-ISI Program. The requirements for examination of these welds are included in Paragraph H above.

WCRE-16 4.1.2 Feedwater System (AE) Revision 0 Page 3 of 7

WOLF CREEK GENERATING STATION THIRD INTERVAL IS PROGRAM PLAN

2. These welds have been selected for examination per the RI-HELB Program. The requirements for examination of these welds are included in Paragraph F above.

3. These welds have Thermal Fatigue identified as the degradation mechanism.

WCRE-I 6 4.1.2 Feedwater System (AE) Revision 0 Page 4 of 7

WOLF CREEK GENERATING STATION THIRD INTERVAL 1S1 PROGRAM PLAN TABLE AE.1 I-Perlod I ExaminationsI I System: AE I Relief Request or Component Name .

Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes AE-04-R007 AE-01-04 PIPING INTEGRAL ATTACHMENTS 14 MT C-C C3.20 AE-04-R007 AE-01-04 PIPING SUPPORT 14 VT-3 F-A F1.20 AE-04-R023 AE-01-04 PIPING SUPPORT 14 VT-3 F-A F1.20 AE-05-R011 AE-03-05 PIPING SUPPORT 14 VT-3 F-A F1.20 AE-04-F0 55 Iu rar&: ,l oAl. ImLC I'ut 16 0.844 UT R-A R1.11 131 1,3 AE-04-S010-C AE-01-04 167X14-REDUCER TO 16 PIPE 16 0.844 UT R-A R1.11 131 1.3 AE-04-S025-A AE-01-04 4" PIPE TO 4' ELBOW 4 0.337 UT R-A R1.11 159 1,2.3 AE.04-S025-A AE-01-04 4- PIPE TO 4 ELBOW 4 0.337 UT USAR 3.6.2 159 1,2.3 AE-04-S025-B AE-01-04 4- ELBOW TO 4- PIPE 4 0.337 UT R-A R1.11 159 1,2,3 AE-04-S025-B AE-01-04 4- ELBOW TO 4- PIPE 4 0.337 UT USAR 3.6.2 159 1,2,3 AE-04-S025-C AE-01-04 4- PIPE TO 4" ELBOW 4 0.337 UT R-A R1.20 159 1,2, AE-04-S025-C AE-01-04 4- PIPE TO 4" ELBOW 4 0.337 UT USAR 3.6.2 159 1,2, AE-05-F038 AE-04-05 4" WELDOLET TO 4- PIPE 4 0.337 UT R-A R1.11 159 1,2,3 AE-05-F038 AE-04-05 4- WELDOLET TO 4 PIPE 4 0.337 UT USAR 3.6.2 159 1,2,3 WCRE-16 4.1.2 Feedwater System (AE) Revision 0 Page 5 of 7

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE AE-2 Period 2 ExaminationsI I System: AEr Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes AE-05-R028 AE-04-05 PIPING INTEGRAL ATTACHMENTS 14 MT C-C C3.20 AE-04-RO19 AE-01-04 PIPING SUPPORT 14 VT-3 F-A F1.20 AE-05-COO1 AE-03-05 PIPING SUPPORT 14 VT-3 F-A F1.20 AE-05-R028 AE-04-05 PIPING SUPPORT 14 VT-3 F-A F1.20 AE-04-F040 AE-02-04 4" WELDOLET TO 4' PIPE 4 0.337 UT R-A R1.11 159 1,2.3 AE-04-F040 AE-02-04 4" WELDOLET TO 4 PIPE 4 0.337 UT USAR 3.6.2 159 1,2.3 AE-04-S026-A AE-02-04 4" PIPE TO 4" ELBOW 4 0.337 UT R-A R1.11 159 1.2,3 AE-04-S026-A AE-02-04 4" PIPE TO 4" ELBOW 4 0.337 UT USAR 3.6.2 159 1,2,3 AE-04-S026-B AE-02-04 4" ELBOW TO 4" PIPE 4 0.337 UT R-A R1.11 159 1,2,3 AE-04-S026-R AE-02-04 4" ELBOW TO 4 PIPE 4 0.337 UT USAR 3.6.2 159 1.2,3 WCRE-16 4.1.2 Feedwater System (AE) Revision 0 Page 6 of 7

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE AE-3 I Period 3 Examinations ISystem: AE Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes AE-04-RO1 6 AE-02-04 PIPING SUPPORT 14 Vr-3 F-A F1.20 AE-04-HOO1 AE-02-04 PIPING SUPPORT 14 Vr-3 F-A F1.20 AE45-R017 AE-03-05 PIPING SUPPORT 14 VT-3 F-A F1 .20 AE-05-F033 AE-03-05 4" PIPE TO VALVE V127 4 0.337 UT R-A R1 .11 159 1,2,3 AE-05-F033 AE-03-05 4 PIPE TO VALVE V127 4 0.337 UT USAR 3.6.2 159 1,2,3 AE-05-FW900 AE-03-05 4 ELBOW TO 4" PIPE 4 0.337 UT R-A R1 .1 159 1.2.3 AE-05-FW900 AE-03-05 4" ELBOW TO 4 PIPE 4 0.337 UT USAR 3.6.2 159 1,2.3 AE-05-FO1 6 AE-03-05 14" ELBOW TO TORSIONAL RESTRAINT 14 0.938 UT USAR 3.6.2 127 2 WCRE-16 4.1.2 Feedwater System (AE) Revision 0 Page 7 of 7

II WOLF CREEK GENERATING STATION M THIRD INTERVAL 1SI PROGRAM PLAN A

4.1.3 Auxiliary Feedwater System (AL)

E

[)

0 A. Applicable System Piping and Instrument Drawings 1

1. M-12ALO I -Auxiliary Feedwater System B. Classification Of Components 5 Details of the classification of the Auxiliary Fecdwater System Components for ISI are included in "Inservice Inspection Classification Basis Document Wolf 0 Creek Generating Station Interval 3'.

C. Nonexempt and Exempt ASME Class Components A listing of Nonexempt and Exempt ASME Class Components are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and 1SI Equipment Drawings The following isometrics detail the rnonexempi components and items subject to NDE in the Auxiliary Feedwater System. These drawings are part of the M-189-50 series.

1. M-189-50AL-OI-Ol Sheet I Auxiliary Feedwater Turbine Driven Pump Suction Piping

2. M-189-5OAL-01-01 Sheet 2 Auxiliary Feedwater Pump Motor Driven Pump Suction Piping

3. M-189-50AL-01-02 Sheet I Motor Driven Auxiliary Feedwater Pump "A" Discharge Piping

4. M-1 89-50AL-02-03 Sheet I Motor Driven Auxiliary Feedwater Pump "B" Discharge Piping Feedwater

5. M-189-50AL-03-04 Sheet I Turbine Driven Auxiliary Feedwater Pump Suction Piping

6. M-189-50AL-04-02 Sheet I Motor Driven Auxiliary Feedwater Pump "A" Discharge Piping

7. M-189-SOAL-05-03 Sheat I Motor Driven Auxiliary Feedwater Pump "B" Discharge Piping

8. M-189-50AL-06-04 Sheet I Turbine Driven Auxiliary Feedwater Pump Discharge Piping WCRE-16 .4.1.3 Auxiliary Feedwater (AL) Revision 0 Page I of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL IS PROGRAM PLAN 4.1.3 Auxiliary Feedwater (AL)

E. Summary OrComponents Subject To Section XI and Augmented NDE/Scheduled For Examination Table I is a summary of the components and items subject to NDE per ASME Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the IS! Database.

TABLE I SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AU AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM PI P2 P3 INTERVAL PIPING WELDED C-C C3.20 9 1 0 0 ATTACHMENTS C-C_____0_

PIPING WELDED D-A DI.20 . 10 0 0 1 1 ATTACHMENTS PIPING COMPONENT F-A F 1.20 32 2 1 2 5 SU PPOR TS _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I__ I___ _ _ _ _ _ _ _ _ _

PIPING COMPONENT F-A F1.30 , 45 1 2 2 5 SUPPORTS ____

EQUIPMENT SUPPORTS F-A F1.40 8 0 4 0 4 (Other Than Piping) _

PIPING WELDS NOT R-A RI.20 126 0 0 0 0 SUBJECT TO A DAMAGE Note I Note I MECHANISM Note 1: See Section H for an explanation of Category R-A and Item R.I.xx nomenclature.

WCRE-16 4.1.3 Auxiliary Feedwater (AL) Revision 0 Page 2 of 6

I WOLF CREEK GENERATING STATION M THIRD INTERVAL ISI PROGRAM PLAN A

G 4.1.3 Auxiliary Feedwater (AL)

E i F. Augmented ISI Requirements 0 No Augmented ISI requirements apply to the Auxiliary Feedwater System.

1

/

G. System Pressure Testing 5 In accordance with Section Xl, IWA-5000 and IWC-S000, the Class 2 pressure retaining components within the Auxiliary Feedwater System will receive a system leakage test per IWC-5220 each inspection period.

0 0 In accordance with Section Xi, IWA-5000 and IWD-5000, the Class 3 pressure retaining components within the Auxiliary Feedwater System will receive a system leakage test per 6 IWD-5221 every period and a system hydrostatic test per IWD-5222 at or near the end of the interval. As allowed by Code Case N-498-4, alternative rules may be employed in lieu of the system hydrostatic test of IWD-5222.

Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Program A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class I and 2 piping welds at WCCGS. This program is described in detail in Section 2.3. Since the EPRI methodology used for the RI-ISI Program does not prescribe Code Examination Category and Item Numbers, guidance was taken from Code Case N-578- I for the assignment of these designators. No welds in the Auxiliary Feedwater System were selected for examination in the RI-IS] program.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table AL-I (Period I Examinations), Table AL-2 (Period 2 Examinations),

and Table AL-3 (Period 3 Examinations).

WCRE-16 4.1.3 Auxiliary Feedwater (AL) Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL 1ST PROGRAM PLAN TABLE AL-1 l Perlod I Examinationsl I System: AL I Component Name Drawing Number Component Size Thickness NDE Method Category Item Relief Request Notes AL-04-C013 AL06-04 PIPING INTEGRAL ATTACHMENT 4 PT C-C C3.20 AL-03-RO1 1 AL-0-03 PIPING SUPPORT 4 VT-3 F-A F1.20 AL-04-C013 AL-06-04 PIPING SUPPORT 4 Vr-3 F-A F1.20 AL-03-ROIO AL-02-03 PIPING SUPPORT 6 VT-3 F-A F1.30 WCRE-1 6 4.1.3 Auxiliary Feedwater (AL) Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE AL.2 Period 2 Examinatlons I System: AL I Component Name Drawing Number Component Size Thickness NDE Method Category Item Relief Request Notes AL-03-C004 AL-05-03 PIPING SUPPORT 4 VT-3 F-A F1.20 AL-03-C005 AL-02-03 PIPING SUPPORT 6 VT-3 F-A F1.30 AL-04-C002 AL.03-04 PIPING SUPPORT 6 VT-3 F-A F1.30 PAL02-SUP-1 AL-01-01 SHT. 1 PUMP SUPPORT 10 VT-3 F-A F1.40 PAL02-SUP-2 AL-01-01 SHT. 1 PUMP SUPPORT 10 VT-3 F-A F1.40 PAL01A-SUP-1 AL-01-01 SHT.2 PUMP SUPPORT 8 VT-3 F-A F1.40 PALOIA-SUP-2 AL-01-01 SHT.2 PUMP SUPPORT 8 VT-3 f-A F1.40 WCRE-16 4.1.3 Auxiliary Feedwater (AL) Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE AL-3 l Period 3 Examinations I I System: AL Component Name Drawing Number Component Size Thickness ND[ - Method Category Item Relief Request Notes AL-03-AOOI AL-02-03 PIPING INTEGRAL ATTACHMENTS 6 VT-1 D-A D1.20 AL-04-R014 AL-06-04 PIPING SUPPORT 4 VT-3 F-A F1.20 AL-02-RO1 1 AL-04-02 PIPING SUPPORT 4 VT-3 F-A F1.20 AL-02-C003 AL-01-02 PIPING SUPPORT 6 VT-3 F-A F1.30 AL-03-AOO1 AL-02-03 PIPING SUPPORT 6 VT-3 F-A F1.30 WCRE-16 4.1.3 Auxiliary Feedwater (AL) Revision 0 Page 6 of 6

I1 WOLF CREEK GENERATING STATION A THIRD INTERVAL IS[ PROGRAM PLAN G 4.1.4 Reactor Coolant System (BB) o A. Applicable System Piping and Instrument Drawings 1 . M-12BBOI-Reactor Coolant System

2. M-12BB02-Reactor Coolant System*

3. M-12BB03-Reactor Coolant System 2

• Except for ASME Class 2 components listed in Section 4.3 U B. Classification Of Components L6. Details of the classification of the Reactor Coolant System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

C. Nonexempt and Exempt ASME Class Components A listing of Noncxempt and Exempt ASME Class components are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Reactor Coolant System. These drawings are part of the M-1 89-50 series.

I. M-189-50BB-OO-O Sheet I Reactor Coolant System Primary Loop General Layout

2. M-189-SOBB-I3-01I Sheet I Reactor Coolant Loop I

3. M-189-5OBB-01-02 Sheet I Reactor Coolant Pressurizer Relief Header

4. M-189-5OBB-01-04 Sheet I Reactor Coolant Pressurizer Spray Line

5. M-189-5OBB-301-04 Sheet 2 Reactor Coolant Pressurizer Spray Line

6. M-189-5OBB-01-08 Sheet I Reactor Coolant Pump "A" Seal Water Injection Line

7. M-1 89-50BB-02-01 Sheet I Reactor Coolant Loop 2

8. M-189-50BB-02-02 Sheet I Reactor Coolant Pressurizer Safety Valve Lines

9. M-189-50BB-02-11 Sheet I Reactor Coolant Pump "B" Seal Water Injection Line WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page I of4l

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN D. Applicable 1SI Isometrics and ISI E-quipment Drawings (Cont'd)

10. M-1 89-5OBB-03-01 Sheet I Reactor Coolant Loop 3

11. M-189-SOBB-03.09 Sheet I Reactor Coolant Pump "C" Seal Water Injection Line

12. M-189-SOBB-04-01 Sheet I Reactor Coolant Loop 4

13. M-189-50BB-04-07 Sheet I Reactor Coolant Pump "D" Seal Water Injection Line

14. M-1 89-50BB.05-01 Sheet I Reactor Coolant Pressurizer Surge Line is. M-189-50BB-06-01 Sheet I Reactor Coolant Loop Drain To Reactor Coolant Drain Tank

16. M-189-50]SI-RBBOI Sheet I Reactor Vessel

17. M-189-501SI-RBBOI Sheet 2 Reactor Vessel

18. M-189-501SI-RBBOI Sheet 3 Reactor Vessel

19. M-189-501SI-TBBOI Sheet I Pressurizer Vessel

20. M-189-501SI-TBBOI Sheet 2 Pressurizer Vessel

21. M-189-501SI-EBBOIA Sheet I Steam Generator EBBOIA

22. M-189-501SI-EBBOIB Sheet I Steam Generator EBBOIB

23. M-189-5OlSI-EBBOIC Sheet I Steam Generator EBBOIC

24. M-189-501SI-EBBOID Sheet I Steam Generator EBBOID

25. M-189-501SI-PUMPS Sheet I ISI Pumps WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 2 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL 1SI PROGRAM PLAN 4.1.4 Reactor Coolant (BB)

E. Summary Of Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table I is a summary of the components and items subject to NDE per ASME Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the ISI Database.

TABLE I SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM l CODE l CODE AUG. l AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM PI P2 P3 INTERVAL Circumferential Shell B-A BI.I- 2 0 0 2 2 Welds, Reactor Vessel l Longitudinal Shell Welds, B-A B1.12 0 0 l Reactor Vessel l Circumferential Head B-A B1.21 . 3 0 0 3 3 Welds, Reactor Vessel Meridional Head Welds, B-A B1.22 8 1 2 5 8 Reactor Vessel Shell-to-Flange Weld, B-A BI.30 I 0 0 1 N Reactor Vessel Note 4 Head-to-Flange Weld, B-A B1.40 I 0 0 1 N 4 Reactor Vessel Note 4 Circumferential Shell-To- B-B B2.11 _ 2 1 I 0 2

[Head Welds, Pressurizer Longitudinal Shell-To- B-B B2.12 2 0 I 1 2 Head Welds, Pressurizer Tube Sheet-To-Head B-B B2.40 - 4 0 0 l Weld, Steam Generator Nozzle-to-Vessel Welds, B-D B3.90 8 0 0 8 Reactor Vessel Nozzle Inside Radius B-D B3.100 - -I8 0 0 8 8 Section, Reactor Vessel WCRE-I 6 4.1.4-Reactor Coolant System (BB) Revision 0 Page 3 of41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE I SECTION Xl AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM Pi P2 P3 INTERVAL Nozzlc-to-Vessel Welds, B-D B3.1 10 6 2 2 2 6 Pressurizer Nozzle Inside Radius B-D B3.120 . 6 2 2 2 6 Section, Pressurizer Note I Nozzle Inside Radius B-D B3.140 8 3 3 2 8 Section, Stearn Generator Note I Reactor Vessel Closure B-G-1 B6.10 54 18 18 1854 Head Nuts Note 2 Reactor Vessel Closure B-G-l B6.20 54 18 18 18 54 Studs Note 2 Threads in Reactor Vessel B-G-I B6.40 -54 18 18 84 Flange Note 2 Reactor Vessel Closure B-G-I B6.50 -54 18 18 54 Washers Note 2 Bolts & Studs in Pumps B-G-I B6.180 4 0 0 1 1 Note 2 Flange Surface, When B-G-I 86.190 4 0 0 1 1 Connection Disassembled, Note 2 in Pumps __.

Nuts, Bushings, & B-0-1 B6.200 4 0 0 1 I Washers in Pumps I Note 2 Bolts, Studs, & Nuts in B-G-2 B7.20 . I I 0 0 1 Pressurizer Note 2 Bolts, Studs & Nuts in B-G-2 B7.30 . . 8 0 0 2 2 Steam Generator Note 2 Bolts, Studs & Nuts in B-G-2 B7.50 7 1 1 0 2 Piping Note 2 WCRE-16 4.1.4-Reactor Coolant System (BB) Revision 0 Page 4 of4l

WOLF CREEK GENERATING STATION THIRD INTERVAL IS1 PROGRAM PLAN TABLE 1 SECTION Xl AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO, SYSTEM Pi P2 P3 INTERVAL Bolts, Studs & Nuts in B-G-2 B7.60 - 4 0 0 1 Pumps ____ Note 2 Bolts, Studs & Nuts in B-G-2 B7.70 - 3 1 0 0 Valves Note 2 Welded Attachments For Vessels, Piping, Pumps and B-K B310.10 - 2 Valves _ See Paragraph 1,Note 11 Pump Casings B-L-2 B12.20 - 4 *

• 0

• See Paragraph 1,Note 7 Valve Bodies B-M-2 B12.50 3 I Exceeding NPS 4 'See Paragraph 1,Note 8 Vessel Interior B-N-I B 13.10 I 1 1 1 3 Interior Attachments B-N-2 B13.60 6 0 0 6 6 Beyond Beltline Region in Reactor Vessel Core Support Structure in B-N-3 B 13.70 - - I 0 0 1 Reactor Vessel Welds in CRD Housings B-O B14.10 - - 6 4 0 0 4 Steam Generator Tubing B-Q B 16.20 - - - See Paragraph 1,Note 10 PipingComponent F-A P1.10 - - 86 5 10 7 22 Supports Equipment Supports F-A F1.40 - 79 8 12 ll 31 (Other Than Piping)

Piping Welds Subject to R-A R. 11 38 3 5 3 11 Thermal Fatigue Note 6 Note 6 Piping Welds Not Subject to R-A RI.20 299 9 8 12 29 a Damage Mechanism Note 6 Note 6 WCRE-16 4.1.4-Reactor Coolant System (BB) Revision 0 Page 5 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE 1 SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM P1 P2 P3 INTERVAL Piping Welds Subject USAR 3.6.2 57 0 0 0 0 To HELB Requirements Reactor Coolant Pump AUG.1 AUG.FW 4 *

• 4 4 Flywheel

• See Paragraph. I, Note 9 Shell Circumferential C-A CI.10 . 12 2 1 0 3 Welds Head Circumferential C-A Ct.20 4 0 1 0 1 Welds I Tubesheet-to-Shell Weld C-A CI.30 _ - 4 1 0 0 Nozzle-to-Shell (or Head) C-B C2.21 8 1 0 1 2 Welds in Vessels Without Reinforcing Plate, Greater Than 1/2 Nominal Thickness Nozzle Inside Radius C-B C2.22 4 l 0 0 Section in Vessels Without Reinforcing Plate, Greater than 1/2" Nominal Thickness WCRE-16 4.1.4-Reactor Coolant System (BB) Revision 0 Page 6 of41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE I SECTION Xl AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM DESCRIPTION l CODE CATEGORY l 1 ITEM CODE NO.

AUG.

CATEGORY AUG TOTAL IN EXAMS BY PERIOD & INTERVAL ITEM NO. SYSTEM Pi P2 P3 INTERVAL Reactor Vessel Head B-E B4.11 EA-03-009 EA-03-009UT I I 0 e 2 Vent Penetrations UT Exam Note 5 Reactor Vessel Head E-E B4.12 EA-03-009 EA-03-009UT 78 78 0 78 156 CRDM Penetrations UT Examr Note5 Reactor Vessel Head B-E B4.11 EA-03-009 EA-03-009BMV 0 Vent Penetrations BMV Exam _ Note 5 Reactor Vessel Head B-E B4.12 EA-03-009 EA-03-009BMV 78 78 78 0 156 CRDM Penetrations BMV Exam _ _ 4 A ote 5 Piping Butt Welds Subject R-A R1.20 MRP-139 MRPI39DI 6 6 6 6 18 To PWSCC-Pressurizer UT Exam_ Note 3 Piping Butt Welds Subject R-A R1.20 MRP-139 MRP139D2 4 0 4 4 8 To PWSCC-RC Hot Leg Note 3 UT Exam _____Nt Piping Butt Welds Subject R-A Rl.20 MRP-139 MRP]39E 4 0 4 4 8 To PWSCC-RC Cold Leg N.

UT ExamNote 3 Piping Butt Welds Subject R-A R1.20 MRP-139 MRPI39J 10 10 10 10 30 To PWSCC-Pressurizer and RC k-A R.20 MRP-139 MRP]39 4 0 4 0 4 Hot Leg BMV Examn Piping Butt Welds Subject R-A 11l 20 MRP-139 MRP139K 4 0 4 0 4 To PWSCC-RC Cold Leg.

BMV Examn Note 1: hits Code Item Number is not includea in section Ai iyyb Eaition witn Zuuu Addenda, examination is required per ju(PKOu.D)ak0AZJtx1)

Note 2: Examination of Pressure Retaining Bolting is performed in accordance with Code Case N-652. See Notes 1-6 in Paragraph I for selection and scheduling criteria.

Note 3: Five dissimilar metal welds were selected under RI-ISI requirements. All of the welds subject to PWSCC have additional augmented examinations performed per MRP-139. The RI-ISI exam may be conducted at the same time as the MRP-139 exam.

Note 4: Examination of Reactor Vessel Shell-to-Flange and Head-to Flange welds are performed in accordance with Code Case N-623.

Note 5: These examinations are per NRC Order EA-03-009.

Note 6: See Section H for an explanation of Category R-A and Item RI.xx nomenclature.

WCRE-16 4.1.4-Reactor Coolant System (BB) Revision 0 Page 7 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL IS1 PROGRAM PLAN 4.1.4 Reactor Coolant (BB)

F. Augmented ISI Requirements The following Augmented ISI requirements apply to the Reactor Coolant System:

1. WCGS USAR Sections 3.6.1, Postulated Piping Failures In Fluid Systems Inside and Outside Containment and 3.6.2, Determinaticin Of Break Locations and Dynamic Effects Associated With The Postulated Rupture Of Piping- WCGS has implemented a Risk Informed-High Energy Line Break program as an alternative to the examination methodology of USNRC Branch Technical Position MEB 3-

1. This program is maintained in WCRE-1 4 and is applicable to the piping within the "no break zone" associated with high energy piping in containment penetration areas. The "no break zone" is an area where pipe breaks were not postulated due to the stress levels being within limits specified in USAR Section 3.6.2. The applicable welds are shown on the Reactor Coolant Steam Isometrics within the "No Break Zone". No BB system welds were selected for examination in the RI-HELB program.

2. USNRC RegulatoryGuide 1.14. Revision 1. Reactor Coolant Pump Flywheel Integrity-This Regulatory Guide includes inspection requirements for Reactor Coolant Pump flywheels in Section 4.

WCNOC has committed to these inspections per USAR Appendix 3Aand Technical Specification 5.5.7.

The Reactor Coolant Pump flywheel inspections are included in Table BB-3 with Category "USAR" and Item No. `RG 1.14" but may be performed at anytime during the inspection interval.

3. USNRC Reculatory Guide 1.65. Revision 0. Materials and lnspections for Reactor Vessel Closure Studs-This Regulatory Guide includes inspection requirements for the Reactor Vessel Closure Studs in Section 4. WCNOC has not committed to these inspections in USAR Appendix 3A; however, on page 3A-26, paragraph b. discusses the inservice inspection of the reactor vessel studs (as well as nuts and washers) performed per Section 5.2.4 of the USAR. Because Section 5.2.4 of the USAR specifically references the ASME Section XI ISI Program, the volumetric examination requirements for the reactor vessel studs in Code Case N-652 are understood to satisfy the WCNOC commitment to Regulatory Guide 1.65. These examinations arc included in Tables BB-1, BB-2, and BB-3, see the listings for Category B-G-l Item Number B6.20.

4. USNRC Regulatory Guide 1.150. Revision I. Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations -This Regulatory Guide includes inspection requirements for the ultrasonic examination of Reactor Vessel Welds during Preservice and Inservice Examinations. WCNOC has committed to these inspections per USAR Appendix 3A and Section 5.2.4.

5. MRP-139. Final Version dated July 14.2005 Material Reliability Program:Primarv System Piping Butt Weld Inspection and Evaluation Guideline-This document provides inspection and evaluation guidelines for butt weld locations susceptible to primary water stress corrosion cracking (PWSCC). The WCGS Reactor Coolant System butt weld locations determined to be affected by PWSCC have been identified with Category = MRP-139 and ltemNumber MRP139DI (Pressurizer), Item Number MRP139D2 (RC Hot Leg welds) and Category - MRP-139 and Item Number MRP139E (RC Cold Leg welds). The Item Number MRP-139D welds (Category D per MRP-139) require a volumetric examination every five years for hot legs and once per period for pressurizer, as well as a bare metal visual (BMV) examination in outages when a volumetric examination is not being performed. The I3MV examination has been identified with Category =MRP-139 and Item Number MRP 139J. The Item Number MRP-139E welds (Category E per MRP-139) require a volumetric examination every six years for cold legs, as well as a bare metal visual (BMV) examination once every 3 RFOs (not counting RFOs when the weld is examined volumetrically as one of the three). The BMV examination has been identified with Category MRP-139 and Item Number MRP139K.

6. NRC Order EA-03-009-The NRC issued Order EA-03-009 to mandate inspections of the RPV head.

Each refueling outage, visual inspections are performed to identify potential boric acid leaks from pressure retaining components above the RPV head. These inspections are performed under Wolf Creek's Boric Acid Corrosion Inspection (BACINS) Program. This NRC Order also requires a Bare Metal Visual (BMV) of 100% of the RPV head surface and NDE of each RPV head penetration nozzle on a specified frequency. In order to track these examinations, this requirement has been included in the IS Database as a Category B-E, Item No. B4.12 augmented examination (Category EA-03-009, and Item Nos. EA OO9UT and EA-03-009BMV). Note that Category B-E, Item Nos. B4.II and B4.12 have been eliminated WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 8 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN A from ASME Section Xl, 1998 Edition with 2000 Addenda; so the Section Xl requirements are no longer C applicable and Section Xi examinations will not be scheduled. The applicable welds and surfaces are listed in Tables BB-l, BB-2, and BB3-3 with Note 15.

G.

G System Pressure Testing In accordance with Section XI, IWA-5000 and IWB-5000, the Class I pressure retaining components within the Reactor Coolant System will receive a system leakage test per IWB-5220 prior to plant startup following each refueling outage.

In accordance with Section Xl, IWA-5000 and IWC-S000, the Class 2 pressure retaining components within the Reactor Coolant System will receive a system leakage test per IWC-5220 each inspection period.

[I Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI A Risk Informed Inservice Inspection (RI-1SI) Program has been applied to Code Class I and 2 piping welds at WCGS. This program is described in detail in Section 23. Reactor Coolant System welds selected for examination per the RI-ISI program are listed in Tables BB-l, BB-2 and BB-3. Since the EPRJ methodology used for the RI-ISI Program does not prescribe Code Examination Category and Item Numbers, guidance was taken from Code Case N-578-1 for the assignment of these designators.

When a specific degradation mechanism (DM) exists at a selected location, then the volume to be examined shall be as recommended in Section 4 of EPRI TR- 12657 Rev. B-A. Welds subject to a DM are identified by a note in the Table. Welds selected that have no associated DM shall have the volume examined as shown in Figures 4.1-4 of TR-1 12657 Rev. B-A.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table BB-I (Period I Examinations), Tab'e BB-2 (Period 2 Examinations), and Table BB-3 (Period 3 Examinations). The following Note:; apply to the tables:

1. Bolting is required to be examined only when a connection is disassembled or bolting is removed. The examination of flange bolting in piping systems may be limited to one bolted connection among a group of bolted connections that are similar in design, size, function, and service. Examination of bolted connection is required only once du:ring the interval. See Code Case N-652, B-G-2, Notes I and 3.

2. Bolting is required to be examined only when a connection is disassembled or bolting is removed. For valves, examination of bolting is required only when the component is examined under Examination Category B-M-2. Examination of bolted connection is required only once during the interval.

See Code Case N-652, Category B-G-2, Notes I and 2.

3. Examination may be alternatively performed on the bolts or studs in pump PBBOI B, PBBOI C, or PBBO ID. See Code Case N-652, Category B-G-I, Note 4.

4. Examination of the pump flange will be performed when connection is disassembled for maintenance.

Examination may be alternatively performed on the pump flange of PBBO1B, PBBOIC, or PBBOI D. See Code Case N-652, Category B-G-I, Notes 4 and 5.

5. Examination of the pump nuts, bushings and washers may be alternatively performed on the pump nuts, bushings and washers of PBBOIB, F'BBOIC, or PBBOID. See Code Case N-652, Category B-G-I, Notes 4 and 5.

6. Examination of the steam generator hotleg and coldleg manway bolting may be alternatively performed on the bolting of EBBOIA, EBBOIE, or EBBOID. See Code Case N-652, Category B-G-1, Notes 4 and 5.

WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 9 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN

7. Examination of the pump internal surface is required only when a pump is disassembled for maintenance, repair, or volumetric examination. Examination will be performed only once during the inspection interval and is limited to one pump within a group of pumps which performs a similar function in the system. Examination may be alternatively performed on another pump within the group.

Examination is deferrable to the end of the interval, thus may be performed anytime during the interval.

8. Examination of the valve internal surface is required only when a valve is disassembled for maintenance, repair, or volumetric examination. To aide in scheduling, the valve has been included in each inspection period. However, examination will be performed only once during the inspection interval and is limited to one valve within a group of valves that are the same size, constructional design, and manufacturing methods and which performs a similar function in the system. Examination may be alternatively performed on another valve within the group. If a valve has not been disassembled, examination is deferrable to subsequent periods. (Reference PIR 97-2539)

9. Reactor Coolant Pump motor flywheel examinations are prescribed by Technical Specification 5.5.7.

Technical Specification 5.5.7 requires that each flywheel be inspected in accordance with Regulatory Position C.4.b(2) of Regulatory Guide 1.14 and/or the specified exceptions approved through Amendment 106 of the Technical Specifications. One of the following examinations shall be completed on each flywheel at an interval not to exceed 20 years: 1) a qualified in-place UT examination over the volume from the inner bore of the flywheel tD the circle of one-half the outer radius, or 2) a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel. It is intended that the flywheels be examined during motor refurbishment, which generally occurs at 12-14 year intervals. It is not allowable for the frequency of examination of 5 flywheel to exceed 20 years.

• Failure to examine all flywheels within the First 10-Year Inservice Inspection Interval resulted in an NRC Violation

10. Steam Generator (SG) Tubing, Category B-Q, Item B 16.20, is examined in accordance with the WCNOC Technical Specifications. The examination acceptance criteria is governed by the Technical Specifications. Administrative Procedure AP 29A-003, "Steam Gencrator Management," provides details of SG tubing inspection activities.

11. The 4 Pressurizer Seismic Supports (Code Item FA.40 of Category F-A) and 4 integral attachment Lugs (Code Item B 10.10 of Category B-K) are considered single components (i.e., the four lugs make up one component). Each support and lug is listed in the ISI Database with unique component names and descriptions for traceability purposes. In addition, IOCFR50.55a Request For Alternatives 13R-02 has been submitted to the NRC. 13R-02 requests approval to utilize the alternative requirements of Code Case N-700, which would allow WCNOC to eliminate the examination of the seismic lugs, currently scheduled for Period 3. Until the alternative requirements of 13R-02 are authorized for use by the NRC, the Period 3 scheduling of the lug examination will remain in this ISI Program Plan.

12. These welds have been selected per the RI-ISI Program. The requirements for examination of these welds are included in Paragraph H above.

13. These welds have Thermal Fatigue identified as the degradation mechanism.

14. These welds have been selected in accordance with the Augmented ISI requirements of MRP-I 39.

15. These surfaces and welds have been selected in accordance with the Augmented ISI requirements of NRC Order EA-03-009. These examinations shall utilize approved calibration blocks as required by the demonstrated procedure.

16. An enhanced VT-I examination may be performed in lieu of the UT examination per I OCFRSO.55a(bX)(2Xxxi)(A).

17. Examination of the Reactor Nozzle-to-Vessel welds is performed in accordance with Code Case N-613-1, which allows an alternative examination volume to be utilized.

WCRE-1 6 4.1.4 Reactor Coolant System (BB) Revision 0 Page IO of 41

I WOLF CREEK GENERATING STATION M THIRD INTERVAL ISI PROGRAM PLAN A

G 18. Examination of the Reactor Nozzle-to-Vessel inner radius areaa is performed in accordance with Code E Case N-648-1, and the conditions specified in Revision 14 of Regulatory Guide 1.147.

0 19. These locations are subject to PIWSCC. This examination may be performed at the same time as the 1 MRPI 39 exam.

5

.0 WCRE-1 6 4.1.4 Reactor Coolant System (BB) Revision 0 Page IIof41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB- 1 period I ExaminationsIl ISystem: BB Relief Request or Component Narne Drawing Number Component Descrption Size Thickness NDE Method Category Item Cal Block Notes CH-101-104-A ISI-RBBO0 SHT. 1 RVCLOSUREHEADMERIDIONALWELD NA 8.25 UT B-A B1.22 177 TBBO3-CIRCUM-5-W ISI-TBB03 SHT. 1 BOTTOM HEAD TO SHELL WELD NA 8.25 UT B-B B2.11 101 TBB03-10B-A-W ISI-TBB03 SHT. 1 SAFETY NOZZLE A TO TOP HEAD WELD NA 1.90 UT B-D B3.110 101 TBI03-1OB-B-W ISI-TBB03 SHT. 1 SAFETY NOZZLE B TO TOP HEAD WELD NA 1.90 UT B-D B3.110 101 T8B03-10B-A-IR ISI-TBB03 SHT. 1 SAFETY NOZZLE A INNER RADIUS NA 1.90 UT B-D B3.120 101 16

• e1 ronnn oEr

• e aters n-n, a- n~,~

• ta_ a..- -

TEB03-10B-m-!R *..a* a.b4, _*

%J* .

• vr-l t* S *l JL Ur u S; flcf nnvUUO NA 1.90 UT B-D B3.120 10i 16 EBB0IC-1-B-IR ISI-EBBOIC SHT. I PRIMARY OUTLET NOZZLE INNER RADIUS NA 5.00 UT B-D B3.140 104 16 EBBO1D-1-A-IR ISI-EB8OID SHT. I PRIMARY INLET NOZZLE INNER RADIUS NA 5.00 UT B-D B3.140 104 16 EBBOI D-1-B-IR ISI-EBBOID SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS NA 5.00 UT B-D B3.140 104 16 CH-107-101 ISI-RBB01 SHT. I RV VENT PENETRATION NA NA UTIBMV B-E B4.11 15 CH-1 12-201 ISI-RBBO1 SHT. 1 RV CRDM PENETRATION 1 NA NA UT/BMV B-E 84.12 15 CH-112-202-2 ISI-RBBO1 SHT. 1 RV CRDM PENETRATION 2 NA NA UTIBMV B-E B4.12 15 CH-I 12.202.3 ISI-RBB01 SHT. I RV CRDM PENETRATION 3 NA NA UTI8MV B-E B4.12 15 CH-I 12-2024 ISI-RBBOI SHT. I RV CRDM PENETRATION 4 NA NA UTIBMV B-E B4.12 15 CH-I 12-202-5 ISI-RBBOI SHT. I RV CRDM PENETRATION 5 NA NA UTIBMV B-E B4.12 15 CH-112-203-6 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 6 NA NA UT/BMV B-E B4.12 15 CH-112-203-7 ISI-RBBOI SHT. I RV CRDM PENETRATION 7 NA NA UT/BMV B-E B4.12 15 CH.1 12-203-8 ISI-RBB01 SHT. I RV CRDM PENETRATION 8 NA NA UT/BMV B-E B4.12 15 CH-I 12-203-9 ISI-RBBO1 SHT. 1 RV CRDM PENETRATION 9 NA NA UTIBMV B-E B4.12 15 CH-112-204-10 ISI-RBBOI SHT. I RV CRDM PENETRATION 10 NA NA UT/BMV B-E B4.12 15 CH-112-204-11 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 11 NA NA UT/BMV B-E B4.12 15 CH-1 12-204-12 ISI-RBB01 SHT. 1 RVCRDM PENETRATION 12 NA NA UT/BMV B-E B4.12 15 CH-112-204-13 ISI-RBB01 SHT. I RVCRDM PENETRATION 13 NA NA UT/IMV B-E B4.12 15 CH-I 12-205-14 ISI-RBBO1 SHT. I RV CRDM PENETRATION 14 NA NA UT/BMV B-E B4.12 15 CH-1 12-205-15 ISI-RBB01 SHT. I RV CRDM PENETRATION 15 NA NA UTIBMV B-E B4.12 15 CH-1 12-205-16 ISI-RBBOI SHT. I RV CROM PENETRATION 16 NA NA UT/BMV B-E B4.12 15 CH-112-205-17 ISI-RBBOI SmT. 1 RV CRDM PENETRATION 17 NA NA UT/BMV B-E B4.12 15 CH-112-206-18 ISI-RBB01 SmT. 1 RV CRDM PENETRATION 18 NA NA UTIBMV B-E B4.12 15 CH-112-206-19 ISI-RBBO1 SHT. I RV CRDM PENETRATION 19 NA NA UTIBMV B-E B4.12 15 CH-I 12-206-20 ISI-RBB01 SmT.1 RV CRDM PENETRATION 20 NA NA UT/BMV B-E 84.12 15 CH-I 12-206-21 ISI-RBB01 SHT. I RV CRDM PENETRATION 21 NA NA UT/BMV B-E B4.12 15 WCRE-16 .4 Reactor Coolant System (BB) Revision 0 Page 12of41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB-1 r~eriod IExaminationslI Relief Request or Component Name Drawing Number Component Description Size Thidtness NDE Method Category Item Cal Block Notes CH.1 12-207-22 ISI-RBB01 SHT. I RV CRDM PENETRATION 22 NA NA UT/BMV B-E B4.12 15 CH-112-207-23 ISI-RBBOI SHT.1 RV CRDM PENETRATION 23 NA NA UTtBMV B-E B4.12 15 CH-1 12-207-24 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 24 NA NA UTtBMV B-E B4.12 15 CH-112-207-25 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 25 NA NA UTIBMV B-E. B4.12 15 CH-1 12-207-26 ISI-RBB01 SHT. 1 RV CROM PENETRATION 26 NA NA UT/BMV B-E B4.12 15 CH-1 12-207-27 ISI-RBB01 SHT. I RV CRDM PENETRATION 27 NA NA UT/BMV B-E B4.12 15 CH-1 12-207-28 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 28 NA NA UT/BMV B-E B4.12 15 CH-1 12-207-29 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 29 NA NA UTtBMV B-E B4.12 15 CH-1 12-208-30 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 30 NA NA UT8BMV B-E B4.12 15 CH-1 12-208-31 ISI-RBB01 SHT. I RV CRDM PENETRATION 31 NA NA LJUTBMV 8-E B4.12 15 CH.1 12-208-32 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 32 NA NA UTIBMV B-E B4.12 15 CH-1 12-208-33 !S!-RE!2jO1 5.,T 4 PsV CRnD Iv AcINE IRTION 33 NA NA UTIBMV B-E B,4.12 15 CH-1i12-208-34 ISI-RBB01 SHT. I RV CRDM PENETRATION 34 NA NA UTtBMV B-E B4.12 15 CH-112-208-35 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 35 NA NA UTIBMV B-E 8B4.12 15 CH-1 12-208-36 ISI-RBB01 SHT. I RV CRDM PENETRATION 36 NA NA UTtBMV B-E 84.12 15 CH-1 12-208-37 ISI-RBB01 SHT. i RV CRDM PENETRATION 37 NA NA UTIBMV B-E B4.12 15 CH-112-209-38 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 38 NA NA UTtBMV B-E 64.12 15 CH-112-209-39 ISI-RBB01 SHT. I RV CRDM PENETRATION 39 NA NA UTtBMV B-E B4.12 15 CH-I 12-209-40 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 40 NA NA UT/BMV 8-E B4.12 15 CH-1 12-209-41 ISt-RBB01 SHT. 1 RV CRDM PENETRATION 41 NA NA UTIBMV B-E B4.12 15 CH-1 12-210-42 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 42 NA NA UTtBMV B-E B4.12 15 CH-112-210-43 ISI-RBB01 SHT. I RV CRDM PENETRATION 43 NA NA UT/BMV B-E B4.12 15 CH-1 12-210-44 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 44 NA NA UTtBMV B-E 84.12 15 CHR1-12-210-45 ISI-R8801 SHT. 1 RV CRDM PENETRATION 45 NA NA UTIBMV B-E B4.12 15 CH-112-210-46 ISI-RBB01 SHT.1 RV CRDM PENETRATION 46 NA NA UTIBMV B-E B4.12 15 CH-i 12-210-47 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 47 NA NA UTIBMV 6-E 84.12 15 CH-112-210-48 ISI-RBB01 SHT. I RV CRDM PENETRATION 48 NA NA UTIBMV B-E B4.12 15 CH-112-210-49 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 49 NA NA UTIBMV B-E 84.12 15 CH-1 12-211-50 ISI-RBB01 SHT. I RV CRDM PENETRATION 50 NA NA UTIBMV B-E B4.12 15 CH-112-211-51 ISI-RBB01 SmT. I RV CROM PENETRATION 51 NA NA UT/BMV B-E B4.12 15 CH-1 12-211-52 ISI-RBBD1 SHT. 1 RV CRDM PENETRATION 52 NA NA UTtBMV B-E B4.12 15 CH-1 12-211-53 ISI-RBB01 SHT. I RV CRDM PENETRATION 53 NA NA UT/BMV B-E 84.12 15 CH-I 12-212-54 ISI-RBBI01 SHT. 1 RV CRDM PENETRATION 54 NA NA UTtBMV B-E B4.12 15 CH-i 12-212-55 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 55 NA NA UTtBMV B-E 84.12 15 CH-1 12-212-56 ISl-RBB01 SHT. 1 RV CRDM PENETRATION 56 NA NA UTtBMV B-E B4.12 15 CH-1 12-212-57 ISI-RBB01 SHT. 1 RV CROM PENETRATION 57 NA NA UTtBMV B-E B4.12 15 CH-1 12-212-58 ISI-ROB01 SHT. I RV CRDM PENETRATION 58 NA NA UTIBMV B-E B4.12 15 CH-I 12-212-59 ISI-RBB01 SHT. I RV CRDM PENETRATION 59 NA NA UTtBMV B-E 84.12 15 CH-1112-212-60 ISI-RBB01 SHT. i RV CRDM PENETRATION 60 NA NA UTIBMV B-E 84.12 15 CH-112-212-61 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 61 NA NA UTIBMV B-E 64.12 15 CH-1 12-213-42 ISI-RBB01 SHT. I RV CRDM PENETRATION 62 NA NA UT/BMV B-E B4.12 15 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 13 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL IS PROGRAM PLAN TABLE BB-t Penod I Examinations I I Systern: BB rF-Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes CH-1 12-213-63 ISI-RBBOI SHT. I RV CRDM PENETRATION 63 NA NA UT/BMV B-E B4.12 15 CH-112-213-64 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 64 NA NA UTIBMV B-E B4.12 15 CH-I 12-213-65 ISI-RBBO1 SHT. I RV CRDM PENETRATION 65 NA NA UTIBMV B-E B4.12 15 CH-1 12-214-66 ISI-RBBO1 SHT. 1 RV CRDM PENETRATION 66 NA NA UT/BMV B-E B4.12 15 CH-1 12-214-67 ISI-RB9O1 SHT. I RV CRDM PENETRATION 67 NA NA UT/BMV B-E B4.12 i5 CH-i 12-214-68 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 68 NA NA UTIBMV B-E B4.12 15 CH-I 12-214-69 ISI-RB801 SHT. I RV CRDM PENETRATION 69 NA NA UTIBMV B-E B4.12 15 CH-I 12-214.70 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 70 NA NA UT/BMV B-E B4.12 15 CH-1 12-214-71 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 71 NA NA UTIBMV B-E B4.12 15 CH-1 12-214-72 ISI-R8801 SHT. 1 RV CRDM PENETRATION 72 NA NA UTIBMV B-E 84.12 15 CH-I 12-214-73 ISI-RBBOI SHT. I RV CRDM PENETRATION 73 NA NA UT/BMV B-E B4.12 15 CH-i i2-215474 iSI-RBBOI SHT. 1 RV CRDM PENETRATION 74 NA NA UTIBMV B-E B4.12 15 CH.1 12-215-75 ISI-RBBO1 SHT. I RV CRDM PENETRATION 75 NA NA UT/BMV B-E 84.12 15 CH-1 12-215-76 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 76 NA NA UT/BMV B-E B4.12 15 CH-1 12-215-77 ISI-RB801 SHT. 1 RV CRDM PENETRATION 77 NA NA UTIBMV B-E B4.12 15 CH-112-215-78 ISN-RBBO1 SHT. I RV CRDM PENETRATION 78 NA NA UTIBMV B-E 84.12 15 CH-NUT-01 ISI-RBBOI SHT. 1 REACTOR VESSEL NUT I Vr-I B-G-1 B6.10 CH-NUT-02 ISI-RBBO0 SHT. 1 REACTOR VESSEL NUT 2 VT-I BG-1 B6.10 CH-NUT-03 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 3 VT-I B-G-I B6.10 CH-NUT-04 ISI-RBBO0 SHT. I REACTOR VESSEL NUT 4 VT-1 B-G-I 86.10 CH-NUT-05 ISI-RBBOI SHT. 1 REACTOR VESSEL NUT 4 B--1 B6.10 CH-NUT-06 ISI-RBBO1 SHT. 1 REACTOR VESSEL NUT 6 VT-I BC1 B6.10 CH-NUT-07 ISI-RBBOI SHT. 1 REACTOR VESSEL NUT 7 VT-I B-G-1 B6.10 CH-NUT-08 ISI-RBBOI SHT. 1 REACTOR VESSEL NUT 7 V'T-I B--1 B6.10 CH-NUT-09 ISI.RBBOI SHT. 1 REACTOR VESSEL NUT 9 VT-i B-G-1 86.10 CH-NUT-10 ISI-RBBOI SHT. 1 REACTOR VESSEL NUT 10 V'T-i B-01 B6.10 CH-NUT-I 1 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT II VT-I B4--1 B6.10 CH-NUT-12 ISI-RBB01 SHT. I REACTOR VESSEL NUT 12 V'T-i B-C-I B6.10 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 14 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL 11SI PROGRAM PLAN TABLE BB 1 period 1 Examinations lSystem: 8B r Relief Request or Comnponent Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes CH-NUT-1 3 ISI-RBBO1 SHT.1 REACTORVESSELNUT 13 VT-1 B--C1 B6.10 CH-NUT-14 ISI-RBBO1 SHT. 1 REACTOR VESSEL NUT 14 VT-1 B8G-1 86.10 CH-NUJT-1 5 ISI-RBB01 SHT. I REACTOR VESSEL NUT 15 VT-1 B-G 1 B6.10 CH-NUT-16 ISI-R8B01 SHT. 1 REACTOR VESSEL NUT 16 VT-i BG-1 86.10 CH-NUT-1 7 ISI-RBBOI SHT. 1 REACTOR VESSEL NUT 17 VT-1 B-G-1 B6.10 CH--NUT-i8 ISI-RBBO SHT. I REACTOR VESSEL NUT 18 VT-I B-G-I B6.10 CH-STUD-01 15-RBBO1 SHT. I REACTOR VESSELSTUD I NA NA UT B-G.1 86.20 195 CH-STUD-02 ISI-RBBOI SHT. I REACTOR VESSEL STUD 2 NA NA UT 8-6-1 B6.20 195 CH-STD.03 ISI-RBBOI SHT. 1 REACTOR VESSEL STUD 3 NA NA UT B8G01 B6.20 195 CH-STUD-04 ISI-RBBO1 SHT. I REACTOR VESSEL STUD 4 NA NA UT B-G-1 B6.20 195 CH-STUD-05 ISI-RBBO1 SHT. I REACTOR VESSEL STUD 5 NA NA UT BG-1 B6.20 195 CFI-STUD-06 ISI-RBBO1 SHT. 1 REACTOR VESSEL STUD 6 NA NA UT B-G- 86.20 195 CH-STUD-07 ISl-RBBO1 SHT. 1 REACTOR VESSEL STUD 7 NA NA UT B-6-1 86.20 195 CH-STUD.08 ISI-RBBOI SHT. I REACTOR VESSEL STUD 8 NA NA UT BG-1 86.20 195 CH-STUD-09 ISI.RBB01 SHT. 1 REACTOR VESSEL STUD 9 NA NA UT B-GI 86.20 195 CH--STUD-1 ISI-RBBOI SHT. 1 REACTOR VESSEL STUD 10 NA NA UT B-G-1 86.20 195 CH-STUD-11I ISI-RBBOI SHT. 1 REACTOR VESSEL STUD 11 NA NA UT BG-1 B6.20 195 CH-STUD-12 ISI-RBB01 SHT. I REACTOR VESSEL STUD 12 NA NA UT B-G-1 86.20 195 CH--STUD-13 ISI-RBBO1 SHT. I REACTOR VESSEL STUD 13 NA NA UT B-G-1 B6.20 195 .

CH-STUD-14 ISI-RBBO1 SHT. I REACTOR VESSEL STUD 14 NA NA UT B-G-1 86.20 195 CH-STUD-1 5 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 15 NA NA UT B-G-1 B6.20 195 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page ISof41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB.1 Period 1 Eyarinatons I System:r BB Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes CH-STUD-16 ISI-RBB01 SHT. I REACTOR VESSEL STUD 16 NA NA UT B-G-1 86.20 195 CH-STUD-17 ISI.RBB01 SHT. 1 REACTOR VESSEL STUD 17 NA NA UT B-G-1 B6.20 195 CH-STUD-18 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 18 NA NA UT B-G-1 B6.20 195 RV-LIG-01 ISI-RBBOI SHT. I REACTOR VESSEL THREAD IN FLANGE 1 NA NA UT B-G-1 B6.40 140 RV-LIG-02 ISI-RB801 SHT. I REACTOR VESSEL THREAD IN FLANGE 2 NA NA UT B-G-1 B6.40 140 RV-LIG-03 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 3 NA NA UT B-G-1 86.40 140 RV-LIG-04 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 4 NA NA UT B-G-1 B6.40 140 RV-LIG-05 ISI-RBB01 SIT. 1 REACTOR VESSELTHREAD IN FLANGE 5 NA NA UT B--1 86.40 140 RV-LIG-06 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 6 NA NA UT B-G-1 86.40 140 RV-LIG-07 ISI-RBB01 SHT. I REACTOR VESSEL THREAD IN FLANGE 7 NA NA UT BG-1 B6.40 140 RV-LIG408 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 8 NA NA UT B-G-1 B6.40 140 RV-LIG-09 ISI-RBB01 SHT. I REACTOR VESSEL THREAD IN FLANGE 9 NA NA UT 8-G-1 B6.40 140 RV-LIG-10 ISI-RBB01 SHT. I REACTOR VESSEL THREAD IN FLANGE 10 NA NA UT B-G-1 B6.40 140 RV-LIG-1 1 ISI-RBBO1 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 11 NA NA UT B--1 B6.40 140 RV-UGC12 ISI-RBB01 SHT. I REACTOR VESSEL THREAD IN FLANGE 12 NA NA UT B.G-1 B6.40 140 RV-UG-13 ISI-RBB01 SHT. I REACTOR VESSELTHREAD IN FLANGE 13 NA NA UT B-G-1 B6.40 140 RV-LIG-14 ISI-RBB01 SHT. I REACTOR VESSEL THREAD IN FLANGE 14 NA NA UT B-G-1 86.40 140 RV-LIG-15 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 15 NA NA UT B-G-1 86.40 140 RV-LIG-16 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 16 NA NA UT 8-G-1 B6.40 140 RV-LIG-17 ISI.RBB0i SHT. I REACTOR VESSEL THREAD IN FLANGE 17 NA NA UT B-G-1 86.40 140 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 16 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB 1 Period 1 Examinatbns I System: Be I Relief Request or Component Name DrwAgng Number Component Description Size Thikkness NDE Method Category Item Cal B104ck Notes RV-LIG-1 8 ISI-RBBOI SHTfl.1 REACTOR VESSEL THREAD IN FLANGE 18 NA NA UT B4--1 B6.40 140 CH-WASH-41 ISI-RBB01 SHT. 1 REACTOR VESSELWASHER AND BUSHING 1 VT-1 B-G-1 B6.50 CH-WASH-02 SI-RBB01 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 2 VT-1 B4--1 B6.50 CH-WASH-03 ISI-RBB0I SHT. 1 REACTOR VESSEL WASHER AND BUSHING 3 VT-I B-G-1 86.50 CH-WASH-04 ISI-RBBO1 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 4 VT-1 BG-11 B6.50 CH-WASH-05 ISI-RBB01 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 5 VT-1 B-G-1 B6.50 CH-WASH-06 ISI-RBB01 SHT. I REACTOR VESSEL WASHER AND BUSHING 6 VT-I B4--1 B6.50 CH-WASH-07 ISI-RBB0I SHT. 1 REACTOR VESSEL WASHER AND BUSHING 7 VT-1 B-G-1 B6.50 CH-WASH-8 ISI-RBB01 SHT. I REACTOR VESSEL WASHER AND BUSHING 8 VT-I B--1 B6.50 CH.WASH-09 ISI-RBB01 SHT. I REACTOR VESSEL WASHER AND BUSHING 9 VT-1 B B6.50 CH-WASH-10 ISI-RBB01 SHT. 1 REACTOR VESSELWASHER AND BUSHING 10 VT-I B4--1 B6.50 CH-WASH-1 1 ISI-RBB01 SHT. I REACTOR VESSELWASHER AND BUSHING 11 VT-i B-G-1 B6.50 CH-WASH-12 ISI-RBBOI SHT. I REACTOR VESSEL WASHER AND BUSHING 12 VT-1 B-C-1 B6.50 CH-WASH-13 ISI-RBB01 SHT. I REACTOR VESSELWASHER AND BUSHING 13 VT-1 B4-1 B6.50 CH-WASH-14 ISI-RBBO1 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 14 VT-I B4--1 B6.50 CH-WASH-15 ISI-RBB0I SHT. 1 REACTOR VESSEL WASHER AND BUSHING 15 VT-I B4--I B6.50 CH-WASH-16 ISI-RBBOI SHT. 1 REACTOR VESSEL WASHER AND BUSHING 16 VT-1 BG-1 B6.50 CH-WASH-1 7 ISI.RBB01 SHT. I REACTOR VESSEL WASHER AND BUSHING 17 VT-I B4-.1 86.50 CH-WASH-18 ISI-RBBOI SHT. 1 REACTOR VESSELWASHER AND BUSHING 18 VT-I B-G-1 B6.50 TBB03-1 OD-b ISI-TB803 SHT. 1 TBB03 MANWAY BOLTING VT-I BG-2 B7.20 BB-02-801 OC-FL-b BB-02-02 VALVE 8010C FLANGE BOLTING VT-I B-G-2 87.50 I WCRE-1 6 4.1.4 Reactor Coolant System (BB) Revision 0 Page 17of41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE B-1 renod 1Examinationsl Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes BB-02-8010C-b BB-02-02 VALVE 801 0C BONNET BOLTING VT-1 B-G-2 B7.70 2 T8B03-SKIRT-W ISI-TB803 SHT. 1 SUPPORT SKIRT INTEGRAL ATTACHMENT PT B-K B10.10 13R-02 BB-02-8010A-SURF BB-02-02 VALVE 8010A INTERNAL PRESSURE SURFACE VT-3 B-M-2 B12.50 8 RV-INTERIOR ISI-RBB01 SHT. 1 REACTOR VESSEL INTERIOR VT-3 B-N-I B13.10 CH-214-1 12-B ISI-RBB01 SHT. 1 PENETRATION 67 CRDM HOUSING WELD PT B-0 B14.10 CH-214-1 12-E ISI-RBB01 SIT. 1 PENETRATION 70 CRDM HOUSING WELD PT B-0 814.10 CH-214-1 12-G ISI-RBB01 SHT. I PENETRATION 72 CRDM HOUSING WELD PT B-0 B14.10 CH-215-112-B ISI-RBB01 SHT. 1 PENETRATION 75 CRDM HOUSING WELD PT B-0 B14.10 EBB01A-SEAM-3-W ISI-EBB01A SHT. 1 STUB BARREL TO SHELL SECTION A NA 3.0 UT C-A C1.10 102 EBBO1A-SEAM6-W ISI-EBB01A SHT. I TRANSITION CONE TO SHELL SECTION C NA 3.76 UT C-A C1.10 102 EBB01A-SEAM-2-W ISI-EBBOIA SHT. I TUBESHEETTO STUB BARREL NA 3.0 UT C-A C1.30 102 EBBO1A-1 1-W ISI-EBBOIA SHT. I FEEDWATER NOZZLE WELD NA 3.76 UTIMT C-B C2.21 102 EBB01A-1 1-IR ISI-EBB01A SHT. 1 FEEDWATER NOZZLE INNER RADIUS NA 3.76 UT C-B C2.22 102 BB-02-RO 1 BB-01-02 PIPING SUPPORT 6 VT-3 F-A F1.10 BB-02-R015 BB-01-02 PIPING SUPPORT 3 VT-3 F-A F1.10 BB-04-R009 BB-01-04 SHT. 1 PIPING SUPPORT 4 VT-3 F-A F1.10 BB-04-H009 BB-01-04 SIT. 2 PIPING SUPPORT 4 VT-3 F-A F1.10 BB-04-R033 BB-01-04 SHT. 2 PIPING SUPPORT 4 V1-3 F-A F1 .10 CRDMPL-SUP-1 M-717-0028 CRDM Upper Seismic Support VT-3 F-A F1.40 CRDMPL-SUP-2 M-717-0028 CRDM Upper Seismic Support VT-3 F-A F1.iO WCRE-16 4.1 A Reactor Coolant System (BB) Revision 0 Page 18 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB-1 Perlod I Examinations lISystem: B83 I Relief Request or Component Name Drawing Number Component Descripon Size Thidcness NDE Method Category Item Cal Block Notes EBBOIA-01 231 M-717-00002 SG A LOWER COLUMN SUPPORT VT-3 F-A F1.40 E8801A-05 231 M-71 7-0009 SG A LOWER LATERAL SUPPORT VT-3 F-A F1.40 PBBOIA-SUP-1 ISI-PUMPS RCP A TIE ROD SUPPORT VT-3 F-A F1.40 PBB01A-SUP-1A ISI-PUMPS RCP A COLUMN SUPPORT VT-3 F-A F1.40 RBB-01-01 ISI-RBB01 SHT. I RV SUPPORT PAD I VT-3 F-A F1.40 13R-04 T8803-SKIRT-W ISI-TBB03 SHT. I SUPPORT SKIRT SUPPORT VT-3 F-A F1.40 BB-01-F001 BB-05-01 14'NOZZLE ON 60-BCA-29"TO 14'PIPE 14 1.25 UT R-A R1.11 130 12 8842-F01 9 BB-01-02 3" PIPE TO VALVE PCV-456A 3 0.438 UT R-A R1.11 114 12. 13 BB-04-FW314 BB-01-04 SHT. 1 4- PIPE TO 4" ELBOW 4 0.531 UT R-A R1.1 1 114 12. 13 BB-02-FOGS BB-01-02 6" PIPE TO PRESS. RELIEF NOZZLE SAFE-END 6 0.719 UT R-A R1.20 117 12 BB-04-S007-B BB-01-04 SHT. 2 4" ELBOW TO 4' PIPE 4 0.531 UT R-A R1.20 114 12 BB-04-S007-D BB-01-04 SHT. 2 4" PIPE TO 4 ELBOW 4 0.531 UT R-A R1.20 114 12 BB-0-4-S007-E BB-01-04 SHT. 2 4 ELBOW TO 4" PIPE 4 0.531 UT R-A R1.20 114 12 BB FW308 88-01-08 2'PUP PIECE TO 2' PIPE 2 0.344 UT R-A R1.20 156 12 BB-08-FW309 BB41-08 2' PIPE TO 2-X2X3/4 TEE 2 0.344 UT R-A R1.20 156 12 BB-08-FW31 1 BB-01-08 2'X2X3/4- TEE TO 2 PIPE 2 0.344 UT R-A R1.20 156 12 BB-08-V-1 21-2 88-01-08 V121 TO 2 PUP PIECE 2 0.344 UT R-A R1.20 156 12 TBB03-03-A-W ISI-TBB03 SHT. I SAFETY NOZZLE TO SAFE-END WELD 6 1.42 UT R-A R1.20 170 12, 19 TBB03-01-W ISI-TBB03 SHT. 1 SURGE NOZZLE TO SAFE-END WELD 14 1.51 UT MRP-139 MRP-139D1 171 14 TBB03-01-W ISt-TBB03 SlT. 1 SURGE NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 19 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB-1 lPeriod I Examinatilons I I ystem: 8B r Relief Request or Component Name Drawing Number Component Desciption Size Thickness NDE Method Category Item Cal Block Notes TBB03-02-W ISI-TBB03 SHT. 1 SPRAY NOZZLE TO SAFE-END WELD 4 1.00 UT MRP-139 MRP-139D1 169 14 TB103-02-W ISI-TBB03 SHT. 1 SPRAY NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 TBB03-03-A-W ISI-TBB03 SHT. 1 SAFETY NOZZLE TO SAFE-END WELD 6 1.42 UT MRP-139 MRP.139D1 170 14 TBB03-03-A-W ISI-TBB03 SHT. 1 SAFETY NOZZLE TO SAFE-END WELD BMV MRP4 39 MRP-139J 14 TBB03-03-B-W ISI-TBB03 SHT. i SAFETY NOZZLE TO SAFE-END WELD 6 1.42 UT MRP-139 MRP-139D1 170 14 TBB03-03-B-W ISI-TBB03 SHT. 1 SAFETY NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 TBB03-03-C-W ISI-TBB03 SHT. 1 SAFETY NOZZLE TO SAFE-END WELD 6 1.42 UT MRP-139 MRP-139l1 170 14 TBB03403-C-W ISI-TBB03 SHT. 1 SAFETY NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 TBB03-04-W ISI-TBB03 SHT. 1 RELIEF NOZZLE TO SAFE-END WELD 6 1.42 UT MRP-139 MRP-139D1 170 14 TBB03-04-W ISI-TBB03 SHT. 1 RELIEF NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 RV-301-121-A ISI-RBB01 SIT. 1 LOOP #1 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 BMV MRP-139 MRP-139J 14 RV-301-121-B ISI-RBB01 SHT. 1 LOOP #2 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 BMV MRP-139 MRP-139J 14 RV-301-121-C ISI-RBB01 SHT. 1 LOOP #3 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 BMV MRP-139 MRP-139J 14 RV-301-121-D ISI-RBB01 SHT. I LOOP #4 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 BMV MRP-139 MRP-139J 14 WCRE-1I6 4.1.4 Reactor Coolant System (BB) Revision 0 Page 20 of 41

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WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB.2 redd Eaminaltto~nSI Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Categofy Item Cal Block Notes CH-101-104-B ISI-RBBOI SHT. 1 RVCLOSUREHEADMERIDIONALWELD NA 8.25 UT B-A 81.22 177 CH-101-104-C ISI-RBB01 SHT. 1 RV CLOSURE HEAD MERIDIONAL WELD NA 8.25 UT B-A 81.22 177 TBB03-CIRCUM-1-W ISI-TBB03 SHT. 1 SHELL TO UPPER HEAD WELD NA 1.90 UT B-B 82.11 101 TB803-SEAM4-W ISI-TBB03 SHT. 1 SHELL TO UPPER HEAD LONGITUDINAL WELD NA 1.90 UT B-B 82.12 101 TBB03-10B-C-W ISI-TBB03 SHT. 1 SAFETY NOZZLE C TO TOP HEAD WELD NA 1.90 UT B-D B3.110 101 TBB03-108.D-W ISI-TBB03 SHT. 1 RFltIEF N0771LEl To TOP HEAD WEI L M"A 1.90 llT B-D B3.4 10 4A TBB03-1 OB-C-IR ISI-TBB03 SHT. 1 SAFETY NOZZLE C INNER RADIUS NA 1.90 UT B-D B3.120 101 16 TBB03-10B-D-IR ISI-TBB03 SHT. I RELIEF NOZZLE D INNER RADIUS NA 1.90 UT B-D B3.120 101 16 EBBO C-1-A-IR ISI-EBBOIC SHT. 1 PRIMARY INLET NOZZLE INNER RADIUS NA 5.00 UT B-D B3.140 104 16 EBB01B-1-A-IR ISI-EBB01 B SHT. 1 PRIMARY INLET NOZZLE INNER RADIUS NA 5.00 UT B-D 83.140 104 16 EBBOB-1-8-IR ISI-EBBOIB SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS NA 5.00 UT B-D B3.140 104 16 CH-107-101 ISI-RBBO1 SHT. 1 RV VENT PENETRATION BMV B-E B4.12 15 CH-112-201 ISI-RBB0I SHT. I RV CRDM PENETRATION I BMV B-E B4.12 15 CH-1 12-202-2 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 2 BMV B-E B4.12 15 CH-1 12-202-3 ISI-RBB01 SHT. I RV CRDM PENETRATION 3 BMV 8-E B4.12 15 CH-1`12-2024 ISI-RBB01 SHT. I RV CROM PENETRATION 4 BMV B-E B4.12 15 CH-1 12-202-5 ISI-RBB01 SHT. I RV CRDM PENETRATION 5 BMV B-E 84.12 15 CH.1 12-203-6 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 6 BMV B-E B4.12 15 CH-1 12-203-7 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 7 BMV B-E B4.12 15 CH-1 12-203-8 ISI-RBBI0 SHT. 1 RV CRDM PENETRATION 8 BMV B-E B4.12 15 CH.1 12-203-9 ISI-RBBO1 SHT. I RV CRDM PENETRATION 9 8MV B-E B4.12 15 CH-1 12-204-10 ISI-RBBO1 SHT. 1 RV CRDM PENETRATION 10 BMV 8-E B4.12 15 CH-1 12-204.11 ISI-RBBOI SHT. I RV CRDM PENETRATION 11 BMV B-E B4.12 15 CH.1 12-204-12 ISI-RBB0I SHT. 1 RV CRDM PENETRATION 12 BMV B-E B4.12 15 CH-112-204-13 ISI-RBB01 SHT. I RV CRDM PENETRATION 13 BMV B-E 84.12 15 CH-1 12-205-14 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 14 BMV B-E 84.12 15 CH-1 12-205-15 ISI-RBB01 SHT. I RV CRDM PENETRATION 15 8MV B-E 84.12 15 CH-1 12-205-16 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 16 BMV B-E B4.12 15 CH-1 12-205-17 ISI-RBB01 SHT. 1 RVCRDM PENETRATION 17 BMV 8-E B4.12 15 CH-112-206-18 ISI-RBB0I SHT. 1 RV CROM PENETRATION 18 8MV B-E B4.12 15 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 21 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL lSI PROGRAM PLAN TABLE BB-2 r'eriod 2Examinationsl Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category item Cal Block Notes CH-1 12-206-19 ISIRBBO1 SHT. 1 RV CRDM PENETRATION 19 BMV B-E -8B4.12 15 CH-112-206-20 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 20 BMV B-E 84.12 15 CH-1 12-206-21 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 21 BMV B-E B4.12 15 CH-1 12-207-22 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 22 BMV B-E 84.12 15 CH-1 12-207-23 ISI-RBBD1 SHT.1 RV CRDM PENETRATION 23 BMV B-E 84.12 15 CH-1 12-207-24 ISI-RBB0i SHT. I RV CRDM PENETRATION 24 BMV B-E 84.12 15 CH-i 12-207-25 ISI-RBBO1 SHT. 1 RV CRDM PENETRATION 25 BMV 8-E B4.12 15 CH-1 12-207-26 ISIRBB01 SHT. 1 RV CRDM PENETRATION 26 BMV B-E 84.12 15 CH-1 12-207-27 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 27 BMV B-E 84.12 15 CH-1 12-207-28 ISI-RBB01 SmT. I RV CROM PENETRATION 28 BMV B-E B4.12 15 CH-1 12-207-29 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 29 BMV B-E B4.12 15 CH-1 12-208-30 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 30 ,M~vS  ;.12 15 CH-1 12-208-31 ISI-RB801 SHT. 1 RV CRDM G-E PENETRATION 31 B3MV B4.12 15 CH-1 12-208-32 ISI-RBB01 SHT. I RV CRDM PENETRATION B-E 32 BMV B-E 84.12 15 CH-1 12-208-33 ISI-RB801 SHT. I RV CRDM PENETRATION 33 BMV 84.12 15 CH-1 12-208-34 ISI-RBB01 SHT.1 RV CRDM PENETRATION 8-E 34 BMV B4.12 15 CH-1 12-208-35 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 35 B-E BMV B-E 84.12 15 CH-1 12-208-36 ISI-RBB01 SHT. I RV CRDM PENETRATION 36 BMV B4.12 15 CH-112-208-37 ISI.R8B01 SHT. 1 RV CRDM PENETRATION B-E 37 BMV B4.12 15 CH-1 12-209-38 ISI-R8801 SHT. 1 RV CRDM PENETRATION 38 B-E BMV B-E 84.12 15 CH-1 12-209-39 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 39 BMV 84.12 15 CH-1 12-209-40 ISI-RBB01 RV CRDM PENETRATION B-E SHT.1 40 BMV 84.12 15 CH-1 12-20941 B-E ISI-RBB01 SHT. 1 RV CRDM PENETRATION 41 BMW B-E B4.12 15 CH-1 12-210-42 ISI.RBB01 SHT. I RV CRDM PENETRATION 42 BMV B4.12 15 CH-1 12-21043 ISI-RB8I01 SHT. 1 RV CRDM PENETRATION B-E 43 BMV 84.12 15 CH-112-21W-44 ISI-RBB01 SHT. 1 RV CRDM PENETRATION B-E 44 BMV 84.12 15 CH-112-210-45 lSI-RBB01 SHT. 1 RV CRDM PENETRATION B-E 45 BMV 84.12 15 CH-1 12-21046 ISI-RBB0i RV CRDM B-E SHT. 1 PENETRATION 46 BMV B4.12 15 CH-112-210-47 ISI-RBBOi RV CRDM B-E SHT. 1 PENETRATION 47 BMV 84.12 15 CH.1 12-210-48 ISI-R8801 RV CRDM PENETRATION B-E SHT.1 48 BMV 84.12 15 CH-1 12-210W49 RV CRDM B-E ISI-RBB01 SHT.1 PENETRATION 49 BMV B4.12 15 CH-112-211 50 ISI-RBB01 SHT.1 RV CRDM PENETRATION 50 B-E BMV B4.12 15 CH-1 12-211-51 ISI-RBB01 RV CRDM PENETRATION B-E 84.12 SHT. I 51 BMV 15 CH-112-211-52 ISI-RBBOI SHT. I RV CRDM PENETRATION B-E 52 BMV 84.12 15 CH-112-211-53 RV CRDM PENETRATION B-E ISI-RBB01 SHT. 1 53 BMV B4.12 15 CH-112-212-54 ISI-RBB01 RV CRDM PENETRATION B-E SHT. I 54 BMV B4.12 15 CH-1 12-212-55 RV CRDM B-E ISl-RBB01 SHT. 1 PENETRATION 55 BMV B4.12 15 CH-1 12-212-56 RV CRDM PENETRATION 8-E.

ISI-RBB01 SW-. 1 56 8MV 84.12 15 CH-1 12-212-57 RV CRDM PENETRATION B-E ISI-R8B01 SHT. 1 57 8MV B-E B4.12 15 CH-112-212-58 ISI-R8801 SHT. 1 RV CRDM PENETRATION 58 BMV B4.12 15 CH-1 12-212-59 ISI-RBB01 RV CRDM PENETRATION B-E SHT. I 59 BMV B4.12 15 CH-i 12-212-60 RV CRDM B-E lSI-RBB01 SHT. 1 PENETRATION 60 BMV E4.12 15 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 22 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB-2 rerlo 2 Examinations i Systern: BB Relief Request or Component Name Drawing Number Component Description Sie Thickness NDE Method Categorn I11em Cal Block Notes CH-1 12-212-61 ISI-RBB01 SHT. 1 RV CRDM PENETRATlON 61 BMV B-E 84.12 15 CH-1 12-213-62 ISI-RBBOI SHT. I RV CRDM PENETRATION 62 BMV B-E 84.12 15 CH-1 12-213-63 ISI-RBI01 SHT. 1 RV CROM PENETRATION 63 BMV B-E 84.12 15 CH-1 12-213-64 ISI-RB801 SHT. 1 RV CRDM PENETRATION 64 BMV B-E B4.12 15 CH-1 12-213-65 ISI-RBB01 SHT. I RV CRDM PENETRATION 65 BMV B4.12 15 CH-1 12-21446 ISI-RBB01 SHT. I RV CRDM PENETRATION 66 BMV 8-E B-E B4.12 15 CH-112-214-67 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 67 BMV B4.12 15 CH-1 12-214-68 ISI-RBB01 SHT. I RV CRDM BMV B-E PENETRATION 68 B-E B4.12 15 CH-112-214-69 ISI-RBB01 SHT. I RV CRDM PENETRATION 69 BMV B4.12 15 CH-112-214-70 ISI-RBBO1 SHT. I RV CRDM PENETRATION 70 BMV B-E B-E B4.12 15 CH-112-214-71 ISI-R8B01 SHT. I RV CRDM PENETRATION 71 BMV B4.12 15 CH-1 12-214-72 ISI-RBB01 SHT. 1 RV CRDM BMV B-E PENETRATION 72 A.12 15 iSi-RBiw1 SHT. i RV CRDM PENETRATION BMV 8-E 1- I I CH. -2 I 4wE3 73 B-E B4.12 15 CH-112-215-74 ISI-RBB01 SHT. I RV CRDM PENETRATION 74 BMV B4.12 15 CH-1 12-215-75 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 75 BMV B-E B-E B4.12 15 CH-112-215-76 ISI-RBB01 SHT. I RV CRDM PENETRATION 76 BMV B4.12 15 CH-112-215-77 ISI-RBB01 SHT. i RV CRDM BMV B-E PENETRATION 77 13-E B4.12 15 CH-112-215-78 ISI-RB801 SHT. 1 RV CRDM PENETRATION 78 BMV B4.12 15 CH-NUT-19 ISI-RBB01 SHT. I REACTOR VESSEL NUT 19 VT-I B-G-1 B6.10 CH-NUT-20 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 20 VT-1 B-G-1 86.10 CH-NUT-21 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 21 VT-1 B-G-1 86.10 CH-NUT-22 ISI-RBB01 SHT. I REACTOR VESSEL NUT 22 VT-M B-G-1 B6.10 CH-NUT-23 ISI-R8801 SHT. 1 REACTOR VESSEL NUT 23 VT-I B6.10 B-G-1 CH-NUT-24 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 24 VT-I B6.10 B-G-1 CH-NUT-25 ISI-RBB01 SHT. I REACTOR VESSEL NUT 25 VT-I B6.10 B-G-1 CH-NUT-26 ISI-R8801 SHT. I REACTOR VESSEL NUT 26 VT-1 86.10 CH-NUT-27 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 27 VT-1 8-0-11 B6.10 CH-NUT-28 ISI-RBB0I SHT. 1 REACTOR VESSEL NUT 28 VT-1 B6.10 VT-1 CH-NUT-29 ISI-RBB01 SHT. i REACTOR VESSEL NUT 29 VT-1 B-0-1 86.10 CH-NUT-30 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 30 B-G-11 B6.10 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 23 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL IS1 PROGRAM PLAN TABLE BB- 2 rerod 2 Examinations I l System: BBl Relief Request or Component Name Drawing Number Component Description Size Thidcness NDE Method Category Item Cal Block Notes CH-NUT-31 ISI-RBB01 SHT. t REACTOR VESSEL NUT 31 VT-1 B-G-1 B6.10 CH-NUT-32 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 32 VT-1 B-G-1 B6.10 CH-NUT-33 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 33 VT-1 86.10 B-G-1 CH-NUT-34 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 34 VT-1 B-C-i B6.10 B-G-1 CH-NUT-35 ISI-RBBO1 SHT. 1 REACTOR VESSEL NUT 35 VT-1 B-C-I B6.10 VT-I CH-NUT-36 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 36 06.10 CH-STUD-19 ISI-RBB01 SHT. 1 REACTOR VESSELSTUD 19 NA NA UT B-G-1 B6.20 195 B-C-i CH-STUD-20 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 20 NA NA UT B6.20 195 B-G-1 CH-STUD-21 ISI-RBBO1 SHT. I REACTOR VESSEL STUD 21 NA NA UT 86.20 195 CH-STUD-22 ISl-RBB01 SHT. I REACTOR VESSEL STUD 22 NA NA UT 86.20 195 B-G-i CH-STUD-23 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 23 NA NA UT B6.20 195 CH-STUD-24 ISI-RBB0i SHT. I REACTOR VESSEL STUD 24 NA NA UT B-G-1 B6.20 195 B-G-i CH-STUD-25 ISI-R8B01 SHT. 1 REACTOR VESSEL STUD 25 NA NA UT 86.20 195 B-C-1 CH-STUD-26 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 26 NA NA UT B-G1 B6.20 195 CH-STUD-27 ISI-RBB01 SHT. I REACTOR VESSEL STUD 27 NA NA UT B-&1 B6.20 195 CH-STUD-28 ISt-RBB01 SHT. I REACTOR VESSEL STUD 28 NA NA UT B6.20 195 CH-STUD-29 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 29 NA NA UT B-G-1 B6.20 195 CH-STUD-30 ISI-RBB01 SHT. I REACTOR VESSEL STUD 30 NA NA UT B-C-i B6.20 195 CH-STUD-31 ISI-RBB01 SHT. I REACTOR VESSEL STUD 31 NA NA UT B-G-1 B6.20 195 CH-STUD-32 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 32 NA NA UT B-&1 B6.20 195 CH-STUD-33 ISI-RBB01 SHT. I REACTOR VESSEL STUD 33 NA NA UT B-G- B6.20 195 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 24 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB-2 lPeriod 2 Examinationsl I System: BS I Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal BlocX Notes CH-STUD-34 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 34 NA NA UT B-G-1 B6.20 195 CH-STUD-35 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 35 NA NA UT B-G-1 86.20 195 CH-STUD-36 ISl-RBB01 SHT. 1 REACTOR VESSEL STUD 36 NA NA UT B-G-1 86.20 195 RV-LIG-19 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 19 NA NA UT B-G-1 B6.40 140 RV-LIG-20 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 20 NA NA UT B4--1 B6.40 140 RV-LIG.21 i!S!.B011 SHT. 1 REACTORVESSELTHREADtN FLA.NGE 21 ua uA _IT B-G-11 85.40 4 A0t RV-LIG-22 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 22 NA NA UT B-G-1 86.40 140 RV-LIG-23 ISI-R8B01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 23 NA NA UT B-G-1 B6.40 140 RV-LIG-24 ISI-RBB01 SHT. I REACTOR VESSEL THREAD IN FLANGE 24 NA NA UT B-G-1 B6.40 140 RV-LIG-25 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 25 NA NA UT *B--1 B6.40 140 RV-LIG-26 ISI-R8B01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 26 NA NA UT B-G-1 B6.40 140 RV-LIG-27 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 27 NA NA UT *B-G-1 B6.40 140 RV-LIG-28 ISI-RBB01 SHT. I REACTOR VESSEL THREAD IN FLANGE 28 NA NA Ur B-G-1 B6.40 140 RV-LIG-29 ISI-RBBO1 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 29 NA NA UT *BG-1 B6.40 140 RV-LIG-30 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 30 NA NA UT B-G-1 BS.40 140 RV-LIG-31 ISI-RBBO1 SHT. I REACTOR VESSEL THREAD IN FLANGE 31 NA NA UT *B--1 B6.40 140 RV-LIG-32 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 32 NA NA UT *BG1 B6.40 140 RV-IG-33 ISI-RBB01 SHT. I REACTOR VESSEL THREAD IN FLANGE 33 NA NA UT B-G-1 86.40 140 RV-LIG-34 ISI-RBB01 SHT. I REACTOR VESSEL THREAD IN FLANGE 34 NA NA UT B-G-11 B6.40 140 RV-LIG-35 ISI-RBBOI SHT. I REACTOR VESSEL THREAD IN FLANGE 35 NA NA UT B-G-1 B.40 140 RV-LIG-36 ISI-RBB01 SHT. I REACTOR VESSEL THREAD IN FLANGE 36 NA NA UT B-C-1 B6.40 140 WCRE-l 6 4.1.4 Reactor Coolant System (BB) Revision 0 Page 25 of 41

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WOLF CREEK GENERATING STATION THIRD INTERVAL IS[ PROGRAM PLAN TABLE BB2 Ferid 2 Examinations ISystem: BB I Relief Request or Component Name Drawing Number Component Description Sze Thickness NDE Method Category Item Cal Block Notes CH-WASH-1-9 ISI-RBB0i SHT. I REACTOR VESSEL WASHER AND BUSHING 19 VT-1 BG-1 B6.50 CH--WASH-20 ISI-RBB0I SHT. I REACTOR VESSEL WASHER AND BUSHING 20 B-G-1 B6.50 VT-1 CH-WASH-21 ISI-RBB01 SHT. I REACTOR VESSEL WASHER AND BUSHING 21 B--1 B6.50 VT-1 CH-WASH-22 ISI-RBBOI SHT. 1 REACTOR VESSEL WASHER AND BUSHING 22 B-G-1 B6.50 VT.1 CH-WASH-23 IS1-RBB01 SHT. I REACTOR VESSEL WASHER AND BUSHING 23 VT-1 B--1 86.50 CH-WASH-24 ISI-RBB01 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 24 VT-1 B4--1 B6.50 CH-WASH-25 ISI-RBB01 SHT. I REACTOR VESSELWASHER AND BUSHING 25 VT-1 B-G-1 B6.50 CH-WASH-26 ISI-RBB0I SHT. 1 REACTOR VESSEL WASHER AND BUSHING 26 BG-1 B6.50 CH--WASH-27 ISI-R8801 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 27 VT-1 B--1 B6.50 CH-WASH-28 ISI-RBB01 SHT. 1 REACTOR VESSELWASHER AND BUSHING 28 VT.1 BG-1 86.50 CH-WASH-29 ISI-RBB01 SHT. I REACTOR VESSELWASHER AND BUSHING 29 VT.1 B-G-1 B6.50 CH-WASH-30 ISI-RBB01 SHT. 1 REACTOR VESSELWASHER AND BUSHING 30 VT-1 B-G1 85.50 CH-WASH-31 ISI-RBB01 SHT. 1 REACTOR VESSELWASHER AND BUSHING 31 VT-1 BG-1 B6.50 CH-WASH-32 ISI-RBB01 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 32 VT-I B4--1 B6.50 CH--WASH-33 ISI-RBB01 SHT. 1 REACTOR VESSELWASHER AND BUSHING 33 VT.1 B-C-1 B6.50 CH.WASH.34 ISI-RBB01 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 34 VTr.1 VT-1 VT.1 B-G-1 B6.50 CH-WASH-35 ISI-RBB01 SHT. I REACTOR VESSELWASHER AND BUSHING 35 VT-1 B--1 B6.50 CH-WASH-36 ISI-RBB01 SHT. I REACTOR VESSEL WASHER AND BUSHING 36 B-G-1 B6.50 BB-07-FL1-b BB44407 1 It2FLANGE (RC PUMP Dj BOLTING 2 VT-1 B-C-2 B7.50 1 BB-02-8010A-SURF BB-02-02 VALVE 801 GA INTERNAL PRESSURE SURFACE VT-3 B-M-2 B12.50 8 WCRE-I16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 26 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB-2 Feriod 2 Examinations lISystem: BB l Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes RV-INTERIOR ISI-RBB01 SHT. I REACTOR VESSEL INTERIOR VT-3 B-N-1 B13.10 EBB01A-SEAM-5-W ISI-EBBOIA SHT. 1 SHELL SECTION B TO TRANSITION CONE NA 3.00 UT C-A C1.10 102 EBBOIA-SEAM-8-W ISI-EBBO0A SHT. 1 SHELL SECTION D TO TOP HEAD NA 3.95 UT C-A C1.20 102 BB-04-RD12 BB-01-04 SHT. 1 PIPING SUPPORT 4 VT.3 F-A F1.10 BB-04-R017 BB-01-04 SHT. 1 PIPING SUPPORT 6 Vr-3 F-A F1.10 BB-04-R021 BB41-04 SHT. 1 PIPING SUPPORT 4 VT-3 F-A F1.10 BB-04-C006 BB-01-04 SHT. 2 PIPING SUPPORT 4 VT-3 F-A FI.10 BB-04-CO10 BB-01-04 SHT. 2 PIPING SUPPORT 4 VT-3 F-A F1.10 BB-04-HOO1 BB-01-04 SHT. 2 PIPING SUPPORT 4 VT-3 F-A F1.10 BB-04-HOOS BB-01-04 SHT. 2 PIPING SUPPORT 4 VT*3 F-A F1.10 BB-02-H00i B8-02-02 PIPING SUPPORT 6 VT-3 F-A F1.10 BB-01-HOO0 8-05-01 PIPING SUPPORT 14 VT-3 F-A F1.10 HB-24-R015 BB-06-01 PIPING SUPPORT 2 VT-3 F-A F1.10 CRDMPL-SUP-3 M-717-0028 CRDM Upper Seismic Support VT-3 F-A F1.40 CRDMPL-SUP-4 M-717-0028 CRDM Upper Seismic Support VT-3 F-A F1.40 EBBO1A-02 231 M-717-00002 SG A LOWER COLUMN SUPPORT VT`3 F-A F1.40 EBBO1A-06 231 M-717-00009 SG A LOWER LATERAL SUPPORT VT-3 F-A F1.40 EBOIA-07 231 M-717-00009 SG A LOWER LATERAL SUPPORT VT-3 F-A F1.40 EBBO1A-08 231 M-717-00010 SG A UPPER LATERAL SUPPORT VT-3 F-A F1.40 EBBOIA-UP-2 M-717-00015 SG A UPPER LATERAL SUPPORT VT-3 F-A F1.40 EBBO1A-UP-3 M-717-00015 SG A UPPER LATERAL SUPPORT VT.3 F-A F1.40 WCRE-1 6 4.1.4 Reactor Coolant System (BB) Revision 0 Page 27 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB3-2 rerid 2Examhinations Relief Request or Component Name Drawing Number Component Desciption Size Thickness NDE Method Category Item Cal Block Notes PBB01A-SUP-2 ISI-PUMPS RCP A TIE ROD SUPPORT VT-3 F-A F1.40 P8B01A-SUP-2A ISI-PUMPS RCP A COLUMN SUPPORT VT-3 F-A F1.40 RBB-01-02 ISI-RBB01 SHT. 1 RV SUPPORT PAD 2 VT-3 F-A F1.40 13R-04 RBB-01-03 ISI-R8B01 SHT. 1 RVSUPPORTPAD3 VT-3 F-A F1.40 13R-04 BB-04-FW302 BB-01-04 SHT. I 4" ELBOW TO 4" PIPE 4 0.531 UT R-A RI.11 114 12. 13 BB-02-FW301 BB-02-02 6" 180 DEGREE RET. TO 6" FLANGE (VALVE 8010A) 6 0.719 UT R-A R1.11 117 12. 13 BB-1 -f002 BB-5-01 14" PIPE TO 14" PIPE 14 1.25 UT R-A R1.11 130 12.13 BB-01-SIO1 -13 BB-01 -01 3" NOZZLE TO 3" X 1.5" REDUCER 3 0.438 UT R-A R1.11 112 12,13 BB-01-S201-15 BB-02-01 3" NOZZLE TO 3" X 1.5" REDUCER 3 0.438 UT R-A R1.11 112 12,13 BB-01-F108 BB-01-01 31" ELBOW TO 31" PIPE 31 2.88 UT R-A R1.20 SAP-01. 105 12 BB-01-S105-04 BB-1-01 31" PIPE TO 31" ELBOW 31 2.88 UT R-A R1.20 SAP-01, 105 12 BB-04-F014 BB-01-04 SHT. 1 PCV-455C TO 4' PIPE 4 0.531 UT R-A R1.20 114 12 BB-04-SO1 5-B BB-01-04 SHT. 2 4" ELBOW TO 4" PIPE 4 0.531 UT R-A R1.20 114 12 BB-04-S015-D 88-01-04 SHT. 2 4" PIPE TO 4" ELBOW 4 0.531 UT R-A R1.20 114 12 BB-04-S015-E BB-01-04 SHT. 2 4- ELBOW TO 4" PIPE 4 0.531 UT R-A Ri .20 114 12 BB-02-FO01A BB-02-02 6" PIPE-PRESSURIZER SAFETY NOZZLE SAFE-END 6 0.719 UT R-A R1.20 117 12 TBB03-04-W ISI-TBB03 SHT. I RELIEF NOZZLE TO SAFE-END WELD 6 1.42 UT R-A R1.20 170 12, 19 RV-301-121 -A ISI-RBB01 SHT. 1 LOOP #1 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 UT MRP-139 MRP-1391D2 179 14 RV-301.121-A ISI-RBB01 SHT. I LOOP #1 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 BMV MRP-139 MRP-139.j 14 RV-301-1 21-B ISI-RBB01 SHT. 1 LOOP #2 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 UT MRP-139 MRP-1391D2 179 14 RV-301-121-8 ISI-RBB01 SHT. 1 LOOP #2 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 BMV MRP-139 MRP-1 39. j 14 RV-301-121 -C ISI-RBB01 SHT. 1 LOOP #3 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 UT MRP-139 MRP-1391D2 179 14 RV-301-121-C ISI-RBB01 SHT. 1 LOOP #3 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 BMV MRP-139 MRP-139J 14 WCRE-1 6 4.1.4 Reactor Coolant System (BB) Revision 0 Page 28 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB- 2 Period 2 Examinations ISystem: BS Rerief Request or Component Name Drawing Number Component Description Size Thidcness NDE Method Category Item Cal Block Notes RV-301-1221-D ISI-RBBI01 SHT. I LOOP #4 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 UT MRP-139 MRP-139D2 179 14 RV-301-121-D ISI-RBBOt SHT. I LOOP #4 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 BMV MRP-139 MRP-139J 14 RV-302-121-A ISI-RBB01 SHT. 1 SAFE-END TO LOOP #1 RPV INLET NOZZLE 27.5 2.79 UT MRP-139 MRP-139E 179 14 RV-302-121-A ISI-RBB01 SHT. 1 SAFE-END TO LOOP #1 RPV INLET NOZZLE 27.5 2.79 BMV MRP-139 MRP-139K 14 RV-302-121-B ISI-RBB01 SHT. 1 SAFE-END TO LOOP #2 RPV INLET NOZZLE 27.5 2.79 UT MRP-139 MRP-139E 179 14 RV-302-121-B ISI-RB801 SHT. I SAFE-END TO LOOP #2 RPV INLET NOZZLE 27.5 2.5 BMV MRP-139 MRP-139K 14 RV-302-121-C ISI-RBB01 SHT. 1 SAFE-END TO LOOP #3 RPV INLET NOZZLE 27.5 2.79 UT MRP-139 MRP-139E 179 14 RV-302-121-C ISI-RBB01 SHT. 1 SAFE-END TO LOOP #3 RPV INLET NOZZLE 27.5 2.79 BMV MRP-139 MRP-139K iA RV-302-121O-D ISI-RBBI01 SHT. 1 SAFE-END TO LOOP #4 RPV INLET NOZZLE 27.5 2.79 UT MRP-139 MRP-139E 179 14 RV-302-121-D ISI-RBB01 SHT. 1 SAFE-END TO LOOP #4 RPV INLET NOZZLE 27.5 2.79 BMV MRP-139 MRP-139K 14 TBB03-01-W ISI-TB803 SHT. 1 SURGE NOZZLE TO SAFE-END WELD 14 1.51 UT MRP-139 MRP-139D1 171 14 TBB03-01-W ISI-TBB03 SHT. 1 SURGE NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 TBB03-02-W ISI-TBB03 SHT. 1 SPRAY NOZZLE TO SAFE-END WELD 4 1.00 UT MRP-139 MRP-139D1 169 14 TBB03-02-W ISI-TBB03 SHIT. I SPRAY NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139-J 14 TBB03-03-A-W ISI-TBB03 SHT. I SAFETY NOZZLE TO SAFE-END WELD 6 1.42 UT MRP.139 MRP-139D1 170 14 TBB03-03-A-W ISI-TBB03 SHT. I SAFETY NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 TB803-03-B-W ISI-TBB03 SHT. I SAFETY NOZZLE TO SAFE-END WELD 6 1.42 UT MRP-139 MRP-139D1 170 14 TBB03-03-B.W ISI-TBB03 SHT. I SAFETY NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 TBB03.03-C-W ISI-TBB03 SHT. I SAFETY NOZZLE TO SAFE-END WELD 6 1.42 UT MRP-139 MRP-13901 170 14 TBB03-03-C-W ISI-TBB03 SI-T. 1 SAFETY NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 TBB03-04-W ISI-TBB03 SHT. 1 RELIEF NOZZLE TO SAFE-END WELD 6 1.42 UT MRP-139 MRP-139D1 170 14 TBB03-04-W ISI-TBB03 SHT. 1 RELIEF NOZZLE TO SAFE-END WELD BMV MRP-139 MRP.139J 14 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 29 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL SI PROGRAM PLAN TABLE BB.3 rerod3 xaminabons, Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes RV-101-17`1 ISI-RBB01 SHT. 1 RV CIRCUMFERENTIAL SHELL WELD NA 9.63 UT B-A B1.11 176 RV.103-121 ISI-RBBOI SHT. 1 RV CIRCUMFERENTIAL SHELL WELD NA 9.63 UT B-A B1.11 175,176 RV-101-122A ISI-RBB01 SHT. 1 RV LONGITUDINAL SHELL WELD NA 11.75 UT B-A B1.12 175 RV-101-122B ISI-RBB01 SHT. I RV LONGITUDINAL SHELL WELD NA 11.75 UT B-A B1.12 175 RV-`1O1-122C ISI-RBB01 SHT. I RV LONGITUDINAL SHELL WELD NA 11.75 UT B-A B1.12 175 RV-101-124A ISI-RBBOI SHT. 1 RV LONGITUDINAL SHELL WELD NA 9.63 UT B-A B1.12 176 RV-101-124B ISI-RBB01 SHT. 1 RV LONGITUDINAL SHELL WELD NA 9.63 UT B-A B1.12 176 RV-101-124C ISI-RBB01 SHT. 1 RV LONGITUDINAL SHELL WELD NA 9.63 UT B-A B1.12 176 RV-101-142A ISI-RBBOI SHT. 1 RV LONGITUDINAL SHELL WELD NA 9.63 UT B-A 61.12 176 RV.10i-142B ISI-RBBOi SHT. 1 RV LONGITUDINAL SHELL WELD NA 9.63 UT B-A B1.12 176 ftV-101-142C ISI-RBBOI SHT. 1 RV LONGITUDINAL SHELL WELD NA 9.63 UT B-A B1.12 176 CH-103-10i ISI-RBB01 SHT. I RV CLOSURE HEAD CIRCUMFERENTIAL WELD NA 8.25 UT B-A B1.21 177 RV-101-.141 ISI-RBB01 SHT. 1 RV LOWER HEAD TO SHELL WELD NA 6.38 UT B-A B1.21 176, 177 RV-102-151 ISI-RBB01 SHT. I RV LOWER HEAD TO DOLLAR PLATE WELD NA 6.38 UT B-A B1.21 177 CH4101-104.D ISI-RBB01 SHT. 1 RV CLOSURE HEAD MERIDIONAL WELD NA 8.25 UT B-A B1.22 177 RV-101-154A ISI-RBB01 SHT. 1 RV LOWER HEAD MERIDIONAL WELD NA 6.38 UT B-A B1.22 177 RV-101-1 546 ISI-RBB01 SHT. 1 RV LOWER HEAD MERIDIONAL WELD NA 6.38 UT B-A B1.22 177 RV-1 01-I1SAC ISI-RBB01 SHT. 1 RV LOWER HEAD MERIDIONAL WELD NA 6.38 UT B-A B1.22 177 RV-101-154AD ISI-RBB01 SHT. I RV LOWER HEAD MERIDIONAL WELD NA 6.38 UT B-A B1.22 177 RV-1014121 ISI-RBB01 SHT. 1 RV FLANGE TO VESSEL WELD NA 11.75 UT B-A B1.30 178 CH.101-101 ISI-RBB01 SHT. I RV CLOSURE HEAD TO FLANGE WELD NA 8.25 UT/MT B-A B1.40 176 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 30 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL SI PROGRAM PLAN TABLE BB-3

~erid 3Examinations l ISystem: BBI Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes TBB03-SEAM-1-W ISI-TBB03 SHT.1 SHELL TO BOTTOM HEAD LONGITUDINALWELD NA 3.75 UT B-B B2.12 101 EBBOID-SEAM-1-W ISI-EBB01D SHT. I BOTTOM HEAD TOTUBESHEET NA 5.00 UT B-B B2.40 104 RV-105-121-A ISI-RBB01 SHT. 1 INLET NOZZLE B TO VESSEL WELD NA 11.75 UT B-D B3.90 175,178 RV-105-121-B ISI-RBB01 SHT. 1 INLET NOZZLE C TO VESSEL WELD NA 11.75 UT B-D B3.90 175.178 RV-105-121-C ISI-RBBO1 SHT. 1 INLET NOZZLE F TO VESSEL WELD NA 11.75 UT B-D B3.90 175.178 RV-105-121-D ISI-RBB01 SHT. I INLET NOZZLE G TO VESSEL WELD NA 11.75 UT B-D B3.90 175,178 RV-105-121-A-IR ISI-RBB01 SHT. I INLET NOZZLE B INNER RADIUS AND BORE VT-1 B-D B3.100 18 RV-105-121-B-IR ISI-RB801 SHT. 1 INLET NOZZLE C INNER RADIUS AND BORE VT-1 B-D B3.1 00 18 RV-105-121-C-IR ISI-RBBI0 SHT. 1 INLET NOZZLE F INNER RADIUS AND BORE VT-1 B-D B3.100 18 RV-105-121-D-IR ISI-RBB01 SHT. 1 INLET NOZZLE G INNER RADIUS AND BORE VT-1 B-D B3.100 18 RV-107-121-A ISI-RBB01 SHT. 1 OUTLET NOZZLE A TO VESSEL WELD NA 11.75 UT B-D B3.90 175,178 RV-107-121-B ISI-RBBO1 SHT. I OUTLET NOZZLE DTO VESSEL WELD NA 11.75 UT B-D 83.90 175.178 RV-107.121-C ISI-RBB01 SHT. 1 OUTLET NOZZLE E TO VESSEL WELD NA 11.75 UT B-D B3.90 175.178 RV-107-121-D ISI-RBB01 SHT. 1 OUTLET NOZZLE HTO VESSEL WELD NA 11.75 UT B-D B3.90 175,178 RV-107-121-A-IR ISI-RBB01 SHT. 1 OUTLET NOZZLE A INNER RADIUS AND BORE VT-1 B-D B3.100 18 RV-107-121-B-IR ISI-RBB01 SHT. I OUTLET NOZZLE DINNER RADIUS AND BORE VT-1 B-D 83.100 18 RV-107-121-C-IR ISI-RBB01 SHT. 1 OUTLET NOZZLE C INNER RADIUS AND BORE VT-1 B-D B3.1WD 18 RV-107-121-D-IR ISI-RBB01 SHT. 1 OUTLET NOZZLE DINNER RADIUS AND BORE VT-1 B-D B3.100 18 TBB03-1OA-W ISI-TBB03 SHT. 1 SURGE NOZZLE TO BOTTOM HEAD WELD NA 2.55 UT B-D B3.110 101 TBB03-IOC-W ISI-TBB03 SHT. 1 SPRAY NOZZLE C TO TOP HEAD WELD NA 1.90 UT B-D 83.110 101 TBB03-10A-IR ISI-TBB03 SHT. 1 SURGE NOZZLE INNER RADIUS NA 2.55 UT B-D B3.120 101 16 WCRE-l16 4.1.4 Reactor Coolant System (BB) Revision 0 Page31 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB- 3 r~erod 3 Exarmnations I Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes TBB03-10C-IR ISI-TBB03 SHT.1 SPRAY NOZZLE C INNER RADIUS NA 1.90 UT B-D B3.120 101 16 E6BBIA-l-A-IR ISI-EBBOIA SHT. 1 PRIMARY INLET NOZZLE INNER RADIUS NA 5.00 UT 8-0 B3.140 104 16 EBB01A-1-B-IR ISI-EBBOIA SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS NA 5.00 UT B-D B3.140 104 16 CH-107-101 ISI-RBB0I SHT. I RV VENT PENETRATION NA NA UT 8-E B4.11 15 CH-1 12-201 ISI-RB801 SHT. I RV CRDM PENETRATION 1 NA NA UT B-E B4.12 15 CH-1 12-202-2 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 2 NA NA UT B-E B4.12 15 CH-1 12-202-3 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 3 NA NA UT B-E B4.12 15 CH-1 12-202-4 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 4 NA NA UT B-E 84.12 15 CH-I 12-202-5 ISI-RBBOI SHT. I RV CRDM PENETRATION 5 NA NA UT B-E 84.12 15 CH- 12-2034 !S!-ROf SHT.14 .RV CRDM PENETRTION 7 NA NA UT B-E B4.12 15 CH-1 12-203-7 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 7 NA NA UT B-E B4.12 15 CH.1 12-203-8 ISI-RBBOi SHT. 1 RV CRDM PENETRATION 8 NA NA UT B-E 64.12 15 CH-1`12-203-9 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 9 NA NA UT B-E 64.12 15 CH-112-204-10 ISI-RB801 SHT. 1 RV CRDM PENETRATION 10 NA NA UT B-E B4.12 15 CH-1 12-204-11 ISI-RBB01 SHT. I RV CROM PENETRATION 11 NA NA UT B-E B4.12 15 CH-1 12-204-12 ISI-RBBO1 SHT. I RV CRDM PENETRATION 12 NA NA UT B-E B4.12 15 CH-1 12-204-13 ISI-RBB01 SHT. I RV CRDM PENETRATION 13 NA NA UT B-E B4.12 15 CH-112-205-14 ISI-RBBO1 SHT. 1 RV CRDM PENETRATION 14 NA NA UT B-E B4.12 15 CH-1 12-205-15 ISI-RBBO1 SIT. 1 RV CRDM PENETRATION 15 NA NA UT B-E 84.12 15 CH-112-205-16 ISI-RBBO1 SHT. 1 RV CRDM PENETRATION 16 NA NA UT B-E B4.12 15 CH-I 12-205-17 ISI-RBBOI SHT. I RV CRDM PENETRATION 17 NA NA UT B-E B4.12 15 CH.1 12-206-18 ISI-RBBO1 SHT. I RV CRDM PENETRATION 18 NA NA UT B-E 84.12 15 CH-1 12-206-19 ISI-RBBOI SHT. I RV CRDM PENETRATION 19 NA NA UT B-E B4.12 15 CH-1 12-206-20 ISI RBBO1 SHT. 1 RV CRDM PENETRATION 20 NA NA UT B-E B4.12 15 CH-1 12-206-21 ISI-RBBO1 SHT. I RV CRDM PENETRATION 21 NA NA UT 8-E B4.12 15 CH-1 12-207-22 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 22 NA NA UT B-E B4.12 15 CH-I 12-207-23 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 23 NA NA UT B-E 84.12 15 CH-1 12-207-24 ISI-RBBO1 SHT. 1 RV CRDM PENETRATION 24 NA NA UT B-E 64.12 15 CH-1 12-207-25 ISI-RBBOI SHT. I RV CRDM PENETRATION 25 NA NA UT 8-E B4.12 15 CH.1 12-207-26 ISI-RBB01 SHT. I RV CRDM PENETRATION 26 NA NA UT B-E B4.12 15 CH-1 12-207-27 ISI-RBB01 SHT. I RV CRDM PENETRATION 27 NA NA UT B-E B4.12 15 CH-1 12-207-28 ISI-RBBO1 SHT. 1 RV CRDM PENETRATION 28 NA NA UT B-E B4.12 15 CH-112-207-29 ISI-RBBOI S-T. I RV CRDM PENETRATION 29 NA NA UT B-E B4.12 15 CH- 12-208-30 ISI-RBB0I SHT. 1 RV CRDM PENETRATION 30 NA NA UT B-E B4.12 15 CH-1 12-208-31 ISI-RBBO1 SHT. 1 RV CRDM PENETRATION 31 NA NA UT B-E B4.12 15 CH-1 12-208-32 ISI-RBBOI SHT. 1 RV CRDM PENETRATION 32 NA NA UT B-E 84.12 15 CH-1 12-208-33 ISI-RBBOi SHT. I RV CRDM PENETRATION 33 NA NA UT B-E B4.12 15 CH-1 12-208-34 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 34 NA NA UT B-E 84.12 15 CH.112-208-35 ISI-RBBOI SI-IT. I RV CRDM PENETRATION 35 NA NA UT B-E B4.12 Is WCRE-16 .4 Reactor Coolant System (BB) Revision 0 Page 32 of 41

O Iru')-.. - mrT1 C'R' 1-4 WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB-3 IPeriod3ExaminationslI Relief Request or Component Name Orawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes CH-1 12-208-36 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 36 NA NA UT B-E 84.12 15 CH-1 12-208-37 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 37 NA NA UT B-E 84.12 15 CH-1 12-209-38 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 38 NA NA UT B-E 84.12 15 CH-1 12-209-39 ISI-R3BOI SHT. 1 RV CRDM PENETRATION 39 NA NA UT B-E 84.12 1s CH-1 12-209-40 ISI-R8B01 SHT. 1 RV CRDM PENETRATION 40 NA NA UT B-E 84.12 1s CH-1 12-209-41 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 41 NA NA UT B-E B4.12 15 CH-1 12-210-42 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 42 NA NA UT B-E B4.12 15 CH.1 12-210-43 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 43 NA NA UT B-E B4.12 15 CH-1 12-210-44 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 44 NA NA UT B-E B4.12 .15 CH-1 12-210-45 ISI-RBB01 SHT. 1 RV CROM PENETRATION 45 NA NA UT B-E B4.12 15 CH-1 12-210-46 ISI-RBB01 SHT. I RV CRDM PENETRATION 46 NA NA UT B-E B4.12 15 CH-112-210-47 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 47 NA NA UT Q-E 94.12 CH-1 12-210-48 ISI.R9B01 SHT. 1 RV CRDM PENETRATION 48 15 NA NA UT B-E B4.12 CH-1 12-210-49 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 49 NA NA UT B-E B4.12 15 CH-112-211-50 ISI-RBB01 SHT. I RV CRDM PENETRATION 50 NA NA UT B-E B4.12 15 CH-112-211-51 ISI-RBB01 SHT. I RV CRDM PENETRATION 51 NA NA UT B-SE B4.12 15 CH-1 12-211-52 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 52 NA NA UT B-E B4.12 15 CH-1 12-211-53 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 53 NA NA UT B-E B4.12 15 CH-1112-212-54 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 54 NA NA UT B-E B4.12 15 CH-112-212-55 ISI-RB801 SHT. 1 RV CRDM PENETRATION 55 NA NA UT B-E B4.12 15 CH-1 12-212-56 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 56 NA NA UT B-E B4.12 15 CH-112-212-57 ISI-RBB01 SHT. I RV CRDM PENETRATION 57 15 NA NA UT B-E B4.12 CH-112-212-58 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 58 NA NA UT B-E 84.12 15 CH-1 12-212-59 ISI-RBB01 SHT. I RV CRDM PENETRATION 59 NA NA UT B-E B4.12 15 CH-1 12-212-60 ISI-RBB01 SHT. I RV CRDM PENETRATION 60 NA NA UT B-SE B4.12 15 CH-1 12-212-61 ISI-RBB01 SHT. I RV CRDM PENETRATION 61 NA NA UT B-E B4.12 15 CH-1112-213-62 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 62 NA NA UT B-E B4.12 15 CH-1 12-213-63 ISI-RBB01 SHT. I RV CRDM PENETRATION 63 NA NA UT B-E 84.12 15 CH-1 12-213-64 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 64 NA NA UT B-E B4.12 15 CH-1 12-213-65 15 ISI-RBB01 SHT. I RV CRDM PENETRATION 65 NA NA UT B-E B4.12 CH-i 12-214-66 ISI-RBB01 SHT. I RV CRDM PENETRATION 66 NA NA UT B-E B4.12 15 CH- 12-214-67 ISI-RBBOi SHIT. I RV CRDM PENETRATION 67 NA NA UT B-E B4.12 15 CH-112-214-68 ISI-RBB01 SHT. I RV CRDM PENETRATION 68 NA NA UT B-E B4.12 15 CH-112-214-69 ISI-RB801 SHT. I RV CRDM PENETRATION 69 NA NA UT B-E B4.12 15 CH-1i12-214-70 ISI-RBB01 SHT. I RV CRDM PENETRATION 70 NA NA UT B-E B4.12 15 CH-112-214-71 ISI-RBB01 SHT. I RV CRDM PENETRATION 71 NA NA UT B-E B4.12 15 CH-112-214-72 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 72 NA NA UT B-E B4.12 15 CH-1 12-214-73 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 73 NA NA UT B-E B4.12 15 CH-1 12-215-74 ISI-RBB01 SHT. I RV CRDM PENETRATION 74 NA NA UT B-E B4.12 15 CHM1 12-215-75 ISI.RBB01 SHT. 1 RV CRDM PENETRATION 75 NA NA UT B-E B4.12 15 CH-1 12-215-76 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 76 NA NA UT B-E 84.12 15 CH-1 12-215-77 ISI-RBB01 SHT. 1 RV CRDM PENETRATION 77 NA NA UT B-E B4.12 15 WCRE-16 .4 Reactor Coolant System (BB) Revision 0 Page 33 of 41

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WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB-3 Feriod 3 Examinations l I System: BB I Relief Request or Component Name Drawing Number Component Description Size Thckness NDE Method Category Item Cal Block Notes CH-1 12-215-78 ISI-RBB01 SHT.-1 RV CRDM PENETRATION 78 NA NA UT B-E B4.12 Is CH-NUT-37 ISI-RBB0I SHT. I REACTOR VESSEL NUT 37 VT-11 B-G-1 B6.10 CH-NUT-38 ISI-RB801 SHT. I REACTOR VESSEL NUT 38 VT-1 B-4-1 B6.10 CH-NUT-39 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 39 VT-1 B-G-1 86.10 CH-NUT-40 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 40 VT-1 B-GC1 B6.10 CH-NUT-41 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 41 VT-1 B-G-1 B6.10 CH-NUT-42 ISI-RBB01 SHT. I REACTOR VESSEL NUT 42 VT-1 B-C-1 B6.10 CH-NUT-43 ISI-RBB01 SHT. I REACTOR VESSEL NUT 43 VT-1 B-G-1 B6.10 CH-NUT-44 ISI-RBB01 SHT. I REACTOR VESSEL NUT 44 VT-1 B-GC1 B6.10 CH-NUT-45 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 45 VT-1 BG-1 B6.10 CH-NUT-46 ISI-RBB01 SHT. I REACTOR VESSEL NUT 46 VT-1 B-G-1 B6.10 CH-NUT-47 ISI-RBB01 SHT. I REACTOR VESSEL NUT 47 VT-1 B-G-1 B6.10 CH-NUT-48 ISI-RBBOi SHT. I REACTOR VESSEL NUT 48 VT-1 B-4-1 86.10 CH-NUT.49 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 49 VT-1 B-C1- B6.10 CH-NUT-50 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 50 VT-1 B-G-1 66.10 CH-NUT-51 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 51 VT-1 B-4-1 B6.10 CH-NUT-52 ISI-RBB01 Sif. I REACTOR VESSEL NUT 52 VT-1 B-4-1 B6.10 CH-NUT-53 ISI-RBB01 SHT. 1 REACTOR VESSEL NUT 53 VT-1 B-4-1 B6.10 CH-NUT-54 ISI-RBB01 SHT. I REACTOR VESSEL NUT 54 VT-I B-G-1 B6.10 CH-STUD-37 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 37 NA NA UT B-G1 B6.20 195 CH-STUD-38 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 38 NA NA UT B-4-1 B6.20 195 WCRE-1 6 4.1.4 Reactor Coolant System (BB) Revision 0 Page 34 of4l

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB-3 reriod 3 Examinationsl I System: BB I Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes CH-STUD-39 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 39 NA NA UT B-G-1 B6.20 195 CH-STUD.40 ISI-RBB01 SHT. I REACTOR VESSEL STUD 40 NA NA UT B-G-1 B6.20 195 CH-STUD-41 ISI-RBB01 SHT. I REACTOR VESSEL STUD 41 NA NA UT B--1 B6.20 195 CH-STUD-42 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 42 NA NA UT B-G-1 B6.20 195 CH-STUD-43 ISI-RBB01 SHT. I REACTOR VESSEL STUD 43 NA NA UT B--1 B6.20 195 CH-STUD-44 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 44 NA NA UT B-G-1 B6.20 195 CH-STUD-45 ISI-RBB01 SHT. I REACTOR VESSEL STUD 45 NA NA UT B4--1 B6.20 195 CH-STUD-46 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 46 NA NA UT B4--1 86.20 195 CH-STUD47 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 47 NA NA UT B-G-1 86.20 195 CH-STUD-48 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 48 NA NA UT B-G-1 B6.20 195 CH-STUD-49 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 49 NA NA UT B4--1 86.20 195 CH-STUD-50 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 50 NA NA UT B-G-1 B6.20 195 CH-STUD-51 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 51 NA NA UT B-G-1 B6.20 195 CH-STUD-52 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 52 NA NA UT BG-1 B6.20 195 CH-STUD-53 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 53 NA NA UT B4--1 B6.20 195 CH-STUD-54 ISI-RBB01 SHT. 1 REACTOR VESSEL STUD 54 NA NA UT B-G-1 B6.20 195 RV-LIG-37 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 37 NA NA UT B-G-1 86.40 140 RV-LIG-38 ISI-RBB01 SHT. 1 REACTOR VESSELTHREAD IN FLANGE 38 NA NA UT B4--1 B6.40 140 RV-LIG-39 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 39 NA NA UT B-G-1 B6.40 140 RV-LIG-40 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 40 NA NA UT B-G-1 86.40 140 RV-LIG-41 ISI-RBBI01 SHT. I REACTOR VESSEL THREAD IN FLANGE 41 NA NA UT B--1 B6.40 140 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 35 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL IS[ PROGRAM PLAN TABLE 8B-3 reriod 3 Examinations ISystem: BB I Refief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Black Notes RV-LIG-42 ISI-RBB01 SHT. 1 REACTOR VESSELTHREAD IN FLANGE 42 NA NA UT B--1 B6.40 140 RV-LIG-43 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 43 NA NA UT B-G-1 B6.40 140 RV-LIG-44 ISI-RBB01 SHT. I REACTOR VESSEL THREAD IN FLANGE 44 NA NA UT BG-1 86.40 140 RV-LIG.45 ISI-RBB01 SHT. I REACTOR VESSEL-THREAD IN FLANGE 45 NA NA UT B-G-1 86.40 140 RV-LIG-46 ISI-RBBI01 SHT. I REACTOR VESSELTHREAD IN FLANGE 46 NA NA UT B-G-1 B6.40 140 RV-LIG47 ISI-RBBOi SHT. 1 REACTOR VESSEL THREAD IN FLANGE 47 NA NA UT B-G1 B6.40 140 RV-LIG-48 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 48 NA NA UT B-G-1 B6.40 140 RV-LIG-49 ISI-RBB0I SHT. 1 REACTOR VESSEL THREAD IN FLANGE 49 NA NA UT B-G-1 B6.40 140 RV-LIG-50 ISI-RBB01 SHT. I REACTOR VESSEL THREAD IN FLANGE 50 NA NA UT B-G-1 B6.40 140 RV-LIG-51 ISI-R8B01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 51 NA NA UT BS--1 B6.40 140 RV-LIG-52 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 52 NA NA UT BG-1 B6.40 140 RV-LIG-53 ISI-RBB01 SHT. i REACTOR VESSEL THREAD IN FLANGE 53 NA NA UT B-G-1 B6.40 140 RV-LIG-54 ISI-RBB01 SHT. 1 REACTOR VESSEL THREAD IN FLANGE 54 NA NA UT B-G-1 B640 140 CH-WASH-37 ISI-RB801 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 37 VT-1 B-G-1 B6.50 CH-WASH-38 ISI-RBB01 SHT. I REACTOR VESSEL WASHER AND BUSHING 38 VT-1 B-<-1 B6.50 CH-WASH-39 ISI-RBB01 SHT. I REACTOR VESSEL WASHER AND BUSHING 39 VT-1 B-G-1 B6.50 CH-WASH.40 ISI-RBB01 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 40 VT-1 B-G-1 86.50 CH-WASH-41 ISI-RBB01 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 41 VT-i B-G-1 86.50 CH-WASH-42 ISI-RBB01 SHT. 1 REACTOR VESSELWASHER AND BUSHING 42 VT-1 B-G-1 B6.50 CH-WASH-43 ISI-RBB01 SHIT. I REACTOR VESSELWASHER AND BUSHING 43 VT-1 B-G-1 B6.50 CH-WASH-44 ISI-RBB01 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 44 VT-1 B-G1 86.50 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 36 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB- 3 lPerbd 3 ExaminatlonsIl I Systcrn: BB I Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes CH-WASH-45 ISI-RBB01 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 45 VT-1 BG1 B6.50 CH-WASH-46 ISI-RBB01 SHT. I REACTOR VESSEL WASHER AND BUSHING 46 VT-1 B-G-1 B6.50 CH-WASH-47 ISI-RBBOi SHT. I REACTOR VESSELWASHER AND BUSHING 47 VT-1 B-G-1 B6.50 CH-WASH-48 ISI-RBB01 SHT. I REACTOR VESSELWASHER AND BUSHING 48 VT-1 B-G-1 B6.50 CH-WASH-49 ISI-RBB01 SHT. 1 REACTOR VESSELWASHER AND BUSHING 49 VT-1 B-G-1 B6.50 CH-WASH-50 ISI-RBB01 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 50 VT-1 B-G-1 B6.50 CH-WASH-51 ISI-RBB01 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 51 VT-1 B-G-1 B6.50 CH-WASH-52 ISI-RBB01 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 52 VT-1 B-G-1 B6.50 CH-WASH-53 ISI-RBB01 SHT. 1 REACTOR VESSEL WASHER AND BUSHING 53 VT-1 B-G-1 B6.50 CH-WASH-54 ISI-RBB01 SHT. 1 REACTOR VESSELWASHER AND BUSHING 54 VT-1 BG-1 B6.50 PBB0IA-STUDS M-712-00057 PBB01A PUMP MAIN BOLTS I STUDS (24) NA NA UT B-G-1 B6.180 3 PB801A-FLANGE ISI-PUMPS PBB01A FLANGE SURFACE VT-1 B-G-1 B6.190 4 PBBO1A-WASHERS/NUTS M.712.00057 PBBOIA PUMP MAIN NUTS, BUSHINGS, WASHERS (24) VT-1 B-G-1 B6.200 5 EBBOI D-2-A-b ISI-EBBOID SHT. 1 EBBOID HOTLEG MANWAY BOLTING VT-1 B-G-2 B7.30 6 EBBOID-2-B-b ISI-EBB01D SHT. 1 EBBO0D COLDLEGMANWAY BOLTING VT-1 B-G-2 B7.30 6 PBBO1A-SEALBOLT M-712-00058 RCP A #1 SEAL HOUSING BOLTSISTUDS & NUTS 2 VT-1 B-G-2 B7.60 3 TBB03-LUG-A-W ISI.TBB03 SHT. 1 SEISMIC LUG INTEGRAL ATTACHMENT PT B-K 810.10 13R-02. 11 TBB03-LUG-B-W ISI-TBB03 SHT. I SEISMIC LUG INTEGRAL ATTACHMENT PT B-K 810.10 13R-02, 11 TBB03-LUG-C-W ISI-TBB03 SHT. I SEISMIC LUG INTEGRALATTACHMENT PT B-K 810.10 13R-02. 11 TBB03-LUG.D-W ISI-TBB03 SHT. 1 SEISMIC LUG INTEGRAL ATTACHMENT PT B-K 810.10 13R-02, 11 PBBOIA-SURF ISI-PUMPS PBB01A INTERNAL PRESSURE SURFACE VT-3 B-L-2 1 B12.20 7 WCRE-1 6 4.1.4 Reactor Coolant System (BB) Revision 0 Page 37 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB- 3

,Feriod 3 Examinations I ISystern: BB-T Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes 8B2-0801 OA-SURF BB-02-02 VALVE 8010A INTERNAL PRESSURE SURFACE VT-3 B-M-2 B12.50 8 RV-INTERIOR ISI-RBB01 SHT. 1 REACTOR VESSEL INTERIOR VT-3 B-N-1 B13.10 RV-CSL-104-142-A ISI-RBBOI SHT. I CORE SUPPORT LUG VT-3 B-N-2 B13.60 RV-CSL-104-142-B ISI-RBB01 SHT. 1 CORE SUPPORT LUG VT-3 B-N-2 B13.60 RV-CSL-104-142-C ISI-RBBO1 SHT. 1 CORE SUPPORT LUG VT-3 B-N-2 B13.60 RV-CSL-104-142-D ISI-RBB01 SHT. 1 CORE SUPPORT LUG VT-3 B-N-2 B13.60 RV-CSL-104-142-E ISI-RBB01 SHT. 1 CORE SUPPORT LUG VT-3 B-N-2 B13.60 RV-CSL-104-142-F ISI-RBB01 SHT. 1 CORE SUPPORT LUG VT-3 B-N-2 813.60 RV-CORE STRUCT ISI-RBB01 SHT. I REMOVABLE CORE SUPPORT STRUCTURES VT-3 B-N-3 B13.70 EBBOIA-16-W ISI-EBB01A SHT. 1 STEAM NOZZLE WELD NA 3.95 UT/MT C-B C2.21 102 BB-02-H007 BB-01-02 PIPING SUPPORT 3 VT-3 F-A F1.10 BB-02-H008 BB-01-02 PIPING SUPPORT 3 VT-3 F-A F1.10 BB-04-R014 BB-01-04 SHT. 1 PIPING SUPPORT 4 VT-3 F-A F1.10 BB-04-C003 8B-01-04 SHT. 2 PIPING SUPPORT 4 VT-3 F-A F1.10 BB-04-R008 8B-01-04 SHT. 2 PIPING SUPPORT 4 V`1-3 F-A F1.10 BB-111-H001 BB-02-11 PIPING SUPPORT 2 V`1-3 F-A F1.10 BB-01-R004 88-05-01 PIPING SUPPORT 14 VT-3 F-A F1.10 CRDMPL-SUP-5 M-717-0028 CRDM Upper Seismic Support V`1-3 F-A F1.40 CRDMPL-SUP-6 M-717-0028 CRDM Upper Seismic Support VT-3 F-A F1.40 EBBO1A-03 231 M-717-00002 SG A LOWER COLUMN SUPPORT VT-3 F-A F1.40 EBB01A-04 231 M-717-00002 SG A LOWER COLUMN SUPPORT V`1-3 F-A F1.40 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 38 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE 88- 3 lcriod 3 Examinations I System: BO Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes P8B0IA-SUP-3 ISt-PUMPS RCP A TIE ROD SUPPORT VT-3 F-A F1.40 PBB01A-SUP-3A ISI-PUMPS RCP A COLUMN SUPPORT VT-3 F-A F1.40 RBB-01-04 ISI-RBBO1 SHT. I RV SUPPORT PAD 4 VT-3 F-A F1.40 13R-04 TBB03-LUG-A-W ISI-TBB03 SHT. 1 SEISMIC SUPPORT VT-3 F-A F1.40 13R-02,1 1 TBB03-LUG.B-W ISI-TBB03 SHT. I SEISMIC SUPPORT VT-3 F-A F1.40 13R-02,1 1 TBB03-LUG-C-W ISI-TBB03 SHT. I SEISMIC SUPPORT VT-3 F-A F1.40 13R-02,1 1 TBB03-LUG-D-W ISI-TBB03 SHT. 1 SEISMIC SUPPORT VT-3 F-A F1.40 13R-02.1 1 BB-01-S301-09 BB-03-01 3" NOZZLE TO 3" X 1.5" REDUCER 3 0.438 UT R-A R1.11 112 12,13 BB-0-S401-10 BB-04-01 3- NOZZLE TO 3" X 1 1/2' REDUCER 3 0.438 UT R-A R1.1 1 112 12,13 BB-01--S001-6 BB-05-01 14' PIPE TO 14" ELBOW 14 1.25 UT R-A R1.11 130 12,13 13B-01-F102 BB-01-*01 27 1/2' ELBOW-LOOP #1 RPV INLET SAFE-END 27.5 2.5 UT R-A R1.20 SAP-07, 106 12 BB-01-F202 BB-02-01 27 1/2 ELBOW-LOOP #2 RPV INLET SAFE-END 27.5 2.5 UT R-A R1.20 SAP-07. 106 12 BB-01-F103 BB-01 -01 SAFE END TO 29" ID. PIPE 29 2.5 UT R-A R1.20 SAP-01. 105 12 BB-i-F203 BB-02-01 SAFE END TO 29 ID PIPE 29 2.5 UT R-A R1.20 SAP-07, 106 12 13B-01-F303 BB-03-01 SAFE END TO 29- ID PIPE 29 2.5 UT R-A R1.20 SAP-07, 106 12 BB-04-S002-E BB-01-04 SHT. 2 6 X4" EXPANDER TO 6" PIPE 6 0.719 UT R-A R1.20 117 12 BB-06FOOI BB-02-01 3" PIPE TO 3" NOZZLE ON 036-BCA-31" 3 0.438 UT R-A R1.20 112 12.13 BB-06-PW6000 BB-02-01 3- PIPE TO CAP (B.W.) 3 0.438 UT R-A R1.20 112 12 H-B-24-W501 BB-06-01 2" PIPE TO 2 ELBOW 2 0.344 UT R-A R1.20 156 12 RV-301-12 1-A ISI-RBB01 SHT. I LOOP #1 RPV OUTLET NOZZLE TO SAFE-END 29 2.5 UT R-A R1.20 179 12, 19 RV-302-1 21-A ISI-RBB01 SHT. I SAFE-END TO LOOP #1 RPV INLET NOZZLE 27.5 2.5 UT R-A R1.20 179 12, 19 WCRE-16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 39 of 41

, 1 WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB- 3 erhid 3 Examinationsl l Systern: 8Bl Relief Request or Component Name Drawing Number Component Descdption Size Thickness NDE Method Category Item Cal Block Notes RV-302-121-D ISI-RBBO1 SHT. 1 SAFE-END TO LOOP #4 RPV INLET NOZZLE 27.5 2.5 UT R-A R1.20 179 12, 19 PBBOIA-FLYWHEEL ISI-PUMPS PUMP FLYWHEEL NA NA UT/PT/MT USAR RG1.14 9 PBBO1B-FLYWHEEL ISI-PUMPS PUMP FLYWHEEL NA NA UTIPTIMT USAR RG1.14 9 PBBO1C-FLYWHEEL ISI-PUMPS PUMP FLYWHEEL NA NA UT/PTIMT USAR RG1.14 9 PBBOID0-FLYWHEEL ISI-PUMPS PUMP FLYWHEEL NA NA UTIPT/MT USAR RGt.14 9 RV-301.121-A ISI-RBB01 SHT. I LOOP #1 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 UT MRP-139 MRP-13902 179 14 RV-301-121-A ISI-RBB01 SHT. 1 LOOP #1 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 BMV MRP-139 MRP-139J 14 RV-301-121-B ISI-RBB01 SHT. 1 LOOP #2 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 UT MRP-139 MRP-139D2 179 14 RV-301-121-8 ISI-RBB01 SHT. I LOOP #2 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 BSMV kiRD_!!39 0RP 139J1 14 RV-301-121-C ISI-RBB01 SHT. I LOOP #3 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 UT MRP-139 MRP-139D2 179 I14 RV-301-121-C ISI-RBB01 SHT. 1 LOOP #3 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 BMV MRP-139 MRP-139J 14 RV-301-121-D ISI-RBB01 SHT. 1 LOOP #4 RPV OUTLET NOZZLE TO SAFE-END 2.92 MRP-139 `14 29 UT MRP-139D2 179 RV-301-121-D ISI-RBB01 SHT. I LOOP #4 RPV OUTLET NOZZLE TO SAFE-END 29 2.92 BMV MRP-1 39 MRP-139J 14 RV-302-121-A ISI-RBBOi SHT. I SAFE-END TO LOOP #1 RPV INLET NOZZLE 27.5 2.79 UT MRP-139 MRP-139E 179 14 RV-302-121-B 1SI-RBB01 S-T. 1 SAFE-END TO LOOP #2 RPV INLET NOZZLE 27.5 2.79 UT MRP-139 MRP-139E 179 14 RV-302-121-C ISI-RBB01 SHT. 1 SAFE-END TO LOOP #3 RPV INLET NOZZLE 27.5 2.79 UT MRP-139 MRP-139E 179 RV-302-121-D ISI-RBB01 SHT. 1 SAFE-END TO LOOP #4 RPV INLET NOZZLE 27.5 2.79 UT MRP-139 MRP-139E 179 14 TBB03-01-W ISI-TBB03 SHT. 1 SURGE NOZZLE TO SAFE-END WELD 14 1.51 UT MRP-139 MRP-139D1 171 14 TBB03-01-W ISI-TBB03 SHT. 1 SURGE NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 TBBO3.02-W ISI-TBB03 SHT. I SPRAY NOZZLE TO SAFE-END WELD 1.00 UT MRP.139 MRP-13901 169 14 TBB03-02-W ISI.TBB03 SHT. 1 SPRAY NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 TB803-03-A-W ISI-TBB03 SHT. I SAFETY NOZZLE TO SAFE-END WELD 6 1.42 UT MRP-139 MRP-139D1 170 14 TBB03.03-A-W ISI-TBB03 SHT. 1 SAFETY NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 TBB03-03-B-W ISI-TBB03 SHT. 1 SAFETY NOZZLE TO SAFE-END WELD 6 1.42 UT MRP-139 MRP-139D1 170 14 TBB03-03-B-W ISI-TBB03 SHT. 1 SAFETY NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 6

TB83-03-C-W ISI-TBBO03 SHT. 1 SAFETY NOZZLE TO SAFE-END WELD 1.42 UT MRP-139 MRP-139D1 170 14 TBB03-03-C-W ISI-TBB03 SHT. 1 SAFETY NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 WCRE 16 4.1.4 Reactor Coolant System (BB) Revision 0 Page 40 of 41

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BB-3 Pedod 3 Examinations l System: BB llo Ro!lief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes TBB03-04-W ISI-TBB03 SHT. 1 RELIEF NOZZLE TO SAFE-END VELD 6 1.42 UT MRP-139 MRP-139D1 170 14 TBB03-04-W ISI-TBB03 SHT. 1 RELIEF NOZZLE TO SAFE-END WELD BMV MRP-139 MRP-139J 14 WCRE-16 4.1.4 Rcactor Coolant System (BB) Revision 0 Page 41 of 41

I WOLF CREEK GENERATING STATION Ii THIRD INTERVAL IS[ PROGRAM PLAN A

G 4.1.5 Chemical and Volume Control System (BG)

E DI 0 A. Applicable System Piping and Instrument Drawings 1

1. M-12BGOI-Chemical and Volume Control System

2. M 12BG03-Chcmical and Volume Control System 1)

B. Classification Of Components Details of the classification of the Chemical and Volume Control System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek 0 Generating Station Interval 3".

6 C. Nonexempt and Exempt ASME Class Components A listing of Nonexempt and Exempt ASME Class components are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and IS Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Chemical and Volume Control System. These drawings are part of the M-189-50 series.

1. M-189-50BG-0I-01 Sheet I Chemical and Volume Control Normal Charging Line Containment Penetration

2. M-189-SOBG-01-21 Sheet I Chemical and Volume Control Normal and Alternate Charging Lines 3 M-189-5OBG-02-22 Sheet I Chemical and Volume Control Letdown Line

4. M-189-50BG-02-22 Sheet 2 Chemical and Volume Control Letdown Line Containment Penetration

5. M-189-5OBG-03-23 Sheet I Chemical and Volume Control Excess Letdown Line

6. M-189-50BG-04-09 Sheet I Chemical and Volume Control RCP Seal Water Injection Containment Penetration

7. M-189-SOBG-05-24 Sheet I Chemical and Volume Control Auxiliary Spray Line

8. M-189-5OBG-06-02 Sheet I Chemical and Volume Control Centrifugal Charging Pump Suction

9. M-189-5OBG-06-02 Sheet 2 Chemical and Volume Control CCP Discharge (HPSI Discharge)

10. M-189-50BG-06-10 Sheet I Chemical and Volume CCP Discharge to Seal Water Injection Filters

11. M-189-501SI-PUMPS Sheet I ISI Pumps WCRE-16 4.1.5 Chemical and Volume Control System (BG) Revision 0 Page I of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL 15 PROGRAM PLAN 4.1.5 Chemical and Volume Control System (BG)

E. Summary Or Components Subject To Section Xi and Augmented NDE/Scheduled For Examination Table I is a summary of the components and items subject to NDE per ASME Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the IS1 Database.

TABLE I SECTION Xi AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM Pi P2 P3 INTERVAL PIPING WELDED CC C3.20 4 1 0 0 l ATTACHMENTS PUMPS WELDED C-C C3.30 . 8 0 1 0 ATTACH-MENTS PRESSURE RETAINING C-G C6.10 4 0 0 2 2 PUMP WELDS PIPING COMPONENTS F-A FP.10 . 15 1 2 1 4 SUPPORTS PIPING COMPONENTS F-A P1.20 . 30 1 2 2 5 SUPPORTS I SUPPORTS OTHER F-A F.40 8 2 2 0 4 THAN PIPING SUPPORTS PIPING WELDS SUBJECT R-A R1.1 I . 25 2 2 3 7 TO THERMAL FATIGUE Note I Note I PIPING WELDSNOT R-A R1.20 . 167 4 4 4 12 SUBJECT TO A DAMAGE Note I Note I MECHANISM _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

PIPING WELDS SUBJECT . USAR 3.6.2 103 0 0 0 0 TO HELB REQUIREMENTS __ _ -

Note 1: See Section H for an explanation of Category R-A and Item Rl.xx nomenclature.

WCRE-I 6 4.1.5 Chemical and Volume Control System (BG) Revision 0 Page 2 of 6

I WOLF CREEK GENERATING STATION A THIRD INTERVAL IS11 PROGRAM PLAN

[3 4.1.5 Chemical and Volume Control System (BG) 0 F. Augmented ISI Requirerments The following Augmented ISI requirements apply to the Chemical and Volume Control System:

1. WCGS USAR Sections 3.6.1, Postulated Piping Failures In Fluid Systems Inside and

/ Outside Containment and 3.6.2, Determination Of Break Locations and Dynamic Effects

- Associated With The Postulated Rupture Of Piping- WCGS has implemented a Risk U Informed-High Energy Line Break program as an alternative to the examination O methodology of USNRC Branch Technical Position MEB 3-1. This program is 6 maintained in WCRE-14 and is applicable to the piping within the "no break zone" associated with high energy piping in containment penetration areas. The "no break zone' is an area where pipe breaks were not postulated due to the stress levels being within limits specified in USAR Section 3.6.2. No welds in the BG system were selected under the RI-HELB program.

G. System Pressure Testing In accordance with Section Xi, IWA-5000 and IWB-S000, the Class I pressure retaining components within the Chemical and Volume Control System will receive a system leakage test per IWB-5220 prior to plant startup following each refueling outage.

In accordance with Section Xl, IWA-5000 and IWC-5000, the Class 2 pressure retaining components within the Chemical and Volume Control System will receive a system leakage test per IWC-5220 each inspection period.

Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Program A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class I and 2 piping welds at WCCiS. This program is described in detail in Section 2.3.

Chemical and Volume Control System welds selected for examination per the RI-ISI program are listed in Tables BG-1, BG-2 and BG-3. Since the EPRI methodology used for the RI-ISI Program does not prescribe Code Examination Category and Item Numbers, guidance was taken from Code Case N-578-1 for the assignment of these designators.

When a specific degradation mechanism (DM) exists at a selected location, then the volume to be examined shall be as recommended in Section 4 of EPRI TR-4 12657 Rev.

B-A. Welds subject to a DM are identified by a note in the Table. Welds selected that have no associated DM shall have the volume examined as shown in Figures 4.1-4 of TR-112657 Rev. B-A.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table BG-I (Period I Examinations), Table BG-2 (Period 2 Examinations),

and Table BG-3 (Period 3 Examinations). ). The following Notes apply to the tables:

1. These welds have been selected per the RI-ISI Program. The requirements for examination of these welds are included in Paragraph H above.

2. These welds have Thermal Fatigue identified as the degradation mechanism.

WCRE-16 4.1.5 Chemical and Volume Control System (BG) Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BG- 1 I Perid 1Examinations I _System: BG I Relief Request or Compornent Name Drawving Number Component Description Size Thickness NDE Method Category Item Cal Block Notes BG-02-A002 BG-06-02 SHT. 1 PIPING INTEGRAL ATTACHMENTS 8 PT C-C C3.20 BG-21 -F01 2 BG-01-21 3" PIPE TO VALVE BB8378A 3 0.438 UT R-A R1.11 112 1.2 BC-23-FW582 BG-03-23 VALVE BBV065 TO 2' PIPE 2 0.344 UT R-A R1.11 156 1 BG-23-W5S4 BG-03-23 2"TEE TO 2" PIPE 2 0.344 UT R-A R1.20 156 1 BG-02-F045 BG-06-02 SHT. 2 4" PIPE TO 4' ELBOW 4 0.531 UT R-A R1.20 114 1 BG-02-FW312 BG-06-0Z SHT. 2 4" PIPE TO 4" ELBOW 4 0.531 uT R-A R1.20 114 1

BG-02-S040-C BG-06-02 SHT. 2 4" ELBOW TO 4" PIPE 4 0.531 UT R-A R1.20 114 BG-24-HOO1 BG-05-24 PIPING SUPPORT 2 VT-3 F-A F1.10 BG-02-A002 BG-062 SHT. 1 PIPING SUPPORT 8 VT-3 F-A F1.20 PBG05A-SUP-1 BG-06-02 SHT. 1 CHARGING PUMP ASUPPORT 6 VT-3 F-A F1.40 PBGO5A-SUP-2 BG-06-02 SHT. 1 CHARGING PUMP A SUPPORT 6 VT-3 F-A F1.40 WCRE-16 4.1.5 Chemical and Volume Control System (BG) Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BG-2 l Period 2 Examinatins I System: BG I Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes PBG05A-SUP-3 BG-06.02 SHT. 1 CHARGING PUMP A INTEGRALLY WELDED ATTACH. 6 PT C-C C3.30 BG-21-FO13B BG-01-21 3' PIPE TO VALVE 8378A 3 0.438 UT R-A R1.11 112 1,2 BG-22-F327A BG-02-22 SHT.1 3' ELBOW TO 3" PIPE" 3 0.438 UT R-A R1.11 112 1,2 BG-21-FW314 BG-01-21 3' PIPE TO 3" ELBOW 3 0.438 UT R-A R1.20 112 ¶ BG-02-FW333 BG-06-02 SHT. 2 4 TEE TO 4' PIPE 4 0.531 UT R-A R1.20 114 1 BG n"2-0C A 4'

• EE -O0 4' P;PEE 4 0.531 UT R-A R1.20 114 1

BG-10-FW066 BG-06-10 3 X 2' REDUCER TO 2' PIPE 2 0.344 UT R-A R1.20 156 BG-21-HO08 BG-01-21 PIPING SUPPORT 3 VT-3 F.A F1.10 BG-22-H007 BG-02-22 SHT. 1 PIPING SUPPORT 3 Vr-3 F-A F1.10 BG-02-R019 BG-06-02 SHT. 2 PIPING SUPPORT 4 VT-3 F-A F1.20 BG-10-C528 BG-610 PIPING SUPPORT 2 VT.3 F-A F1.20 PBGO5A-SUP-3 BG.06-02 SHT. 1 CHARGING PUMP A SUPPORT 6 VT-3 F-A F1.40 PBGO5A-SUP-4 BG-06-02 SHT. 1 CHARGING PUMP A SUPPORT 6 VT-3 F-A F1.40 WCRE-I 6 4.1.5 Chemical and Volume Control System (BG) Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL IS[ PROGRAM PLAN TABLE BG.3 l Period 3 Examinations I Systern: SG I Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes PBG05A-F-1 BG-06-02 SHT. I CHARGING PUMP AFLANGE TO PUMP CASING WELD 6 0.28 PT C-G C6.10 PBG05A-F-2 BG-06-02 SHT. 2 CHARGING PUMP AFLANGE TO PUMP CASING WELD 4 0.531 PT C-G C6.10 BG-24-FW552 BG-05-24 2' PIPE TO BBVO84 SAFE END 2 0.344 UT R-A R1.11 156 1.2 BG-24-FWt553A BG-05-24 BBVO84 SAFE END TO 2" X 2" X 3/4" TEE 2 0.344 UT R-A R1.11 156 1.2 BG-23-W594A 8G-03-23 2" PIPE TO 2"X 2"X 3/4" TEE 2 0.344 UT R-A Ri.11 156 1.2 BG-24-FW554 8G-05-24 2"X 2"X V4"TEE TO 2"P!PE 2 0.3A ULT R.A R1.20 156 1 BG-10-F003 BG-06-10 3 X 2"REDUCER TO 2" PIPE 2 0.344 UT R-A R1.20 156 1 BG-02-S040-A BG-062 SHT. 2 4" ELBOW TO 4" PIPE 4 0.531 UT R-A R1.20 114 1 BG-02-S048-8 BG-06.02 SHT. 2 4" TEE TO 4" X3" REDUCER 4 0.531 UT R-A R1.20 114 1 BG-22-H008 BG-02-22 SHT. 1 PIPING SUPPORT 3 VT-3 F-A F1.10 BG-02-C013 BG-6-02 SHT. 1 PIPING SUPPORT 8 VT-3 F-A F1.20 BG-02-H007 BG06.02 SHT. I PIPING SUPPORT 6 VT-3 F-A F1.20 WCRE"16 4.1.5 Chemical and Volume Control System (BG) Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION

1. THIRD INTERVAL 11SI PROGRAM PLAN A

G E 4.1.6 Steam Generator Blowdown System (BM) 0l A. Applicable System Piping and Instrument Drawings 1

1. M-12BMO1-Steam Generator Blowdown System 5 B. Classification Of Components 2 Details of the classification of the Steam Generator B lowdown System components for ISI 6 are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

0 6 C. Nonexempt and Exempt A.SME Class Components A listing of Nonexempt and Exempt ASME Class components are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Steam Generator Blowdown System. These drawings are part of the M-l 89-50 series.

1. M-189-50BM-01-01 Sheet I Steam Generator Blowdown Loop A &D

2. M-1 89-SOBM-01 -02 Sheet I Steam Generator Blowdown Loop B&C WCRE-1 6 4.1.6 Steam Generator Blowdown System (BM) Revision 0 Page I of 3

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.6 Steam Generator Blowdown System (BM)

E. Summary Of Components Subject To Section Xi and Augmented NDE/Scheduled For Examination Table I is a summary of the components and items subject to NDE per ASME Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the ISI Database.

TABLE I SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM PI P2 P3 INTERVAL PIPING WELDS SUBJECT - USAR 3.6.2 36 0 0 l 0 TO HELB l REQUIREMENTS_.l WCRE-16 4.1.6 Steam Generator Blowdown System (BM) Revision 0 Page 2 of 3

I1 WOLF CREEK GENERATING STATION A THIRD INTERVAL ISI PROGRAM PLAN E 4.1.6 Steam Generator Blowdown System (BM)

[I) 0 F. Augmented ISI Requirements The following Augmented ISI requirements apply to the Steam Generator Blowdown 2 System:

I. WCGS USAR Sections 3.6.1, Postulated Piping Failures In Fluid Systems Inside and 2 Outside Containment and 3.6.2, Determination Of Break Locations and Dynamic Effects Associated With The Postulated Rupture Of Piping- WCGS has implemented a Risk U Informed-High Energy Line Break program as an alternative to the examination o methodology of USNRC Branch Technical Position MEB 3-1. This program is maintained in WCRE-14 and is applicable to the piping within the "no break zone" associated with high energy piping in containment penetration areas. The "no break zone" is an area where pipe breaks were not postulated due to the stress levels being within limits specified in USAR Section 3.6.2. No welds in the BM system were selected under the RI-HELB program.

G. System Pressure Testing In accordance with Section Xl, IWA-5000 and IWC-5000, the Class 2 pressure retaining components within the Steam Generator Blowdown System will receive a system leakage test per IWC-5220 each inspection period.

Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Program The RI-IS] Program is not applicable to the BM system.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table BM-I (Period I Examinations), Table BM-2 (Period 2 Examinations),

and Table BM-3 (Period 3 Examinations). Because no components or component supports in the BM System have been selected or scheduled for examination, Tables BM-1, BM-2 and BM-3 are not included.

WCRE-16 4.1.6 Steam Generator Blowdown System (BM) Revision 0 Page 3 of 3

WOLF CREEK GENERATING STATION THIRD INTERVAL 1SI PROGRAM PLAN 4.1.7 Borated Refueling Water System (BN)

A. Applicable System Piping and Instrument Drawings

1. M-I2BNOI-Borated Refueling Water System B. Classification Of Compon( nts Details of the classification of the Borated Refueling Water System components for IS! are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

C. Nonexempt and Exempt ASME Class Components A listing of Nonexempt and Exempt ASME Class components are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and 1SI Equipment Drawings The following isometrics anI drawings detail the nonexempt components and items subject to NDE in the Borated Refueling Water System. These drawings are part of the M-189-50 series.

I M-189-50BN-0I-01 Sheet I Borated Refueling Water Storage Supply

2. M-189-5OBN-01Ol1 Sheet 2 Borated Refueling Water Storage Supply

3. M-189.50BN-0l-01 Sheet 3 Borated Refueling Water Storage Supply WCRE-16 4.1.7 Borated Refueling Water System (BN) Revision 0 Page I of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.7 Borated Refueling Water System (BN)

E. Summary Of Components Subject To Section Xi and Augmented NDE/Scheduled For Examination Table I is a summary of the components and items subject to NDE per ASME Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the ISI Database.

TABLE I SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM Pi P2 P3 INTERVAL PIPING WELDED C-C C3.20 -4 1 0 0O ATTACHMENTS PIPING WELDS NOT R-A RI.20 124 0 0 0 0 SUBJECT TO A DAMAGE Note I Note 1 MECHANISM PIPING COMPONENTSl F-A Fl.20 23 1 I l2l 4 SUPPORTS I l I I l_ __ l l Note 1: See Section H for an explanation of Category R-A and Item RI.xx nomenclature.

WCRE-16 4.1.7 Borated Refueling Water System (BN) Revision 0 Page 2 of 6

I WOLF CREEK GENERATING STATION M THIRD INTERVAL SI PROGRAM PLAN A

E 4.1.7 Borated Refueling Water System (BN)

F. Augmented ISI Requirements i

1 No Augmented ISI requirements apply to the Borated Refueling Water System.

/

G. System Pressure Testing In accordance with Section XI, IWA-5000 and ]WC-5000, the Class 2 pressure retaining components within the Borated Refueling Water System will receive a system leakage test per IWC-5220 each inspection period.

0

$3 Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Program A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class I and 2 piping welds at WCGS. This program is described in detail in Section 2.3.

No components in the BN system were selected for examination in the RI-ISI program.

1. Components and Component Supports Selected/Scheduled For Examination The components and compDnent supports selected for examination during Interval 3 are included in Table BN-I (Period I Examinations), Table BN-2 (Period 2 Examinations),

and Table BN-3 (Period 3 Examinations).

WCRE-1 6 4.1.7 Borated Refueling Water System (BN) Revision 0 Page 3 of 6

G>O5 go Ore cs>ra 7'.>31 WOLF CREEK GENERATING STATION THIRD INTERVAL [SI PROGRAM PLAN TABLE BN-1 l Period I Examinations I System: UNT I Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes BN-01-AOOI BNOI-01 SHT.2 INTEGRALPIPINGATTACHMENTS 14 PT C-C C3.20 BN-01-AOOI BN-01.01 SHT. 2 PIPING SUPPORT 14 VT-3 F-A F1.20 WCRE-16 4.1.7 Borated Refueling Water System (BN) Revision 0 Page 4 of 6

C;-,r-:> a:)=m WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BN- 2

[ Period 2 Examinations I System: BN I Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes BN-01-H003 BN-01-01 SHT. 1 PIPING SUPPORT 24 VT-3 F-A F1.20 WCRE-16 4.1.7 Borated Refueling Water System (BN) Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE BN-3 I Period 3 Examinations l ISystern: BN Relief Request Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block or Notes BN-01.R008 BN-01.01 SHT. 2 PIPING SUPPORT 8 VT-3 F-A F1.20 BN-01-ROOI BN4-011 SHlT. 3 PIPING SUPPORT 12 VT-3 F.A F1.20 WCRE-1 6 4.1.7 Borated Refueling Water System (BN) Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.8 Essential Service Water System (EF)

A. Applicable System Piping and Instrument Drawings

1. M-12EFOI-Essential Service Water System

2. M-12EF02-Essential Service Water System

3. M-K2EFOI-Essential Service Water System

4. M-K2EF03-Essential Service Water System B. Classification OrComponents Details of the classification of the Essential Service Water System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

C. Nonexempt and Exempt ASME Class Components A listing of Nonexempt and Exempt ASME Class components is included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Essential Service Water System. These drawings are part of the M-189-50 series.

1. M-189-5OEF-01-01 Sheet I Essential Service Water "A" Train Supply

2. M-189-SOEF-0-101 Sheet 2 Essential Service Water "A" Train Supply

3. M-189-5OEF-01-02 Sheet I Essential Service Water "A" Train Supply

4. M-189-5OEF-01-02 Sheet 2 Essential Service Water "A" Train Supply

5. M-189-50EF-01-03 Sheet I Essential Service Water "A" Train Return

6. M-189-SOEF-01-03 Sheet 2 Essential Service Water "A"Train Return

7. M-189-50EF-01-07 Sheet I Essential Service Water "A" Train Return

8. M-189-50EF-01-08 Sheet I Essential Service Water "A"Train Supply

9. M-189-5OEF-0I-09 Sheet I Essential Service Water Containment Cooling "A"Train Supply

10. M-189-50EF-01-10 Sheet I Essential Service Water Containment Cooling "A"Train Return I1. M-189-50EF-02-01 Sheet I Essential Service Water "B"Train Supply

12. M-1 89-5OEF-02-01 Sheet 2 Essential Service Water "B"Train Supply

13. M-189-50EF-02-01 Sheet 3 Essential Service Water "B"Train Return

14. M-189-SOEF-02-04 Sheet I Essential Service Water "B"Train Supply

15. M-1 89-SOEF-02-05 Sheet I Essential Service Water "B" Train Return

16. M-189-50EF-02-05 Sheet 2 Essential Service Water "B"Train Return

17. M-189-50EF-02-06 Sheet I Essential Service Water "B"Train Supply

18. M-189-50EF-02-08 Sheet I Essential Service Water "B"Train Supply

19. M-189-50EF-02-08 Sheet 2 Essential Service Water "B" Train Supply

20. M-189-50EF-02-09 Sheet I Essential Service Water Containment Cooling "B"Train Supply

21. M-189-5OEF-02-10 Sheet I Essential Service Water Containment Cooling "B"Train Return W'CRE-16 4.1.8 Essential Service Water System (EF) Revision 0 Page I of 6

C-1 t)r4=~nt -T-fl a:)

t? C D> -

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.8 Essential Service Water System (EF)

E. Summary OrComponents Subject To Section XI and Augmented NDE/Scheduled For Examination Table I is a summary of the components and items subject to NDE per ASME Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the ISI Database.

TABLE I SECTION Xi AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG, AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM PI P2 P3 INTERVAL PIPING WELDED C-C C3.20 4 0 1 0 ATTACHMENTS VESSEL WELDED D-A D1.10 . 4 1 1 0 2 ATTACHMENTS PIPING WELDED rl-A D!.20 2 2 2 2 S6-ATTACHMENTS PUMP WELDED ATTACHMENTS A 01.30 - 2 0 0 1 I PIPING COMPONENT F-A F 1.20 -3 0 I 0 I SUPPORTS PIPING COMPONENT F-A Fl.30 l 219 6 7 10 23 SUPPORTS EQUIPMENT SUPPORTS F-A F 1.40 - - 6 1 2 0 3 (Other Than Piping)

PIPING WELDS NOT R-A Rl.20 l l 26 0 0 0 0 SUBJECT TO A DAMAGE Note I Note I MECHANISM ____

Note 1: See Section H for an explanation of Category R-A and Item RI .xx nomenclature.

WCRE-16 4.1.8 Essential Service Water System (EF) Revision 0 Page 2 of 6

I WOLF CREEK GENERATING STATION M THIRD INTERVAL ISI PROGRAM PLAN A

G 4.1.8 Essential Service Water System (EF)

E F. Augmented ISI Requirements l0 1 No Augmented ISI requirements apply to the Essential Service Water System.

/2 G. System Pressure Testing S In accordance with Section XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining

/ components within the Essential Service Water System will receive a system leakage test per IWC-5220 each inspection period.

0 0 In accordance with Section Xl, IWA-5000 and IWD-5000, the Class 3 pressure retaining 6 components within the Essential Service Water System will receive a system leakage test per IWD-5221 every period and a system hydrostatic test per IWD-5222 at or near the end of the interval. As allowed by Code Case N-498-4, alternative rules may be employed in lieu of the system hydrostatic test of IWD-5222.

Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Progragm A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class I and 2 piping welds at WCCS. This program is described in detail in Section 2.3. Since the EPRI methodology used for the RI-ISI Program does not prescribe Code Examination Category and Item Numbers, the assignment of these designators is the same as utilized in Code Case N-578-1. No welds in the EF system were selected for examination in the RI-ISI program.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table EF-I (Period I Examinations), Table EF-2 (Period 2 Examinations),

and Table EF-3 (Period 3 Examinations).

WCRE-16 4.1.8 Essential Service Water System (EF) Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EF- I I Peniod I Examinationsl I System: EFl Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes FEF02A-SUPPORT-1 EF-01-01 SHT. 1 VESSEL INTEGRAL ATTACHMENTS 30 VTr-1 D-A D1.10 EF-01-C004 EF-01-03 SHT. 2 PIPING INTEGRAL ATTACHMENTS 30 VT-1 D-A D1.20 EF-01-C005 EF-02-01 SHT. 2 PIPING INTEGRAL ATTACHMENTS 30 VT-1 D-A D1.20 EF-01-C004 EF-01-03 SHT. 2 PIPING SUPPORT 30 VT-3 F-A F1.30 EF-07-C003 EF-01-08 PIPING SUPPORT 8 VT-3 F-A F1.30 K-EF-1 1-H007 EF-02-01 SHT. 1 PIPING SUPPORT 30 VT-3 F-A F1.30 EF-05-HOI1 EF-02-05 SHT. I PIPING SUPPORT 24 VT-3 F-A F1.30 EF-04-R009 EF-02-06 PIPING SUPPORT 14 VT-3 F-A F1.30 EF-08-C013 EF-02-08 SHT. I PIPING SUPPORT 8 VT-3 F-A F1.30 PEFO1A-SUPPORT-1 EF-01-01 SHT. 1 ESW PUMP A SUPPORT 30 VT-3 F-A F1.40 WCRE-1 6 4.1.8 Essential Service Water System (EF) Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EF- 2 l Penod 2 Examinationsl System: EF Relief Request or Component Name Drawing Number Component Description Size Thickness NOE Method Category Item Cal Block Notes GN-01-F036 EF-01-10 PIPING INTEGRAL ATTACHMENTS 14 PT C-C C3.20 FEF02A-SUPPORT-2 EF-01-01 SHT. 1 VESSEL INTEGRAL ATTACHMENTS 30 VT-1 D-A D1.10 EF-03-C004 EF-01-03 SHT. 1 PIPING INTEGRAL ATTACHMENTS 24 VT-1 D-A D1.20 EF46-A014 EF-02-06 PIPING INTEGRAL ATTACHMENTS 8 VT-1 D-A D1.20 EF-02-R017 EF-01-09 PIPING SUPPORT 14 VT-3 F-A F1.20 EF-06-C026 EF-01-02 SHT. 2 PIPING SUPPORT 8 VT-3 F-A F1.30 EF-03-C004 EF-01-03 SHT. 1 PIPING SUPPORT 24 VT-3 F-A F1.30 EF-03-*1004 EF-01-03 SHT. 2 PIPING SUPPORT 16 VT-3 F-A F1.30 EF-03-R004 EF-01-03 SHT. 2 PIPING SUPPORT 14 VT-3 F-A F1.30 EF-08-001 EF-01-07 PIPING SUPPORT 8 VT-3 F-A F1.30 EF-05-R005 EF-02-05 SHT. i PIPING SUPPORT 24 VT-3 F-A F1.30 EF4-6-A014 EF-02-06 PIPING SUPPORT 8 VT-3 F-A F1.30 FEF02A-SUPPORT-1 EF-41-01 SHT. 1 VESSEL SUPPORT 30 VT-3 F-A F1.40 FEF02A-SUPPORT-2 EF-014-1 SHT. 1 VESSEL SUPPORT 30 VT-3 F-A F1.40 WCRE-16 4.1.8 Essential Service Water System (EF) Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL IS PROGRAM PLAN TABLE EF- 3 I Period 3 Examinations I System: EFl Relief Request Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block or Notes EF-03-R021 EF-01-03 SHT. 1 PIPING INTEGRALATTACHMENTS 24 VT-1 D-A D1.20 EF-03-C016 EF-01-03 SHT. 2 PIPING INTEGRAL ATTACHMENTS 8 VT-1 0-A D1.20 PEF01A-SUPPORT-1 EF-1-01 SHT. 1 ESW PUMP INTEGRAL ATTACHMENT 30 VT-1 D-A D1.30 K-EF-1 1-ROI EF-01-01 SHT. I PIPING SUPPORT 30 VT-3 F-A F1.30 K-EF-11 -R003 EF-014-1 SHT. 1 PIPING SUPPORT 30 VT-3 F-A F1.30 K-EF-1 1-R005 EF-01-01 SHT. 1 PIPING SUPPORT 30 VT-3 F-A F1.30 EF-01-C002 EF-01-01 SHT. 2 PIPING SUPPORT 30 VT-3 F-A F1.30 EF-02-AOIO EF-01-01 SHT. 2 PIPING SUPPORT 18 VT-3 F-A F1.30 EF-03-R021 EF-01-C3 SHT. 1 PIPING SUPPORT 24 VT-3 F-A F1.30 EF-03-C016 EF-014-3 SHT. 2 PIPING SUPPORT 8 VT-3 F-A F1.30 EF-07-C009 EF-01-07 PIPING SUPPORT 8 VT-3 F-A F1.30 EF-05-RO1 3 EF-02-05 SHT. 1 PIPING SUPPORT 24 VT-3 F-A F1.30 EF46H-001 EF-02-06 PIPING SUPPORT 8 VT-3 F-A F1.30 WCRE-16 4.1.8 Essential Service Water System (EF) Revision 0 Page6of6

I WOLF CREEK GENERATING STATION 11.' THIRD INTERVAL ISI PROGRAM PLAN A

G 4.1.9 Component Cooling Water System (EG)

E 1) 0 A. Applicable System Piping and Instrument Drawings 1

1. M-12EGOI-Component Cooling Water System

2. M-12EG02-Component Cooling Water System

3. M-12EG03-Component Cooling Water System

/2 B. Classification or Components 0 Details of the classification of the Component Cooling Water System components for ISI 0 are included in "Inservice Inspection Classification Basis Document Wolf Creek 6 Generating Station Interval 3".

C. Nonexempt and Exempt ASME Class Components A listing of Noncxempt and Exempt ASME Class components is included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Component CDoling Water System. These drawings are part of the M-189-50 series.

1. M-189-50EG-01-01 Sheet I Component Cooling Water "A"Train CCW Heat Exchanger

2. M-189-50EG-01-02 Sheet I Component Cooling Water "A"Train Supply

3. M-189-50EG-01-02 Sheet 2 Component Cooling Water "A" Train Return

4. M-189-50EG-02-03 Sheet I Component Cooling Water "B"Train CCW Heat Exchanger

5. M-189-50EG-02-03 Sheet 2 Component Cooling Water "B" Train

6. M-189-50EG-02-05 Sheet I Component Cooling Water "B"Train Return

7. M-1 89-50EG-02-05 Sheet 2 Component Cooling Water "B" Train Supply

8. M-189-50EG-03-06 Sheet I Component Cooling Water Common Header

9. M- 189-50EG-03-07 Sheet I Component Cooling Water Common Header

10. M-189-50EG-04-01 Sheet I Component Cooling Water RHR Heat Exchanger Supply I. M-189-50EG-04-01 Sheet 2 Component Cooling Water RHR Heat Exchanger Return

12. M-189-50EG-05-06 Sheet I Component Cooling Water Letdown Heat Exchanger Supply

13. M-189-50EG-05-06 Sheet 2 Component Cooling Water Letdown Heat Exchanger Return

14. M-189-50EG-06-09 Sheet I Component Cooling Water RCP "B"&

"C" Supply

15. M-189-50EG-06-09 Sheet 2 Component Cooling Water RCP Return WCRE-16 4.1.9 Component Cooling Water System (EG) Revision 0 Page I of 6

C;,{cwr-s ~mc>

WOLF CRFFK GENERATING STATION THIRD INTERVAL IS PROGRAM PLAN 4.1.9 Component Cooling Water System (EG)

E. Summary Of Components Subject To Section Xi and Augmented NDEIScheduled For Examination Table I is a summary of the components and items subject to NDE per ASME Section Xi or per Augmented requirements. A detailed listing of these components and items is maintained in the ISI Database.

TABLE I COMPONENT OR ITEM DESCRIPTION SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE CODE CATEGORY CODE ITEM NO.

AUG.

CATEGORY AUG ITEM NO.

TOTAL IN SYSTEM PI EXAM' P2 I

VESSEL WELDED D-A D1.10 . 10 4 2 ATTACHMENTS PIPING WELDED D-A DI.20 58 2 2 ATTACHMENTS prn,,nin flfTfl~l

%.n^ A~Sr 0.C rariu ,J~v~rOJNL. I r- I.JU 0

- 2 6 3 U SUPPORTS l ll EQUIPMENT SUPPORTS F-A FI.40 20 4 2 (OTHER THAN PIPING) I WCRE-16 4.1.9 Component Cooling Water System (EG) Revision 0 Page 2 of 6

I WOLF CREEK GENERATING STATION A

11 THIRD INTERVAL IS1 PROGRAM PLAN G

E 4.1.9 Component Cooling Water System (EG) 0 F. Augmented ISI Requirements 1

No Augmented ISI requirements apply to the Component Cooling Water System.

G. System Pressure Testing 5

In accordance with Section Xl, IWA-5000 and IWD-5000, the Class 3 pressure retaining

/ components within the Component Cooling Water System will receive a system leakage test per IWD-522 1 every period and a system hydrostatic test per IWD-5222 at or near 0 the end of the interval. As allowed by Code Case N4984, alternative rules may be 6 employed in lieu of the system hydrostatic test of IWD-5222.

Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Program The RMISI Program is not applicable to the EG system.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table EG-1 (Period I Examinations), Table EG-2 (Period 2 Examinations),

and Table EG-3 (Period 3 Examinations).

WCRE-l 6 4.1.9 Component Cooling Water System (EG) Revision 0 Page 3 of 6

csO~lMC)>-=m-.

WOLF CREEK GENERATING STATION THIRD INTERVAL IST PROGRAM PLAN TABLE EG-1 I Period 1 Examinations I System: EG I Component Name Drawing Number Component Descriptilon Size Thickness NDE Method Category Item Relief Request Notes EEGO1A-SUP.1 EG-01-01 CCW HX INTEGRAL ATTACHMENT VT-1 D-A 01.10 EEGOIA-SUP-2 EG-01-01 CCW HX INTEGRAL ATTACHMENT VT-1 0-A D1.10 EEG0IA-SUP-3 EG-01-01 CCW HX INTEGRAL ATTACHMENT VT-t D-A D1.10 EEGO1A-SUPA EG-01-01 CCW HX INTEGRAL ATTACHMENT VT-1 D-A D1.10 EG-01.R023 EG-01-01 PIPING INTEGRAL ATTACHMENTS 20 VT-1 D-A 01.20 EG-02-A005 EG-01-02 SHT. 1 PIPING INTEGRAL ATTACHMENT 12 VT-1 D-A D1.20 EG-01-R023 EG-01-01 PIPING SUPPORT 20 VT-3 F-A F1.30 EG-02-A005 EG-01-02 SHT. I PIPING SUPPORT 12 VT-3 F-A F1.30 EG-18-R005 EG-02-05 SHT. 1 PIPING SUPPORT 12 VT-3 F-A F1.30 EG-06-C006 EG-03-06 PIPING SUPPORT 18 VT-3 F-A F1.30 EG-46-H002 EG-03-06 PIPING SUPPORT 12 VT-3 F-A F1.30 EG-MO-t001 EG-06-09 SHT. 1 PIPING SUPPORT 10 VT-3 F-A F1.30 EG-14-H001 EG-06-09 SHT. I PIPING SUPPORT 8 VT-3 F-A F1.30 EG-13-CO09 EG-06-09 SHT. 2 PIPING SUPPORT 6 VT-3 F-A F1.30 EEGOIA-SUP-1 EG-01-01 CCW HX SUPPORT VT-3 F-A F1.40 EEGOIA-SUP-2 EG-01-01 CCW HX SUPPORT VT-3 F-A F1.40 EEGO1A-SUP-3 EG-01-01 CCW HX SUPPORT VT-3 F-A F1.40 EEGOIA-SUP-4 EG-01-01 CCW HX SUPPORT VT-3 F-A F1.40 WCRE-16 4.1.9 Component Cooling Water System (EG) Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EG-2 l Period 2 Examinationsl I System: EG I Component Name Drawing Number Component Description Size Thidcness NDE Method Category Item Relief Request Notes EBGO1-SUPPORT-1 EG-05-06 LETDOWN HX INTEGRAL ATTACHMENT VT-1 D-A D1.10 EBG01-SUPPORT-2 EG-05-06 LETDOWN HX INTEGRAL ATTACHMENT VT-1 D-A D1.10 EG-04-AOOI EG-04-01 SHT. 2 PIPING INTEGRAL ATTACHMENTS 18 VT-1 D-A D1.20 EG-06-C016 EG-05-06 SHT. 1 PIPING INTEGRAL ATTACHMENT 6 VT.1 D-A D1.20 EC-18i-COO EG-01-02 SHT. I PIPING SUPPORT 12 VT-3 F-A F1.30 EG-05-C003 EG-02-05 SHT. 1 PIPING SUPPORT 12 VT-3 F-A F1.30 EG-07-C003 EG-03-07 PIPING SUPPORT 12 VT-3 F-A F1.30 EG-04-HW07 EG-04-01 SHT. 1 PIPING SUPPORT 18 Vr-3 F-A F1.30 EG-04-AWOi EG-04-01 SHT. 2 PIPING SUPPORT 18 VT-3 F-A F1.30 EG-04-C009 EG-04-01 SHT. 2 PIPING SUPPORT 18 VT-3 F-A F1.30 EG-06-C016 EG-0-06 SHT. I PIPING SUPPORT 6 VT-3 F-A F1.30 EG-09-C002 EG-06-09 SHT. 2 PIPING SUPPORT 10 VT-3 F-A F1.30 EG-17-R009 EG-06-09 SHT. 2 PIPING SUPPORT 6 VT-3 F-A F1.30 EBGO1-SUPPORT-1 EG-05-06 LETDOWN HX SUPPORT VT-3 F-A F1.40 EBGOI-SUPPORT-2 EG-05-06 LETDOWN HX SUPPORT VT-3 F-A F1.40 WCRE-1 6 4.1.9 Component Cooling Water System (EG) Revision 0 PageS of6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EG. 3 I Period 3 Examinations]

I Systern: EG I Component Name Drawinq Number Component Desiotion Size Thickness NDE Method Category Item RerietReouest Notes EG-07-C021 EG-03-07 PIPING INTEGRAL ATTACHMENT 12 VT-1 D-A D1.20 EG-01-COOI EG-01-01 PIPING INTEGRAL ATTACHMENTS 20 VT-1 D-A D1.20 EG-02-H005 EG-01-02 SHT. 1 PIPING SUPPORT 12 VT-3 F-A F1.30 EG-1 8-H003 EG-0142 SHT. 2 PIPING SUPPORT 12 VT-3 F-A F1.30 EG-03-H005 EG-02-03 SHT. 2 PIPING SUPPORT 20 Vr-3 F-A F1.30 EG-05-COO1 EG-02-05 SHT. I PIPING SUPPORT 12 VT-3 F-A F1.30 EG-1 8-H006 EG-02-05 SHT. I PIPING SUPPORT 12 VT-3 F-A F1.30 EG-07-C021 EG-03-07 PIPING SUPPORT 12 VT-3 F-A Fi.30 EG-01-Cool EG-01-01 PIPING SUPPORT 20 VT-3 F-A F1.30 EG-0R004 EG-09 SHT. 1 PIPING SUPPORT 10 VT-3 F-A F1.30 EG-12-C004 EG4-6-09 SHT. I PIPING SUPPORT 8 VT-3 F-A F1.30 EG-07-R026 EG-03-07 PIPING SUPPORT 12 VT-3 F-A F1.30 PEGOIA-SUP-1 EG-01-01 PUMP SUPPORT 18 VT-3 F-A F1.40 EECO1A-SUP-1 EG-01-02 SHT. I FUEL POOL COOLING HX SUPPORT VT.3 F-A F1.40 EECOIA-SUP-2 EG-01-02 SHT. 1 FUEL POOL COOUNG HX SUPPORT VT-3 F-A F1.40 EECOIA-SUP.3 EG-01-02 SHT. i FUEL POOL COOUNG HX SUPPORT VT-3 F-A F1.40 WCRE-16 4.1.9 Component Cooling Water System (EG) Revision 0 Page 6 of 6

II WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN A

G 4.1.10 Residual Heat Removal System (EJ)

E DI A. Applicable System Piping and Instrument Drawings 0

1k 1. M-12EJOI-Residual Heat Removal System 2

B. Classification Of Components Details of the classification of the Residual Heat Removal System components for ISI are 2 included in "Inservice Inspection Classification Basis Document Wolf Creek Generating 0 Station Interval 3".

0 (B C. Nonexempt and Exempt ASME Class Components A listing of Nonexempt and Exempt ASME Class components is included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Residual Heat Removal System. These drawings are part of the M-189-50 series.

1. M-189-SOEJ-Ol-Ol Sheet I Residual Heat Removal "A" Train RHR Pump Suction

2. M-189-50E0-01-01 Sheet 2 Residual Heat Removal "A"Train RHR Pump Discharge

3. M-189-SOEJ-O-01 Sheet 3 Residual Heat Removal "A"Train RHR Pump Suction

4. M-189-501E1-0-01 Sheet 4 Residual Heat Removal "A"Train RHR Pump Discharge to Safety Injection

5. M-189-50EJ-01-0I Sheet 5 Residual Heat Removal Return to Refueling Water Storage Tank

6. M-189-5OEJ-01-04 Sheet I Residual Heat Removal "A" Train RHR Pump Suction

7. M- 189-5OEJ-02-02 Sheet I Residual Heat Removal "B"Train RHR Pump Suction

8. M-189-50EJ-02-02 Sheet 2 Residual Heat Removal "B" Train RHR Pump Discharge

9. M-1 89-50EJ-02-02 Sheet 3 Residual Heat Removal "B" Train RHR Pump Suction

10. M-189-50EJ-02-02 Sheet 4 Residual Heat Removal "B" Train RHR Pump Discharge to Safety Injection I. M-1 89-50EJ-02-02 Sheet 5 Residual Heat Removal "B" Train RHR Pump Discharge to Safety Injection

12. M-189-SOEJ-02-04 Sheet I Residual Heat Removal "B"Train RHR Pump Suction WCRE-16 4.1.10 Residual Heat Removal System (El) Revision 0 Page I of 15

I WOLF CREEK GENERATING STATION M THIRD INTERVAL ISI PROGRAM PLAN A

G D. Applicable ISI Isometrics and ISI Equipment Drawings (Cont'd)

E

13. M-189.S0EJ.02-04 Sheet 2 Residual Heat Removal "B" Train RHR Pump Discharge to Accumulator Injection

14. M-1 89-50EJ-02.04 Sheet 3 Residual Heat Removal "B" Train RHR Pump

1) Discharge to Safety Injection Loop No. 2 & 3

15. M-189-501SI-EEJOIA Sheet I RHR Heat Exchanger "A" EEJO IA JIL

16. M-189-501SI-EEJOIB Sheet I RHR Heat Exchanger "B" EEJOIB 2

c) 17. M-189-501SI-PUMPS Sheet 1 ISI Pumps 0

6 WCRE-16 4.1.10 Residual Heat Removal System (EJ) Revision 0 Page 2 of 15

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.10 Residual Heat Removal System (EJ)

E. Summary Of Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table I is a summary of the components and items subject to NDE per ASME Section Xl or per Augmented requirements. A detailed listing of these components and items is maintained inthe ISI Database.

TABLE I SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM PI P2 P3 INTERVAL PRESSURE RETAINING B-G-2 B7.70 6 1 0 2 3 BOLTING-VALVES Note I VALVE BODY B-M-2 B12.50 6 *

• 3 3 EXCEEDING NPS 4 See Paragraph I,Note 2 PRESSURE RETAINING C-A C.I0 2 0 0 I VESSEL WELDS-SHELL PRESSURE RETAINING C-A C1.20 . 2 0 0 1 VESSEL WELDS-CIRC.

PRESSURE RETAINING C-B C2.33 4 0 1 1 2 NOZZLE WELDS-VES.

VESSEL WELDED C-C C3.10 2 0 0 1 1 ATTACHMENTS PIPING WELDED C-C C3.20 46 2 I 2 S ATTACHMENTS PUMP WELDED C-C C3.30 6 0 0 1I ATTACHMENTS PRESSURE RETAINING C-G C6.10 2 1 0 0 PUMP WELDS VESSEL WELDED D-A D1.10 10 0 3 2 S ATTACHMENTS PIPING COMPONENTS F-A F1.10 13 1 2 2 5 SUPPORTS I ,

WCRE-16 4.1.10 Residual Heat Removal System (EJ) Revision 0 Paae 3 of I5

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE I SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM Pt P2 P3 INTERVAL PIPING COMPONENTS F-A F1.20 132 7 7 8 22 SUPPORTS EQUIPMENT SUPPORTS F-A FI.40 18 3 3 3 9 (OTHER THAN PIPING) l PIPING WELDS SUBJECT R-A RI.1 I 18 0 0 6 6 TO THERMAL FATIGUE Note 2 Note 2 PIPING WELDS NOT R-A R1.20 506 is 14 18 47 SUBJECT TO A DAMAGE .

MECHANISM Note 2 Note 2 ___

Note *: Ex^.n ti orf PDressu.. o,..:g B"odi.n is pIo a edGI acordaince with Code Case 14-652. See Note in Paragmaph i for selection and sch eduing criteria.

Note 2: See Section H for an explanation of Category R-A and Item RI .xx nomenclature.

WCRE-16 4.1.10 Residual Heat Removal System (EJ) Revision 0 Pawe 4 of 15

WOLF CREEK GENERATING STATION THIRD INTERVAL 1SI PROGRAM PLAN A

E 4.1.10 Residual Heat Removal System (EJ)

E F. Augmented IS Requirements No Augmented ISI requirements apply to the Residual Heat Removal System.

G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWB-5000, the Class I pressure retaining components within the Residual Heat Removal System will receive a system leakage test per IWB-5220 prior to plant startup following each refueling outage.

o3 6

In accordance with Section XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining components within the Residual Heat Removal System will receive a system leakage test per IWC-5220 each inspection period.

Procedures used to perform System Piessure Testing are listed in Table 4.2.1 IH. Risk Informed ISI Program A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class I and 2 piping welds at WCGS. This program is described in detail in Section 2.3. Residual Heat Removal System welds selected for examination per the RI-ISI program are listed in Tables EJ-I, EJ-2 and EJ-3. Since the EPRI methodology used for the RI-ISI Program does not prescribe Code Examination Category and Item Numbers, guidance was taken from Code Case N-578-1 for the assignment of these designators.

When a specific degradation mechanism (DM) exists at a selected location, then the volume to be examined shall be as recommended in Section 4 of EPRI TR-l 12657 Rev. B-A. Welds subject to a DM are identified by a note in the Table. Welds selected that have no associated DM shall have the volume examined as shown in Figures 4.1-4 of TR-I 12657 Rev. B-A.

Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table EJ-I (Period I Examinations), Table EJ-2 (Period 2 Examinations), and Table EJ-3 (Period 3 Examinations). The following Notes apply to the tables:

I. Bolting is required to be examined only when a connection is disassembled or bolting is removed. For valves, examination of bolting is required only when the component is examined under Examination Category B-M-2. Examination of bolted connection is required only once during the interval. See Code Case N-652, Category B-G-2, Notes I and 2.

2. Examination of the valve internal surface is required only when a valve is disassembled for maintenance, repair, or volumetric examination. To aid in scheduling, the valve has been included in each inspection period. However, examination will be performed only once during the inspection interval and is limited to one valve within a group of valves that are the same size, constructional design, and manufacturing methods and which performs a similar function in the system. Examination may be alternatively performed on another valve within the group.

If a valve has not been disassembled, examination is deferrable to subsequent periods.

(Reference PIR 97-2539)

3. These welds have been selected per the RI-ISI Program. The requirements for examination of these welds are included in Paragraph H above.

4. These welds have Thermal Fatigue identified as the degradation mechanism.

WCRE-16 4.1.10 Residual Heat Removal System (EJ) Revision 0 Page 5 of 15

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EJ.1 Period I Examinations System: EJ I Relief Request or Component Name Drawing Number Component Description Size ThIcknesss NDE Method Category Item Cal Block Notes EJ-04-BB-PV-8702A-b EJ-01-04 VALVE PVW8702A BOLTI NG 12 VT 1 B-G-2 87.70 1 EJ-04-BB-PV-8702A-SURF EJ-01-04 VALVE PV-8702A INTER HNAL PRESSURE SURFACE 12 VT-3 B-M-2 B12.50 2 EJ-04-HV-870IA-SURF EJ-01-04 VALVE HV-8701A INTERtNAL PRESSURE SURFACE 12 VT-3 B-M-2 812.50 2 EJ-04-8841A-SURF EJ-02-04 SHT. 3 VALVE 8841A INTERNAtL PRESSURE SURFACE 6 VT-3 B-M-2 812.50 2 DDIItNSCCI-f OAl AYrV E.jI.Q.AOf2 Ej-01 -1 ST. 4 ...... ~, ....._-ntis .rt

_._.1 a PT C-C C3.20 EJ-04-R008 EJ-02-04 SHT. 3 PIPING INTEGRAL ATVikCHMENTS 6 PT C-C C3.20 PEJOIA-F-2 EJ-01-01 SHT. 2 RHR PUMP A FLANGE 1r0 PUMP CASING WELD 8 0.322 PT C-G C6.10 EJ-04-C021 EJ-01-04 PIPING SUPPORT 12 VT-3 F-A F1.10 EJ-01-H013 EJ-01-01 SHT. 3 PIPING SUPPORT 10 vr-3 F-A F1.20 EJ-01.H014 EJ-01-01 SHT, 4 PIPING SUPPORT 10 VT-3 F-A F1.20 EJ-04-A002 EJ-01-01 SHT. 4 PIPING SUPPORT 6 VT-3 F-A F1.20 EJ-04-C013 EJ-01-01 SHT. 4 PIPING SUPPORT 6 VT-3 F-A F1.20 EJ-03-C007 EJ-02-02 SHT. 3 PIPING SUPPORT 8 VT-3 F-A F1.20 EJ-03-RO15 EJ-02-02 SHT. 3 PIPING SUPPORT B VT-3 F-A F1.20 WCRE-16 4.1.10 Residual Heat Removal System (EJ) Revision 0 Page 6 of 15

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EJ- 1 SeriodTI Examinaoiens b ystem: EJ- I Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes EJ-04-R008 EJ-02-04 SHT. 3 PIPING SUPPORT 6 VT-3 F-A F1.20 PEJOIA-SUP-1 EJ-01-01 SHT. 2 RHR PUMP A SUPPORT 8 0.322 VT-3 F-A F1.40 PEJO1A-SUP-2 EJ-01-01 SHT. 2 RHR PUMP A SUPPORT 8 0.322 VT-3 F-A F1.40 PEJOiA.SUP-3 EJ-01-01 SHT. 2 RHR PUMP A SUPPORT 8 0.322 VT-3 F-A F1.40 E,-u2-J- 3'n7. i ao rnrc *v i< cLCNVt 12 1..25 U. R-A Ri1.20 i26 3 EJ-01-FW342 EJ-01-41 SHT. 4 10^ ELBOW TO 10 PIPE 10 0.365 UT R-A R1.20 204 3 EJ-01-FW343 EJ-014-1 SHT. 4 10^ PIPE TO 10 ELBOW 10 0.365 UT R-A R1.20 204 3 EJ-01-S025-B EJ-01-01 SHT. 5 I OPIPE TO 10 ELBOW 10 0.365 UT R-A R1 .20 204 3 EJ-04-FW312 EJ-01-01 SHT. 4 6- PIPE TO 10 X 10 X 6"l TEE 6 0.719 UT R-A R1.20 117 3 EJ-01-S025-C EJ-01-41 SHT. 5 10" ELBOW TO 10^ PIPE 10 0.365 UT R-A R1.20 204 3 EJ-02-FW339 EJ-02-02 SHT. 2 10^X 8-REDUCER TO 10^'PIPE 10 0.365 UT R-A RI.20 204 3 EJ-02-S034-C EJ-02-02 SHT. 4 10 PIPE TO 10 ELBOW 10 0.365 UT R-A R1.20 204 3 EJ-02-S034-D EJ-02-02 SHT. 4 10 ELBOWTO 10 PIPE 10 0.365 UT R-A R1.20 204 3 EJ-04-S025-B EJ-01-01 SHT. 4 10^X 10-X 6 TO 10PIPE 10 1 UT R-A R1.20 122 3 E-01 -FW358 EJ-01-01 SHT. 2 8- FLANGE TO 8" PIPE 8 0.322 UT R-A R1.20 203 3 WCRE-16 4.1.10 Residual Heat Removal System (EJ) Revision 0 Page 7 of 15

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EJ.

I Period I Examinations System: W Relief Request or Component Name Drawing Number Component Description Size Thicknes S NDE Method Category Item Cal Block Notes EJ-01-S01-S EJ-01-01 SHT. 3 6" PIPE TO 8' EL8OW 8 0.322 UT R-A R1.20 203 3 EJ-41-S016-C EJ-01-01 SHT. 3 8" ELBOW TO 8" PIPE 8 0.322 UT R-A R1.20 203 3 EJ-03-S003-F EJ-02402 SHT. 3 8" ELBOWTO 8" PIPE 8 0.322 UT R-A R1.20 203 3 EJ-03-S003-H EJ-02-02 SIT. 3 8" ELBOW TO 8" PIPE 8 0.322 UT R-A R1.20 203 3 WCREI16 4.1.10 Residual Heat Removal System (EJ) Revision 0 Page 8 of 15

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EJ- 2 l Period 2 Examinations I Systern: EJ I Relief Request or Component Name Drawing Number Component Descriplion Size Thickness NDE Method Category Item Cal Block Notes EJ-04-4B-PV-8702A-SURF EJ-01-04 VALVE PV-8702A INTERNAL PRESSURE SURFACE 12 VT-3 B-M-2 B12.50 2 EJ-04-HW-87OIA-SURF EJ-01-04 VALVE HV-8701A INTERNAL PRESSURE SURFACE 12 VT-3 B-M-2 B12.50 2 EJ-04-41A-SURF EJ-02-04 SHT. 3 VALVE 8841A INTERNAL PRESSURE SURFACE 6 VT-3 B-M-2 B12.50 2 EEJ01A-NB-1 ISI-EEJ01A SHT. 1 NOZZLE B TO SHELL WELD (OUTLET) VT-2 C-B C2.33 EJ-03-R006 EJ-02-02 SHT. 3 PIPING INTEGRAL ATTACHMENT 8 PT C-C C3.20 EEJOIA-SUP-3 ISI-EEJ01A SHT. I SUPPORT LUG TO SHELL WELD VT-1 D-A D1.10 EEJOIA-SUP-4 ISI-EEJOIA SHT. 1 SUPPORT LUG TO SHELL WELD D-A D1.10 EEJOIA-SUP-5 ISI-EEJ01A SI-IT. 1 SUPPORT LUG TO HEAD WELD (HEAD) VT-1 D-A D1.10 EJ434-ROI8 EJ-OS-04 PIPING SUPPORT 12 VT-3 F-A F1.10 EJ-04-R012 EJ-02-04 SHT. i PIPING SUPPORT 12 VT-3 F-A F1.10 EJ-01-HOO EJ1-01-O SHT. I PIPING SUPPORT 14 VT-3 F-A F1.20 EJ-01-R029 EJ4-1-01 SHT. 4 PIPING SUPPORT 10 VT-3 F-A F1.20 EJ-04-H002 EJ-01-01 SHT. 4 PIPING SUPPORT 10 VT-3 F-A F1.20 EJ-02-R027 EJ-02-02 SHT. 2 PIPING SUPPORT 10 VT-3 F-A F1.20 WCRE-16 4.1.10 Residual Heat Ritmoval System (EJ) Revision 0 Page 9c of 15

WOLF CREEK GENERATING STATION THIRD INTERVAL lSI PROGRAM PLAN TABLE EJ- 2

[ Penod 2 Examinationsl I System: EJl Relief Request or Component Name DrawiAng Number Component Description Size Thickness NDE Method Category Item Cal Block Notes EJ-03-RW05 EJ-02-02 SHT. 3 PIPING SUPPORT 8 VT-3 F-A F1.20 EJ403-RW06 EJ-02-02 SHT. 3 PIPING SUPPORT 8 VT-3 F-A F1.20 EJ-02-RO1 2 EJ-02-04 SI-T. I PIPING SUPPORT 12 VT-3 F-A F1.20 EEJOIA-SUP-3 ISI-EEJOiA SHT. 1 RHR HX SUPPORT VT-3 F-A F1.40 EEJ01A-SUP-4 ISI-EEJO1A SHT. 1 RHR HX SUPPORT VT-3 F-A F1.40 EEJ01A-SUP-5 ISI-EEJO1A SHT. 1 RHR HX SUPPORT VT-3 F-A Fi.40 EJ-04-F034 EJ-04104 12" PIPE TO 12" ELBOW 12 1.125 UT R-A R1.20 126 3 EJ-02-SW08-B EJ-02-02 SHT. I 14" ELBOWTO 14 PIPE 14 0.438 UT R-A R1.20 192 3 EJ-02-FW31 7 EJ-02-04 SHT. I 12'ELBOWTO 12-PIPE 12 0.375 UT R-A R1.20 183 3 EJ-02-SOO1-C EJ-02-04 SHT. I 12" PIPE TO 12" ELBOW 12 0.375 UT R-A R1.20 183 3 EJ-04-FO1 9 EJ-02-04 SHT. I 12 PIPE TO 12- PIPE 12 0.5 UT R-A R1.20 128 3 EJ-01-S01 8-B EJ-01-01 SHT. 3 10"X 10"X 10"TEETO 10"PIPE 10 0.365 UT R-A R1.20 204 3 EJ-01-SO18-C EJ-01-01 SHT. 3 10- PIPE TO 10 X 8 REDUCER 10 0.365 UT R-A R1.20 204 3 EJ-01-S024-D EJ-01-01 SHT.4 10' PIPE TO 10"TEE 10 0.365 UT R-A R1.20 204 3 WCRE-I 6 4.1.I( OResidual Heat Removal System (EJ) Revision 0 Page 10 of 15

WOLF CREEK GENERATING STATION THIRD INTERVAL IS] PROGRAM PLAN TABLE EJ- 2 1 Period 2 Examinationsl ISystem: EJ- I Relref Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category item Cal Block Notes EJ-01-S024-F EJ-01-01 SHT. 4 10" TEE TO 1O" PIPE 10 0.365 UT R-A R1.20 204 3 EJ-02-F050 EJ-02-02 SHT. 5 1IOPIPE TO 10" ELBOW 10 0.365 UT R-A R1.20 204 3 EJ-02-S022-B EJ-02-02 SHT. 3 10" PIPE TO 10WX 10'X 8TEE 10 0.365 UT R-A R1.20 204 3 EJ-02-S022-D EJ-02-02 SHT. 3 10"X 10"X8'TEETO10'PIPE 10 0.365 UT R-A R1.20 204 3 EJ-02-S045-B EJ-02-02 SHT. 5 10OELBOWTO 10' PIPE 10 0.365 UT R-A R1.20 204 3 EJ-02-FW311 EJ-02-02 SHT. 3 8"PIPE TO 10X 10X8'TEE 8 0.322 UT R-A R1.20 203 3 WCRE-16 4.1.10 Residual Heat Removal System (EJ) Revision 0 Page 11 of 15

WOLF CREEK GENERATING STATION THIRD INTERVAL 1SI PROGRAM PLAN TABLE EJ- 3 l Period 3 Examinationsl I System: EJ I Relief Request or Component Name Drawing Number Component Description Sze Thickness NDE Method Category Item Cal Block Notes EJ-04-HV-8701A-b EJ-01-04 VALVE HV-8701A BOLTING 12 VT-1 B-G-2 B7.70 I

EJ-04-8841A b EJ-02-04 SHT. 3 VALVE 8841A BOLTING 6 B-G-2 B7.70 2

EJ-04-BB.PV-8702A-SURF EJ-01-04 VALVE PV-8702A INTERNAL PRESSURE SURFACE 12 VT-3 B4M-2 B12.50 2

EJ-04-HV-8701A-SURF EJ-01-04 VALVE HV-8701A INTERNAL PRESSURE SURFACE 12 B-M-2 B12.50 2

EJ-04-8841A-SURF EJ-02-04 SHT. 3 VALVE 8841A INTERNAL PRESSURE SURFACE 6 VT-3 BM-2 B12.50 EEJO1A-SEAM-1-W ISI-EEJO0ASHT. I BONNET FLANGETO CHANNEL WELD NA 0.88 UT C-A C1.10 172 EEJD1A-SEAM-2-W ISI-EEJOIASHT. 1 CHANNELTOHEADWELD NA 0.88 UT C-A C1.20 172 EEJOIA.NA.1 ISI.EEJOIA SHT. 1 NOZZLE A TO SHELL WELD (INLET) VT-2 C-B C2.33 EEJO1A-SKIRT-W ISI-EEJO1A SHT. 1 SUPPORT SKIRT WELD PT C-C C3.10 EJ-01-C015 EJ-O1.01 SHT. 3 PIPING INTEGRAL ATTACHMENTS 8 PT C-C C3.20 EJ-02-C012 EJ-02-02 SHT. 4 PIPING INTEGRAL ATTACHMENTS (8 LUGS) 10 PT C-C C3.20 PEJO1A-SUP-1 EJ-01-01 SHT. 2 RHR PUMP A INTEGRALLY WELDED ATTACHMENTS B PT C-C C3.30 EEJOIA-SUP-1 ISI-EEJ01A SHT. 1 SUPPORT LUG TO SHELL WELD VT-1 0-A 01.10 EEJOIA-SUP-2 ISI-EEJOIA SHT. 1 SUPPORT LUG TO SHELL WELD VT-1 D-A 01.10 WCRE-16 4.1.10 Residual Heat Removal System (EJ) Revision 0 Page 12 of 15

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EJ- 3 l Period 3 Examinationsl lISystem: EJ r Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes EJ-04-H007 EJ-01-04 PIPING SUPPORT 12 VT-3 F-A F1.10 EJ-04-C020 EJ-02-04 SHT. 1 PIPING SUPPORT 12 VT-3 F-A F1.10 EJ-01-C015 EJ-01 -01 SHT. 3 PIPING SUPPORT 8 VT-3 F-A F1.20 EJ-01-R016 EJ-01.01 SHT. 1 PIPING SUPPORT 14 V`.3 F-A F1.20 Ej-01-ROi9 EJ-01-01 SHr. 1 PIPING SUPPORT 14 VT-3 F-A F1.20 EJ-01-R006 EJ-01-01 SHT. 2 PIPING SUPPORT 10 VT-3 F-A Fl.20 EJ-02-R023 EJ-02-02 SHT. 3 PIPING SUPPORT 10 VT-3 F-A F1.20 EJ-02-C012 EJ-02-02 SHT. 4 PIPING SUPPORT 10 VT-3 F-A F1.20 EJ-04-R010 EJ-02-04 SHT. 2 PIPING SUPPORT 6 VT-3 F-A F1.20 EJ-04-COII EJ-02-04 SHT. 3 PIPING SUPPORT 6 VT-3 F-A F1.20 EEJOIA-SKIRT-W ISI-EEJ01A SHT. 1 RHR HX SUPPORT VT-3 F-A F1l.40 EEJO1A-SUP-1 ISI-EEJOIA SHT. 1 RHR HX SUPPORT VT-3 F-A F1.40 EEJ01A-SUP-2 ISI-EEJ01A SHT. 1 RHR HX SUPPORT VT.3 F-A F1.40 EJ-04-F048A EJ-01-04 12 PIPE TO VALVE HV-8701A 12 1.125 UT R-A R1.11 126 3,4 WCRE-16 4.1.10 Residual Heat Removal System (EJ) Revision 0 Page 13 of 15

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EJ- 3 l Perod 3 Examinations l I System: _EJ Relief Request or Component Name Drawing Number Component Descripfion Size Thickness NDE Method Category Item Cal Black Notes EJ-04-S016-G EJ-42-04 SHT. I 12' PIPE TO 12" ELBOW 12 1.125 UT R-A R1.1 1 126 3,4 EJ-04-SOI1644 EJ-02-04 SHT. 1 12- ELBOW TO 12-PIPE 12 1.125 UT R-A RI.11 126 3,4 EP-1 -FOO9 EJ-01-01 SHT. 4 6' PIPE TO VALVE 8818A 6 0.719 UT R-A R1.11 117 3,4 EP-02-F022A EJ-02-04 SHT. 2 6- PIPE TO VALVE 8818C 6 0.719 UT R-A R1.11 117 3,4 EP-01-F021 EJ-02-04 SHT. 2 6' PIPE TO VALVE 8818D 6 0.719 UT R-A RI .11 117 3,4 EJ-04-S014-D EJ-02-04 SHT. 1 12" ELBOW TO 12 PIPE 12 1.125 UT R-A R1.20 126 3 EJ-01-F005 EJ-01-01 SHT. I 14- PIPE TO 14' ELBOW 14 0.438 UT R-A R1.20 192 3 EJ-01-FW3113B EJ-01-01 SHT. 1 12'ELBOWTO 12'PIPE 12 0.375 UT R-A R1.20 183 3 EJ-01-FW333 EJ-01-01 SHT. 1 12" PIPE TO 12" PIPE 12 0.375 UT R-A R1 .20 183 3 EJ-01-S021-E EJ-01-01 SHT. 2 10" PIPE TO 10" ELBOW 10 0.365 UT R-A R1.20 204 3 EJ-01-S021-F EJ-01-01 SHT. 2 10" ELBOWTO 10 PIPE 10 0.365 UT R-A R11.20 204 3 EJ-01-S026-E EJ401-01 SHT. 5 8" PIPE TO 8" ELBOW 8 0.322 UT R-A RI.20 203 3 EJ-02.F021 EJ-02-02 SHT. 2 10" TEE TO 10 PIPE 10 0.365 UT R-A RI.20 204 3 EJ-02-F031 EJ.02-02 SHT. 4 10"TEETO 10 PIPE 10 0.365 UT R-A RI.20 204 3 WCRE-16 4.1.10 Residual Heat Removal System (EJ) Revision 0 Page 14 of 15

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EJ- 3 Period 3 Examinatins I System: EJ I Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal BID4ck Notes EJ-02-SO16-H EJ-02-02 SHT. 2 10" PIPE TO 10" TEE 10 0.365 UT R-A RI.20 204 3 EJ-02-SO16-K EJ-02-02 SHT. 2 10" TEE TO 10" PIPE 10 0.365 UT R-A RI.20 204 3 EJ-02-S023-B EJ-02-02 SHT. 4 10" PIPE TO 10" TEE 10 0.365 UT R-A Ri.20 204 3 EJ-02-S023-D EJ-02-02 SHT. 4 10"TEETO 10" PIPE 10 0.365 UT R-A RI.20 204 3 EJ-04-Fo43 EI01-01 SHT. 4 10"PIPE TO 10"X1O"X6" TEE 10 1.00 UT R-A RI.20 122 3 EJ-04.FW91 0A EJ-02-04 SHT. 2 10" PIPE TO 10" X 10"X 68TEE 10 1.00 UT R-A R1.20 122 3 EJ-04-SOOI-D EJ-02-04 SHT. 2 10" ELBOW TO 10" PIPE 10 1.00 UT R-A R1.20 122 3 EJ-04-SOOI -G EJ-02-04 SHT. 2 10"X 10"X 6"TEETO 10" PIPE 10 1.00 UT R-A R1.20 122 3 EJ-04-FW371 EJ-02-04 SHT. 2 10"X 10"X6"TEETO 6"PIPE 6 0.719 UT R-A R1.20 1177 3 WCRE-1 6 4.1.10 Residual Heat Removal System (EJ) Revision 0 Page 15 of 15

I A WOLF CREEK GENERATING STATION G THIRD INTERVAL 151 PROGRAM PLAN E

4.1.11 High Pressure Coolant Injection System (EM) 0.

D 1 A. Applicable System Piping and Instrument Drawings

]. M-I2EMOI- -High Pressure Coolant Injection System

2. M-12EM02-High Pressure Coolant Injection System*

5 2

• Except for ASME Class 2 components listed in Section 4.3 0 B. Classification Of Components 6 Details of the classification of the High Pressure Coolant Injection System components for ISI are included in "Inservic. Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

C. Nonexempt and Exempt ASME Class Components A listing of Nonexempt and Exempt ASME Class components is included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

Note: for purposes of determining which EM system components are exempt based on size (i.e. NPS 4 inch vs NPS 11/A inch for High Pressure Safety Injection systems), the pumps in the EM system, PEM0IA and PEMOIB, are defined as Intermediate Pressure Safety Injection Pumps (reference USAR Table 6.2.1-3). Thus, the NPS 4 inch exemption is applied. The Centifugal Charging Pumps (CCPs), PBGOSA and PBG05B, are considered the High Head Safety Injection Pumps. Thus, the CCPs and components associated with the boration flowpath to the RCS are subject to the NPS I Y2inch exemption rule. See the ISI Classification Basis Document for definition of which lines fall under each exemption.

D. Applicable IS1 Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the High Pressure Coolant Injection System. These drawings are part of the M-1 89-50 series.

1. M-189-SOEM-0IO Sheet I High Pressure Coolant Injection Safety Injection Pump "A"Suction

2. M-189-50EM-02-01 Shect I High Pressure Coolant Injection Safety Injection Pump "B"Discharge

3. M-189-50EM-03-05 Sheet I High Pressure Coolant Injection Safety Injection Pumps to RHR System

4. M-1 89-50EM-04-03 Sheet I High Pressure Coolant Injection Safety Injection Pumps to RCS

5. M-189-50EM-05-01 Sheet I High Pressure Coolant Injection Safety Injection Pump Suction Cross Tie

6. M-189-SOEM-05-01 Sheet 2 High Pressure Coolant Injection Safety Injection Pump Suction Cross Tie to CVCS

7. M-1 89-50EM-06-02 Sheet I High Pressure Coolant Injection HPSI Discharge to RCS

8. M-1 89-50EM-06-02 Sheet 2 High Pressure Coolant Injection HPSI Discharge to RCS WCRE-16 4.1.11 High Pressure Coolant Injection System (EM) Revision 0 Page I of 12

WOLF CREEK GENERATING STATION THIRD INTERVAL IS1 PROGRAM PLAN D. Applicable ISI Isometrics and ISI Equipment Drawings (Coot'd)

9. M-l 89-5OEM-06-03 Sheet I High Prcssure Coolant Injection HPSI Discharge to RCS

10. M-189-50!SI-PUMPS Sheet I IS Pumps WCRE-1 6 4.1.11 High Pressure Coolant Injection System (EM) Revision 0 Page 2 of 12

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.11 High Pressure Coolant Injection System (EM)

E. Summary Of Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table I is a summary of the components and items subject to NDE per ASME Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the IS[ Database.

TABLE I SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM Pi P2 P3 INTERVAL PRESSURE RETAINING B-G-2 B7.50 4 0 0 I BOLTING-PIPING NoteI PRESSURE RETAINING B-G-2 17.70 - 4 0 0 BOLTING-VALVES XINotI VALVE BODY B-M-2 B12.50 . . 4 I

• EXCEEDING NPS 4 *SeeParagraph 1,Note 3 PRESSURE RETAINING C-A C1.20 . . 2 0 2 0 2 VESSEL WELDS-CIRC.

PRESSURE RETAINING C-B C2.21 . 2 0 2 0 2 NOZZLE-SHELL WELD VESSEL WELDED C-C C3.10 4 0 1 0 ATTACHMENTS PIPING WELDED C-C C3.20 . . 24 1 1 1 3 ATTACHMENTS PRESSURE RETAINING C-G C6.10 4 0 I I 2 PUMP WELDS PIPING COMPONENTS F-A F1.10 . 76 7 6 7 20 SUPPORTS _

PIPING COMPONENTS F-A F1.20 I - 83 4 6 5 IS SUPPORTS _ _

WCRE-16 4.1.1 I High Pressure Coolant Injection System (EM) Revision 0 Page 3 of 12

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE 1 SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY M NO CATEGORY ITEM NO. SYSTEM PI P2 P3 INTERVAL EQUIPMENT SUPPORTS F-A FI.40 - 4 1 2 1 4 (OTHER THAN PIPING)

PIPING WELDS SUBJECT R-A RI.11 - 8 0 0 0 0 TO THERMAL FATIGUE Note 2 Note 2 PIPING WELDS SUBJECT R-A RI.16 - 20 0 0 2 2 TO IGSCC or TGSCC Note 2 Note 2 PIPING WELDSNOT R-A R1.20 - 369 2 1 0 3 SUBJECT TO A DAMAGE Note 2 Note 2 M ECHANISM__ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ ___ _ _ _ _ _ _ _

Note 1: Examination of Pressure Retaining Bolting is performed in accordance with Code Case N-652. See Notes I and 2 in Paragraph I for selection and scheduling criteria.

Note 2: See Section 14 for an explanation of Category R-A and Item Rl.xx nomenclature.

WCRE-16 4.1.11 High Pressure Coolant Injection System (EM) Revision 0 Page 4 of 12

WOLF CREEK GENERATING STATION H TH IRD INTERVAL I SI PROGRAM PLAN E 4.1.11 High Pressure Coolant Injection System (EM)

F. Augmented ISI Requirements No Augmented IS] requirements apply to the High Pressure Coolant Injection System.

G. System Pressure Testing In accordance with Section Xl, IWA-5000 and IWB-5000, the Class I pressure retaining components within the High Pressure Coolant Injection System will receive a system leakage test o per IWB-5220 prior to plant startup following each refueling outage.

U In accordance with Section Xi, IWA-5000 and IWC-5000, the Class 2 pressure retaining 6 components within the High Pressure Coolant Injection System will receive a system leakage test per IWC-5220 each inspection period.

Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed 1SI Program A Risk Informed Inservice Inspection (R1-ISI) Program has been applied to Code Class I and 2 piping welds at WCGS. This program is described in detail in Section 2.3. High Pressure Coolant Injection System welds selected for examination per the RI-ISI program are listed in Tables EM-I, EM-2 and EM-3. Since the EPRI methodology used for the RI-ISI Program does not prescribe Code Examination Category and Item Numbers, guidance was taken from Code Case N-578-1 for the assignment of these designators.

When a specific degradation mechanism (DM) exists at a selected location, then the volume to be examined shall be as recommended in Section 4 of EPRI TR-I 12657 Rev. B-A. Welds subject to a DM are identified by a note in the Table. Welds selected that have no associated DM shall have the volume examined as shown in Figures 4.1-4 of TR-l 12657 Rev. B-A.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table EM-I (Period I Examinaticns), Table EM-2 (Period 2 Examinations), and Table EM-3 (Period 3 Examinations). The following Notes apply to the tables:

1. Bolting is required to be examined only when a connection is disassembled or bolting is removed. The examination of flange bolting in piping systems may be limited to one bolted connection among a group of bolted connections that are similar in design, size, function, and service. Examination of bolted connection is required only once during the interval.. See Code Case N-652, B-G-2, Notes I and 3.

2. Bolting is required to be examined only when a connection is disassembled or bolting is removed. For valves, examination of bolting is required only when the component is examined under Examination Category B-M-2. Examination of bolted connection is required only once during the interval. See Code Case N-652, Category B-G-2, Notes I and 2.

3. Examination ofthe valve internal surface is required only when a valve is disassembled for maintenance, repair, or volumetric examination. To aide in scheduling, the valve has been included in each inspection period. However, examination will be performed only once during the inspection interval and is limited to one valve within a group of valves that are the same size, constructional design, and manufacturing methods and which performs a similar function in the system. Examination may be alternatively performed on another valve within the group. If a valve has not been disassembled, examination is deferrable to subsequent periods. (Reference PIR 97-2539)

WCRE-16 4.1.11 High Pressure Coolant Injection System (EM) Revision 0 Page 5 of 12

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN

4. These welds have been selected per the RI-ISI Program. The requirements for examination of these welds are included in Paragraph H above.

5. These welds have IGSCC identified as the degradation mechanism.

WCRE-1 6 4.1.11 High Pressure Coolant Injection System (EM) Revision 0 Page 6 of 12

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EM- I Pe:od S I ExaminationsM I System: EMl Relief Request or Component Name Drawing Number Component Descuption Size Thickness NDE Method Category Item Cal Blo ck Notes EM-05-BB-8949A-SURF EM-03-05 VALVE 8949A INTERNAL PRESSURE SURFACE 6 VT-3 B-M-2 B12.50 3 EM-01-A003 EM-05-O1 SHT. i PIPING INTEGRALATTACHMENTS 6 PT C-C C3.20 EM-N0-RORl EM-03-05 PIPING SUPPORT 6 VT-3 F-A F1.10 EM-03-C012 EM-04-03 PIPING SUPPORT 6 Vr-3 F-A F1.10 FM-tVi-rJ1l3 E'A-04-03 6 VT-3 F-A F1 .10 PIPIN G SUPPORT EM-03.A005 EM-06-03 PIPING SUPPORT 1.5 VT-3 F-A F1.10 EM-03-C033 EM-03 PIPING SUPPORT 1.5 VT-3 F-A F1.10 EM-03-R015 EM-06-03 PIPING SUPPORT 1.5 VT-3 F-A F1.10 EM-03-R018 EM-06-03 PIPING SUPPORT 1.5 VT-3 F-A FI.10 EM-O0-H1015 EM-02-01 PIPING SUPPORT 8 VT-3 F-A F1.20 EM-01-A003 EM-05-O SHT. 1 PIPING SUPPORT 6 VT-3 F-A F1.20 PIPING SUPPORT EM-01-COI 6 EM-S-01 SHT. 2 6 VT-3 F-A F1.20 EM-02-R005 EM-0642 SHT. 2 PIPING SUPPORT 3 VT-3 F-A F1.20 TEMO1-SUPPORT-1 EM-06-02 SHT. 2 B.I.T. TANK SUPPORT VT-3 F-A F1.40 WCRE-16 4.1.11 High Pressure Coolant Injection System (EM) Revision 0 Page 7 of 12

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EM-1 Period I Examinations I System: EM I Relief Request or Component Nat,ne Drawing Number Component Description Size Thickness NDE Method Category Item Cal Blo,xk Notes EM-05-S005-B EM-03-05 6" PIPE TO 8- ELBOW 6 0.719 UT R-A R1.20 117 4 EM-05.SOOS-C EM-03-05 6 ELBOW TO 6" PIPE 6 0.719 UT R-A R1.20 117 4 WCRE-16

• 4.1.1 I High Pressure Coolant Injection System (EM) Revision 0 Page 8 of 12

WOLF CREEK GENERATING STATION THIRD INTERVAL IS[ PROGRAM PLAN TABLE EM.2 l Petiod 2 Examinations ISse:EM Relief Request or Component Name Drawing Number Component Description Size Thickness NOE Method Category Item Cal 13o0c~k Motes

- Cal BIn. Nei.L EM-05-BB-89490-b EM-03-05 VALVE 89490 BOLTING 6 VT-1 B-G-2 B7.70 2 EM-05-BB-8949A-SURF EM-03-05 VALVE 8949A INTERNAL PRESSURE SURFACE 6 VT-3 B-M-2 B12.50 3 TEM01-SEAM-2.W EMN02 SHT. 2 TOP HEAD TO SHELL WELD NA 2.00 UT C-A C1.20 144 TEM01-SEAM-3-W EM-06-02 SHT. 2 BOTTOM HEAD TO SHELL WELD NA 2.00 UT C-A C1.20 144 TEM01-1-W EM-O.-D2 SHT. 2 C. 11 'r CE, *-v TtOP HEAD 'v'vcLD NA 2.00 UT/PT C-B C2.21 144 TEM01-4-W EM-06-02 SHT. 2 INLET NOZZLE TO BOTTOM HEAD WELD NA 2.00 UT/PT C-B C2.21 144 TEM01-SUPPORT-2 EM-062 SHT. 2 VESSEL INTEGRAL ATTACHMENTS PT C-C C3.10 EM-02-R01 0 EM-0602 SHT. 1 PIPING INTEGRAL ATTACHMENTS 4 PT C-C C3.20 PEMO1A-F-1 EM-11-0t SI PUMP A FLANGE TO PUMP CASING WELD 6 0.28 PT C-G C6.10 EM-O5-COOB EM-03-05 PIPING SUPPORT 2 VT-3 F-A F?.10 EM-05-R004 EM-03-05 PIPING SUPPORT 2 F-A F1.10 VT-3 EM-03-C0a8 EM-06-03 PIPING SUPPORT 3 F-A F1.10 Vr-3 EM-03-C035 EM-06-03 PIPING SUPPORT 1.5 F-A F1.10 VT-3 EM-03-C047 EM06-03 PIPING SUPPORT 1.5 VT-3 F-A F1.10 WCRE-16 4.1.11I High Pressure Coolant Injection System (EM) Revision 0 Page 9 of 12

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EM-2 Peri0d 2 ExaminatMns I System: EM I Relief Request or Component Name Drawing Number Component Descrption Size Thickness NDE Method Category Item Cal Block Notes EM-03-RO1 6 EM-06-03 PIPING SUPPORT 1.5 VT-3 F-A F1.10 EM-01-C044 EM-01-01 PIPING SUPPORT 8 VT-3 F-A F1.20 EM-O1-R031 EM-01-01 PIPING SUPPORT 6 VT-3 F-A F1.20 EM-01-C017 EM-0S-01 SHT. I PIPING SUPPORT 6 VT-3 F-A F1.20 EM-01-H003 EM.-t_" qHT. 1 P!P!NG-SUPPOP.T G *vT-3 F-A F11.20 EM-41-1016 EM-OSl SHT. I PIPING SUPPORT 6 VT-3 F-A F1.20 EM-02-RO10 EM-06-02 SHT. I PIPING SUPPORT 4 V7-3 F-A F1.20 TEM01-SUPPORT-2 EM-06-02 SHT. 2 B.I.T. TANK SUPPORT VT-3 F-A F1.40 TEM01-SUPPORT-3 EM-06-02 SHT. 2 B.I.T. TANK SUPPORT VT-3 F-A Fi.40 EM-03-SO1 5-B EM-04-03 6- PIPE TO 6' ELBOW 6 0.719 UT R-A R1.20 117 4 WCRE-16 4.1.11 High Pressure Coolant Injection System (EM) Revision 0 Page 10 of 12

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EM-3 l Periot 3 Examinations I System. EM Relief Request or Component Name Drawing Number Component Description size Thickness NDE Method Category Item Cal Block Notes EM-03-FE-927-FL-b EM-06-03 FLANGE FE-927 BOLTING 1.5 Vr-1 B--2 B7.50 EM-05-BB-8949A-SURF EM-03-05 VALVE 8949A INTERNAL PRESSURE SURFACE 6 VT-3 B-M-2 B12.50 3 EM-02-H002 EM-06-02 SHT. 2 PIPING INTEGRAL ATTACHMENTS 4 PT C-C C3.20 PEMO1A-F-2 EM-01-01 SI PUMP A DISCHARGE FLG. TO PUMP CASING WELD 4 0.337 PT C-G C6.10 FMufnc-n2n P°IPNG SUP.POT a VT-3 F-A F1.10 EM-03-C016 EM-04-03 PIPING SUPPORT 2 VT-3 F-A F1.10 EM-03-H004 EM-04-03 PIPING SUPPORT 6 VT-3 F-A F1.10 EM-03-R005 EM-04-03 PIPING SUPPORT 6 VT.3 F-A F1.10 EM-03-R008 EM-04-03 PIPING SUPPORT 2 VT-3 F-A F1.10 EM-03-C029 EM-06-03 PIPING SUPPORT 1.5 VT-3 F-A F1.10 EM-03-C034 EM-06-03 PIPING SUPPORT 1.5 VT-3 F-A F1.10 EM-01-CO15 EM-05o-1 SHT. 1 PIPING SUPPORT 6 VT-3 F-A F1.20 EM-01-C036 PIPING SUPPORT 5 VT-3 F-A F1.20 EM-02-R007 EM-06-02 SItT. 1 PIPING SUPPORT 4 VT.3 F-A F1.20 WCRE-1 6 4.1.1 I High Pressure Coolant Injection System (EM) Revision 0 Page IIof 12

GGCt 8tntt5s ~rnc>3-WOLF CREEK GENERATING STATION THIRD INTERVAL lSI PROGRAM PLAN TABLE EM-3 r Period 3 Examinations I System: EMI Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes EM-02-ROI 1 EM-0642 Si-IT. I PIPING SUPPORT 4 VT-3 F-A F1.20 EM42-1H002 EM-06-02 SHT. 2 PIPING SUPPORT 4 VT-3 F-A F1.20 TEM01-SUPPORT-4 EM-06-02 SHT. 2 B.I.T. TANK SUPPORT VT-3 F-A F1.40 EM-03-SO11 1F EM-04-03 6PIPETO6"ELBOW 6 0.719 UT R-A R1.16 117 4,5 EM03-101 1-G Et.! A--03 6 E"vJW To06" r;rE 6 0.719 UT R-A R1.16 117 4.5 WCRE-1 6 4.1.11 High Pressure Coolant Injection System (EM) Revision 0 Page 12 of 12

M A WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN G

E D 4.1.12 Containment Spray System (EN) 0 1 A. Applicable System Piping and Instrument Drawings

/ 1. M-12ENO1-Containment Spray System B. Classification Of Components 2

0 Details of the classification of the Containment Spray System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating 0 Station Intcrval 3".

C. Nonexempt and Exempt ASME Class Components A listing of Nonexempt and Exempt ASME Class components is included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Containment Spray System. These drawings are part of the M.

189-50 series.

1. M-189-50EN-01OlOSheet I Containment Spray "A" Train Pump Suction

2. M-189-50EN-01-O1 Sheet 2 Containment Spray "A" Train Pump Discharge

3. M-189-50EN-02-02Sheet I Containment Spray "B" Train Pump Suction

4. M-l 89-5OEN.02-02Sheet 2 Containment Spray "B" Train Pump Discharge

5. M-189-5O0SI-PUMPS Sheet I ISI Pumps WECRE-16 4.1.12 Containment Spray System (EN) Revision 0 Page I of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.12 Containment Spray System (EN)

E. Summary or Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table 1 is a summary of the components and items subject to NDE per ASME Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the IS[ Database.

TABLE I SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO SYSTEM Pi P2 P3 INTERVAL PIPING WELDED C-C C3.20 . 5 0 0 l I ATTACHMENTS PUMP WELDED C-C C3.30 . 6 0 0 1 I ATTACHMENTS PIPING F-A F1.20 22 1 1 2 4 SUPPORTS SUPPORTS OTHER THAN F-A F1.40 . 6 3 0 0 3 PIPING SUPPORTS _

PIPING WELDS NOT R-A Rl 20 93 0 0 0 O SUBJECT TO A DAMAGE MECHANISM. Note I Note I Note 1: See Section H for an explanation of Category R-A and Item Rl.xx nomenclature.

WCRE-16 4.1.12 Containment Spray System (EN) Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.12 Containment Spray System (EN)

F. Augmented ISI Requirements No Augmented ISI requirements apply to the Containment Spray System.

C. System Pressure Testing In accordance with Section XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining components within the Containment Spray System will receive a system leakage test per IWC-S220 each inspection period.

Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Program A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class I and 2 piping welds at WCGS. This program is described in detail in Section 2.3. Since the EPRI methodology used for the RI-IS! Program does not prescribe Code Examination Category and Item Numbers;, the assignment of these designators is the same as utilized in Code Case N-578-1 .No welds in the Containment Spray System were selected for examination in the RI-ISI program.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table EN-I (Period I Examinations), Table EN-2 (Period 2 Examinations),

and Table EN-3 (Period 3 Examinations).

WCRE-16 4.1.12 Containment Spray System (EN) Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EN-1

[ Period I Examinations I I System: EN Relief Request or Component Name Drawing Number Component Size Thickness NDE Method Category Item Cal Block Notes EN-02-H005 EN-02-02 SHT. 2 PIPING SUPPORT 10 VT-3 F-A F1.20 PENO1A-SUP-1 EN-01-01 SHT. I CONTAINMENT SPRAY "K PUMP SUPPORT 12 VT-3 F-A F1 .40 PEN01A-SUP-2 EN-01-01 SHT. I CONTAINMENT SPRAY WAPUMP SUPPORT 12 VT-3 F-A F1.40 PENOIA-SUP-3 EN-01-01 SHT. 1 CONTAINMENT SPRAY A PUMP SUPPORT 12 VT-3 F-A F1.40 WCRE-16 4.1.12 Containment Spray System (EN) Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISt PROGRAM PLAN TABLE EN-2 l Period 2 Examinations lISystem: ENl Relief Request or Component Name Drawing Number Component Size Thickness NDE Method Category Item Cal Block Notes EN-02-R004 EN.02-02 SHT. 2 PIPING SUPPORT 10 Vr-3 F-A F1.20 WCRE-16 4.1.12 Containment Spray System (EN) Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EN- 3 Period 3 Examination ISse:EN Relief Request or Component Name Drawing Number Component Size Thickness NDE Method Category Item Cal Block Notes EN-02-R007 EN-02-02 SHT. 2 PIPING INTEGRAL ATTACHMENTS 10 PT C-C C3.20 PENO1A-SUP-1 EN-01-01 SHT. 1 CS PUMP A INTEGRALLY WELDED ATTACHMENTS 12 PT C-C C3.30 EN-01-RO08 EN-01-01 SHT. 1 PIPING SUPPORT 12 VT-3 F-A F1.20 EN-02-R007 EN-02-02 SHT. 2 PIPING SUPPORT 10 VT-3 F-A F1 .20 WCRE-16 4.1.12 Containment Spray System (EN) Revision 0 Page 6 of 6

I Ii A WOLF CREEK GENERATING STATION G THIRD INTERVAL ]SI PROGRAM PLAN E

4.1.13 Accumulator Safety Injection System (EP) 0 1

A. Applicable System Piping and Instrument Drawings

1. M-12EPOI-Accumulator Safety Injection System 5

B. Classification Of Components 2

6 Details of the classification of the Accumulator Safety Injection System components for 0 ISI are in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

C. Nonexempt and Exempt ASME, Class Components A listing of Nonexempt and Exempt ASME Class components is included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and ISMEquipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Accumulaior Safety Injection System. These drawings are part of the M-189-50 series.

1. M-189-50EP-Ol-Ol Sheet I Accumulator Safety Injection Loop I

2. M-189-5OEP-02-02 Sheet I Accumulator Safety Injection Loop 2

3. M-189-50EP-03-02 Sheet I Accumulator Safety Injection Loop 3

4. M-l 89-50EP-04-01 Sheet I Accumulator Safety Injection Loop 4 WCRE-1 6 4.1.13 Accumulator Safety Injection System (EP) Revision 0 Page I of 7

WOLF CREEK GENERATING STATION THIRD INTERVAL 15 PROGRAM PLAN 4.1.13 Accumulator Safety Injection System (EP)

E. . Summary Of Components Subject To Section XI and Augmented NDE/Scheduled For Examination

-Table I is a summary of the components and items subject to NDE per ASME Section Xl or per Augmented requirements. A detailed listing of these components and items is maintained in the ISI Database.

TABLE I SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM Pi P2 P3 INTERVAL PRESSURE RETAINING B-G-2 B7.70 12 1 2 0 3 BOLTING-VALVES Note I VALVE BODY B.M.2 B12.50 . 12

• 2 EXCEEDING NPS 4 *SeeParanamh 1,Note 2 PIPING COMPONENT F-A P1.10 . 29 3 2 3 8 SUPPORTS PIPING WELDS SUBJECT -ARl6--2 0 0 22 TO IGSCC OR TGSCC R-A Rl.16 120 0 2 Note 2 Note 2 PIPING WELDS NOT R-A 1 20 103 0 2 0 2 SUBJECT TO A DAMAGE .

MECHANISM Note 2 Note 2 Note 1: Bolting examined in accordance with Code Case N-652. See Note I in Paragraph I for selection and scheduling criteria.

Note 2: See Section H for an explanation of Category R-A and Item Rl .xx nomenclature.

WCRE-1 6 4.1.13 Accumulator Safety Injection System (EP) Revision 0 Page 2 of 7

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.13 Accumulator Safety Injection System (EP)

F. Augmented ISI Requirements No Augmented ISI requirements apply to the Accumulator Safety Injection System.

G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWB-5000, the Class I pressure retaining components within the High Pressure Coolant Injection will receive a system leakage test per IWB-5220 prior to plant startup following each refueling outage.

Inaccordance with Section XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining components within the Accumulator Safety Injection System will receive a system leakage test per IWC-5220 each inspection period.

Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Program A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class I and 2 piping welds at WCGS. This program is described in detail in Section 2.3.

Accumulator Safety Injection System welds selected for examination per the RI-ISI program are listed in Tables EP-1, EP-2 and EP-3. Since the EPRI methodology used for the RI-ISI Program does not prescribe Code Examination Category and Item Numbers, guidance was taken from Code Case N-578-1 for the assignment of these designators.

When a specific degradation mechanism (DM) exists at a selected location, then the volume to be examined shal I be as recommended in Section 4 of EPRI TR- 12657 Rev.

B-A. Welds subject to a DM are identified by a note in the Table. Welds selected that have no associated DM shall have the volume examined as shown in Figures 4.1-4 of TR-112657 Rev. B-A.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table EP-1 (Period I Examinations), Table EP-2 (Period 2 Examinations),

and Table EP-3 (Period 3 Examinations). The following Notes apply to the tables:

1. Examination of Pressure Retaining Bolting is performed in accordance with Code Case N-652. Bolting is required to be examined only when a connection is disassembled or bolting is removed. For valves, examination of bolting is required only when the component is examined under Examination Category B-M-2. Examination of bolted connection is required only once during the interval. See Code Case N-652, Category B-G-2, Notes I and 2.

2. Examination of the valve internal surface is required only when a valve is disassembled for maintenance, repair, or volumetric examination. To aide in scheduling, the valve has been included in each inspection period. However, examination will be performed only once during the inspection interval and is limited to one valve within a group of valves that are the same size, constructional design, and manufacturing methods and which performs a similar function in the system. Examination may be alternatively performed on another valve within the group. If a valve has not been disassembled, examination is deferrable tc subsequent periods. (Reference PIR 97-2539)

WCRE-16 4.1.13 Accumulator Safety Injection System (EP) Revision 0 Page 3 of 7

I WOLF CREEK GENERATING STATION M THIRD INTERVAL ISI PROGRAM PLAN A

G E 3. These welds have been selected per the RI-ISI Program. The requirements for examination of these welds is given in Paragraph Habove.

0l 4. These welds have IGSCC identified as the degradation mechanism.

1 5

0 0

WCRE-l 6 4.1.13 Accumulator Safety Injection System (EP) Revision 0 Page 4 of 7

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EP-1

[ Period I ExaminationsI ISystern: EP Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes EP-01-8956A-b EP-01-01 VALVE 8856A BOLTING 10 VT-1 B-G-2 B7.70 EP-01-8818A-SURF EP-01-01 VALVE 8818A INTERNAL PRESSURE SURFACE e VT-3 B-M-2 B12.50 2 EP-01-BB-8948A-SURF EP-01-0 VALVE 8948A INTERNAL PRESSURE SURFACE 10 VT-3 B-M-2 B12.50 2 EP-02-H006 EP-02-02 PIPING SUPPORT 10 VT-3 F-A F1.10 EP-01-H006 EP-04-01 PIPING SUPPORT 2 VT-3 F-A F1.10 EP-01-R008 EP-04-01 PIPING SUPPORT 2 VT-3 F-A F1.10 WCRE-16 4.1.13 Accumulator Sarety Injection System (EP) Revision 0 Page 5 of 7

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EP- 2 aPeriod 2 ExamInatlons I rSystem:. EPT Relief Request or Component Narne Drawing Number Component Description Size Thickness NDE Method Category Item Cal Bo0c:k Notes EP-41-8818A-b EP-01-01 VALVE 8818A BOLTING 6 VT-1 B-G-2 B7.70 I 1

EP-01-BB-8948A-b EP-01-01 VALVE BB-8848A BOLTING 10 Vr-1 B-t-2 B7.70 EP-41-881 BA-SURF EP-01-01 VALVE 8818A INTERNAL PRESSURE SURFACE 6 VT-3 8-M-2 B12.50 2 EP-01-BB-894BA-SURF EP-014-1 VALVE 8948A INTERNAL PRESSURE SURFACE 10 VT-3 B-M-2 812.50 2 EP-Ol-H004 EP-04-01 PIPING SUPPORT 10 VT-3 F-A F1.10 EP-0t-R005 EP-04-01 PIPING SUPPORT 10 VT-3 F-A F1 .10 EP-O -S004-C EP-41-01 10 PIPE TO 10" ELBOW 10 1 tUT R-A R1.20 122 3 EP-01-S004-D EP-414-1 10 ELBOW TO 10" PIPE 10 IIUT R-A R1.20 122 3 WCRE-16 4.1.13 Accumulator Safety Injection System (EP) Revision 0 Page 6 of 7

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE EP- 3 l Period 3 Examinatbns lISystem: EP Relief Request or Component Name Drawing Number Component Descriptlon Size Thickness NOE Method Category Item Cal Block Notes EP-01-881 8A-SURF EP-01-01 VALVE 8818A INTERNAL PRESSURE SURFACE 6 VT-3 B-M-2 812.50 2 EP-01-8B-8948A-SURF EP-014-1 VALVE 8948A INTERNAL PRESSURE SURFACE 10 VT-3 B4V-2 B12.50 2 EP-01-R013 EP-01-01 PIPING SUPPORT 10 VT-3 F-A F1.10 EP-011-C004 EP-04-01 PIPING SUPPORT 2 VT-3 F.A F1.10 EP-01-ROOW EP-04-01 PIPING SUPPORT 6 VT-3 F-A F1 .10 EP-01-S003-K EP-01-01 10" PIPETO 10" ELBOW 10 1 UT R-A R1.16 122 3,4 EP-01-S.03-L EP-01-01 10"ELBOWTO 10 PIPE 10 1 UT R-A R1.16 122 3,4 WCRE-16 4.1.13 Accumulator Safety Injection System (EP) Revision 0 Page 7 of 7

I M

A WOLF CREEK: GENERATING STATION G THIRD INTERVAL ISI PROGRAM PLAN E

• D 4.1.14 Auxiliary Feedwater Pump Turbine System (FC) 0 A. Applicable System Piping anl Instrument Drawings 5 1. M-12FC02-Auxiliary Feedwater Pump Turbine System I

I B. Classification Of Components 0 Details of the classification of the Auxiliary Feedwater Pump System components for ISI 0 are included in "Inscrvice Inspection Classification Basis Document Wolf Creek 6 Generating Station Interval 3".

C. Nonexempt and Exempt ASIVIE Class Components A listing of Nonexempt and Exempt ASME Class components is included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and 1SI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Auxiliary Feedwater Pump System. This drawing is part of the M-189-50 series.

1. M-189-50FC-01-01 Sheet I Auxiliary Turbines Auxiliary Feedwater Pump Turbine Steam Supply Piping WCRE-1 6 4.1.14 Auxiliary Feedwater Pump Turbine System Revision 0 (FC)

Page I of 6

WOLF CREEK GENERLALTING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.14 Auxiliary Feedwater Pump Turbine System (FC)

E. Summary Or Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table I is a summary of the components and items subject to NDE per ASME Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the ISI Database.

TABLE I SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM Pi P2 P3 INTERVAL TO ELB I .E.TUSAR 3.6.2 17 2 I 2 5 TO HELB REQUIREMENTS _____II-- 1 2 WCRE-16 4.1.14 Auxiliary Feedwater Pump Turbine System Revision 0 (FC)

Page 2 of 6

I WOLF CREEK GENERATING STATION

'H THIRD INTERVAL ISI PROGRAM PLAN E 4.1.14 Auxiliary Feedwater Pump Turbine System (FC) 8 F. Augmented ISI Requirements The following Augmented ISI requirements apply to the Auxiliary Feedwater Pump

/ System:

1. WCGS USAR Sections 3.6.1, Postulated Piping Failures In Fluid Systems Inside and Outside Containment and 3.6.2, Determination Of Break Locations and Dynamic Effects Associated With The Postulated Rupture Of Piping- WCGS has implemented a Risk Informed-High Energy Line Break program as an alternative to the examination

()methodology of USNRC Branch Technical Position MEB 3-1. This program is O maintained in WCRE-14 and is applicable to the piping within the "no break zone" associated with high energy piping in containment penetration areas. The "no break zone" is an area where pipe breaks were not postulated due to the stress levels being within limits specified in USAR Section 3.6.2. The applicable welds are shown on the Auxiliary Feedwater Pump System Isometrics within the "No Break Zone" and included in Tables FC-1, FC-2, and FC-3 with Category "USAR" and Item No. "3.6.2".

When a specific degradation mechanism (DM) exists at a selected location, then the volume to be examined shall be as recommended in Section 4 of EPRI TR-] 12657 Rev.

B-A. Welds subject to a DM are identified by a note in the Table. Welds selected that have no associated DM shall have the volume examined as shown in Figures 4.1-4 of TR-112657 Rev. B-A.

G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining components within the Auxiliary Feedwater Pump System will receive a system leakage test per IWC-5220 each inspection period.

Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Program The RI-ISI Program is not applicable to the FC system.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table PC-I (Period I Examinations), Table FC-2 (Period 2 Examinations),

and Table FC-3 (Period 3 Examinations).

WCRE-16 4.1.14 Auxiliary Feedwater Pump Turbine System Revision 0 (FC)

Page 3 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE FC-1 IPeriod 1 Examinationq l System: FC I Relief Request or Component Name Drawing Number Component Desaiption Size Thickness NOE Method Category Item Cal Block Notes FC-01-F022 FC01-01 VALVE V001 TO 4 PIPE 4 0.337 UT USAR 3.6.2 159 FC-01-F023 FC-01-01 4" PIPE TO VALVE V024 4 0.337 UT USAR 3.6.2 159 WCRE-16 4.1.14 Auxiliary Feedwater Pump Turbine System Revision 0 (FC)

Page 4 of 6

cr)(Z) --- C)z-,mm:l> - -

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE FC- 2 l Period 2 Examinationsl I System: FC- I RoAelef Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes FC-01-S021-C FC-01-01 4" PIPE TO 4" ELBOW 4 0.337 UT USAR 3.6.2 159 WCRE-16 4.1.14 Auxiliary Fcedwatcr Pump Turbine System Revision 0 (FC)

Page 5 of 6

r- -CD Ma- I-r WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE FC-3 I Period 3 Examinations ISystem: FC I Relief Request or Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Cal Block Notes FC-01-F026 FC-01i-1 4' PIPE TO VALVE V002 4 0.337 UT USAR 3.6.2 159 FC-01-F027 FC-01-01 VALVE V025 TO 4 PIPE 4 0.337 UT USAR 3.6.2 159 WCRE-16 4.1.14 Auxiliary Feedwater Pump Turbine System Revision 0 (FC)

Page 6 of 6

I A WOLF CREEK GENERATING STATION G THIRD INTERVAL ISI PROGRAM PLAN E

[D 4.1.15 Containment Cooling System (GN) 1 A. Applicable System Piping and Instrument Drawings 2

I

1. M-I2GNO I-Containment Coaling System B. Classification Of Components 2 Details of the classification of the Containment Cooling System components for ISI are 0 included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Li Station Interval 3".

6 C. Nonexempt and Exempt ASME Class Components A listing of Nonexempt and Exempt ASME Class components are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Containment Cooling System. These drawings are part of the M-189-50 series.

1. M-189-50GN-O1-01 Sheet I Containment Cooling System "A" Train Supply

2. M-189-50GN-O1-Ol Sheet2 Containment Cooling System "A" Train Return

3. M-189-SOGN-OlO Sheet 3 Containment Cooling System "A" Train Cooler "A" Supply and Return Headers

4. M-189-5OGN-Ol-O1 Sheet 4 Containment Cooling System "A" Train Cooler "C" Supply and Return Headers

5. M-189-SOGN-02-02 Sheet I Containment Cooling System "B" Train Supply

6. M-189-50GN-02-02 Sheet 2 Containment Cooling System "B" Train Return

7. M-189-5OGN-02-02 Sheet 3 Containment Cooling System "B" Train Cooler "B" Supply and Return Headers

8. M- 189-50GN-02-02 Sheet 4 Containment Cooling System "B" Train Cooler "D" Supply and Return Headers WCRE-16 4.1.15 Containment Cooling System (GN) Revision 0 Page I of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.15 Containment Cooling System (GN)

E. Summary Of Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table I is a summaly of the components and items subject to NDE per ASME Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the ISI Database.

TABLE I SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG. AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. S-YSTEM P1 P2 P3 INTERVAL PIPING WELDED D-A DI.20 . 41 1 2 2 5 ATTACHMENTS PIPING COMPONENT F-A F1.30 112 4 4 4 12 SUPPORTS WCRE-1 6 4.1.15 Containment Cooling System (GN) Revision 0 Page 2 of 6

I WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN A

G 4.1.15 Containment Cooling System (GN)

E F. Augmented IS] Requirements 0

.1 No Augmented ISI requirements apply to the Containment Cooling System.

/ G. System Pressure Testing 5

2 In accordance with Section Xl, IWA-5000 and IWD-S000, the Class 3 pressure retaining components within the Containment Cooling System will receive a system leakage test per IWD-5221 every period and a system hydrostatic test per IWD-5222 at or near the 0 end of the interval. As allowed by Code Case N-498-4, alternative rules may be employed in lieu of the system hydrostatic test of IWD-5222.

Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Program The RI-ISI Program is not applicable to the Containment Cooling System.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table GN-1 (Period I Examinations), Table GN-2 (Period 2 Examinations),

and Table GN-3 (Period 3 Examinations).

WCRE-16 4.1.15 Containment Cooling System (GN) Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE GN.1 Period Examinations G

I System: GN I Component Name Dramwng Number Component Description Size Thickness NOE Method Category Item Relief Request Notes GN-01-C017 GN-01-01 SHT. 2 PIPING INTEGRAL ATTACHMENTS 14 VT-1 D-A D1.20 GN-01-C003 GN-01-01 SHT. I PIPING SUPPORT 14 VT-3 F-A F1.30 GN-01-C017 GN-01-01 SHT. 2 PIPING SUPPORT 14 VT-3 F-A F1.30 GN-02-HOOI GN-02-02 SHT. 2 PIPING SUPPORT 10 VT-3 F-A F1.30 M-620-003-24 GN-02-02 SHT. 4 PIPING SUPPORT 6 VT-3 F-A F1.30 WCRE-16 4.1.15 Containment Cooling System (GN) Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE GN-2 r Period 2 Examinationsl I System: GN- I Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Relief Request Notes M-620-003-09 GN-01-01 SHT. 3 PIPING INTEGRAL ATTACHMENTS a VT-1 D-A D1.20 M-620-003.10 GN-01-01 SHT. 3 PIPING INTEGRAL ATTACHMENTS 8 VT-1 D-A D1.20 GN-01 -H005 GN-01-01 SHT. 2 PIPING SUPPORT 10 VT-3 F-A F1.30 M-620-003-09 GN-01-01 SHT. 3 PIPING SUPPORT 8 VT-3 F-A F1.30 M-620-003-1 0 GN-01-01 SHT. 3 PIPING SUPPORT 8 VT-3 F-A F1 .30 GN-02-C006 GN-02-02 SHT. I PIPING SUPPORT 10 VT-3 F-A F1.30 WCRE-16 4.1.15 Containment Cooling System (GN) Revision 0 Page5 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE GN-3 l Perod 3 Examinations I I System: GNl Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Relief Request Notes M-620-003-13 GN-01-01 SHT. 3 PIPING INTEGRAL ATTACHMENTS 6 VT-1 D-A D1.20 M-620-003-14 GN-01-01 SHT. 3 PIPING INTEGRAL ATTACHMENTS 6 VT-1 D-A D1.20 GN-01-CO16 GN-01-01 SHT. 1 PIPING SUPPORT 14 VT-3 F-A F1.30 M-62D-003-1 3 GN-01-01 SHT. 3 PIPING SUPPORT 6 VT-3 F-A F1.30 M-620 003-14 GN-01i01 SHT. 3 PIPING SUPPORT 6 Vr-3 F-A F1.30 GN-02-C026 GN-02-02 SHT. 1 PIPING SUPPORT 10 Vr-3 F-A F1.30 WCRE-16 4.1.15 Containment Cooling System (GN) Revision 0 Page 6 of 6

I M

A WOLF CREEK GENERATING STATION G THIRD INTERVAL IS1 PROGRAM PLAN E

[ 4.1.16 Standby Diesel Generator Systems (KJ) 0 1

A. Applicable System Piping and Instrument Drawings

1. M-12KJ01-Standby Diesel Generator Cooling System

/ 2. M-12KJ02-Standby Diesel Generator "A" Intake Exhaust, F.O. & Start Air System 2/ito

3. M-12KJ03-Standby Diesel Generator "A" Lube Oil System

4. M-12KJ04-Standby Diesel Generator "B" Cooling Water System

5. M-12KJ05-Standby Diesel Generator "B" Intake Exhaust, F.O. & Start Air System 2 6. M-12KJ06-Standby Diesel Generator "B" Lube Oil System B. Classification Of Components Details of the classification of the Standby Diesel Generator Systems components for ]SI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

C. Noncxempt and Exempt ASMIE Class Components A listing of Nonexempt and Exempt ASME Class components is included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Standby Diescl Gencrator Systems. These drawings are part of the M-189-50 series.

1. M-189-50KJ-01-01 Sheet I Standby Diesel Engine Diesel Generator "A" Cooling Water Piping

2. M-189-50KJ-01-01 Sheet 2 Standby Diesel Engine Diesel Generator "A" Lube Oil Piping

3. M-189-50KJ-O1-O1 Sheet 3 Standby Diesel Engine Diesel Generator "A" Air Intake Piping

4. M-189-50KJ-01-01 Sheet 4 Standby Diesel Engine Diesel Generator "A" Exhaust Piping

5. M-189.50KJ-02-04 Sheet I Standby Diesel Engine Diesel Generator "B" Cooling Water Piping

6. M-189-50KJ.02.04 Sheet 2 Standby Diesel Engine Diesel Generator "B" Lube Oil Piping

7. M-1 89-50KJ-02-04 Sheet 3 Standby Diesel Engine Diesel Generator "B" Air Intake Piping

8. M-1 89-50KJ-02-04 Sheet 4 Standby Diesel Engine Diesel Generator "B" Exhaust Piping WCRE-16 4.1.16 Standby Diesel Generator Systems (KJ) Revision 0 Page I of 6

r,-,c-:, cE:>?--.) -- (:D r--rn a,):i- ---

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.1.16 Standby Diesel Generator Systems (KJ)

E. Summary Of Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table I is a summary of the components and items subject to NDE per ASME Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the ISI Database.

TABLE 1 SECTION XI AND AUGMENTED COMPONENT

SUMMARY

AND SCHEDULE COMPONENT OR ITEM CODE CODE AUG, AUG TOTAL IN EXAMS BY PERIOD & INTERVAL DESCRIPTION CATEGORY ITEM NO. CATEGORY ITEM NO. SYSTEM Pi P2 P3 INTERVAL VESSEL WELDED D-A D11.10 . 16 2 3 3 8 ATTACHMENTS PIPING WELDED D-A D1.20 22 1 l 1 3 ATTACHMENTS PIPING COMPONENT F-A P1.30 60 2 1 3 6 SUPPORTS EQUIPMENT SUPPORTS F-A P1.40 16 2 3 3 8 (OTHER THAN PIPING) =

WCRE-16 4.1.16 Standby Diesel Generator Systems (KI) Revision 0 Page 2 of 6

I WOLF CREEK GENERATING STATION THIRD INTERVAL IS) PROGRAM PLAN 4.1.16 Standby Diesel Generator Systems (KJ)

IiE 5D F. Augmented ISI Requirements A

1 The following Augmented IS requirements apply to the Standby Diesel Generator Systems:

G/ 1. USNRC Repulatorv Guide 1.137. Revision 0 - Fuel-Oil Systems for Standbv Diesel Generators-This Regulatory Guide includes pressure testing requirements for fuel oil systems of standby diesel generators. WCGS has committed to this testing per USAR Appendix 3A and Section 9.5.4. These requirements are satisfied by the implementation 0 of the testing and VT-2 examinations required by Articles IWD-2000 and IWD-5000 of 0 ASME Section XI, 1998 Edition with 2000 Addenda.

6 G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWD-5000, the Class 3 pressure retaining components within the Standby Diesel Generator Systems will receive a system leakage test per IWD-5221 every period and a system hydrostatic test per IWD-5222 at or near the end of the interval. As allowed by Code Case N-498-4, alternative rules may be employed in lieu of the system hydrostatic test of IWD-5222.

Procedures used to perforrn System Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Program The RI-ISI Program is not applicable to the Standby Diesel Generator Systems.

1. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 3 are included in Table KJ-l (Period I Examinations), Table KJ-2 (Period 2 Examinations),

and Table KJ-3 (Period 3 Examinations).

WCRE-1 6 4.1.16 Standby Diesel Generator Systems (KJ) Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE KJ- I I Period I Examinations I I System: KJ I Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Relief Request Notes EK=JOA-SUP-1 KJ-01-01 SHT. 1 WATER JACKET EKJ06A INTEGRAL ATTACHMENT VT-1 D-A D1.10 EKJ06A-SUP-2 KJ-01-01 SHT. 1 WATER JACKET EKJ06A INTEGRAL ATTACHMENT VT-1 D-A 01.10 KJ-01-C016 KJ-02-04 SHT. 4 PIPING INTEGRAL ATTACHMENT 42 VT-1 D-A D1.20 M-018-667-022 KJ-01-Oi SHlT. 2 PIPING SUPPORT 5 VT-3 F-A F1.30 KJ-01-C016 KJ-02-04 SHT. 4 PIPING SUPPORT 42 VT-3 F-A F1.30 EKJ06A-SUP-1 KJ-01-01 SHT. i WATER JACKET HX SUPPORT Vr-3 F-A F1.40 EKJO0A-SUP-2 KJ-01-01 SHT. 1 WATER JACKET HX SUPPORT VT-3 F-A F1.40 WCRE-16 4.1.16 Standby Diesel Generator Systems (KJ) Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE KJ- 2 l Perior 2 Examinations I I System: KJ I Component Name Drawing Number Component Description Size Thickness NDE Method Category Item Relief Request Notes EKJ03A-SUP-1 KJ-Oi-O1 SHT. 1 INTERCOOLER HX INTEGRAL ATTACHMENT VT-1 D-A D1.10 EKJ03A-SUP-2 KJ-01-01 SHT. 1 INTERCOOLER HX INTEGRAL ATTACHMENT VT-1i D-A D1.10 FKJ08A-SUP-2 KJ-01-01 SHT. 2 MAIN LUBE OIL STRAINER A INTEGRAL ATTACHMENT VT-1 D-A D1.10 KJ-01-R008 KJ-01-01 SHT. 4 PIPING INTEGRAL ATTACHMENTS 28 VT-1 D-A D1.20 KJ-01-R008 KJ-01-01 SHT. 4 PIPING SUPPORT 28 VT-3 F-A f1.30 EKJ03A-SUP-1 KJ-01-01 SHT. 1 INTERCOOLER HX SUPPORT VT-3 F-A F1.40 EKJ03A-SUP-2 KJ-01-01 SHT. I INTERCOOLER HX SUPPORT VT-3 F-A F1.40 FKJ08A-SUP-2 KJ-01-01 SHT. 2 MAIN LUBE OIL STRAINER A SUPPORT VT-3 F-A F1.40 WCRE-16 4.1.16 Standby Diesel Generator Systems (KJ) Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE KJ- 3 l Period 3 Examinationsl I System: KJ l Component Name Drawing Number Component Desetiption Size Thickness NDE Method Category Item Relief Request Notes EKJD4A-SUP-1 KJ-01-01 SHT. 1 LUBE OIL EKJ04A INTEGRAL ATTACHMENT VT-1 D-A 01.10 EKJ04A-SUP-2 KJ-01-01 SHT. 1 LUBE OIL EKJ04A INTEGRAL ATTACHMENT VT.1 O-A D1.10 FKJ08A-SUP-1 KJ-01-01 SHT. 2 MAIN LUBE OIL STRAINER A INTEGRAL ATTACHMENT VT-1 O-A 01.10 KJ-01-R015 KJ-01-01 SHT. 3 PIPING INTEGRAL ATTACHMENTS 26 VT-1 D-A 01.20 KJ-01-R015 KJ-01-01 SHT. 3 PIPING SUPPORT 26 VT-3 F-A F1.30 M-01 8-667-035 KJ-01-01 SHT. 2 PIPING SUPPORT 5 VT-3 F-A F1.30 KJ-01-R004 KJ-02-04 SHT. 4 PIPING SUPPORT 28 VT-3 F-A F1.30 EKJ04A-SUP-1 KJ-01-01 SHT. I LUBE OIL COOLER HX SUPPORT VT-3 F-A F1.40 EKJ04A-SUP-2 KJ-01-01 SHT. I LUSE OIL COOLER HX SUPPORT VT.3 F-A F1.40 FKJ08A-SUP-1 KJ-01-01 SHT. 2 MAIN LUBE OIL STRAINER A SUPPORT VT-3 F-A F1.40 WCRE-16 4.1.16 Standby Diesel Generator Systems (KJ) Revision 0 Page 6 of 6

M A~ WOLF CREEK GENERATING STATION l; THIRD INTERVAL ISI PROGRAM PLAN 4.2 WCGS SYSTEMS SUBJECT TO SECTION XI PRESSURE TESTING ONLY A. Applicable System Piping and Instrument Drawings The following systems (or portions of systems) are subject to Section XI Pressure Testing only:

4.2.1 Reactor Coolant System (M-12BB04)

A 4.2.2 Chemical and Volume Control System (M-12BG02) 0 4.2.3 Chemical and Volume Control System (M-12BG04)

O 4.2.4 Chemical and Volume Control System (M-12BG05) 6 4.2.5 Fuel Pool Cooling and Clean-Up System (M-12ECOI) 4.2.6 Fuel Pool Cooling and Clean-Up System (M-12EC02)*

4.2.7 Miscellaneous Buildings HVAC (M-12GFOI) 4.2.8 Fuel Building HVAC (M-12GG02) 4.2.9 Control Building HVAC (M-12GKOI) 4.2.10 Auxiliary Building HVAC (M-12GK03) 4.2.11 Auxiliary Building HVAC (M-12GLOI, M-12GL02, M-12GL03) 4.2.12 Containment Hydrogen Control System (M-12GSO1)*

4.2.13 Liquid Radwaste System (M-12HBOI)*

4.2.14 Emergency Fuel Oil System (M-12JE0l) 4.2.15 Compressed Air System (M-12KA05 Class 3 Components) 4.2.16 Auxiliary Building Floor & Equipment Drain System (M-12LF03) 4.2.17 Nuclear Sampling System (M-12SJiO) 4.2.17 Nuclear Sampling System (M-12SI04)

• Except for ASME Class 2 components listed in Section 4.3 B. Classification OfComponents Details of the classification of the components subject to ASME Section Xl System Pressure Testing are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

C. Applicable ASME Class Components A listing of the ASME Class components subject to ASME Section Xl System Pressure Testing is included in 'Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

D. System Pressure Testing In accordance with Section Xl, IWA-5000 and IWB-5000, the Class I pressure retaining components included on the P&lDs of Section A will receive a system leakage test per IWB-5220 prior to plant startup following each refueling outage.

In accordance with Section Xl, IWA-5000 and IWC-5000, the Class 2 pressure retaining components included on the P&lDs of Section A will receive a system leakage test per IWC-5220 each inspection period.

In accordance with Section Xl, ]WA-5000 and IWD-5000, the Class 3 pressure retaining components included on the P&lDs of Section A will receive a system leakage test per IWD-5221 every period and a system hydrostatic test per IWD-5222 at or near the end of the interval. As allowed by Code Case N-498-4, alternative rules may be employed in lieu of the system hydrostatic test of IWD-5222.

Procedures used to perform System Pressure Testing are listed in Table 4.2.1 WCRE-1 6 4.2 Systems Subject to Section Xl Pressure Testing Only Revision 0 Page 1 of 3

I M

A WOLF CREEK GENERATING STATION THIRD INTERVAL 1SI PROGRAM PLAN E TABLE 4.2-1 SYSTEM PRESSURE TESTING PROCEDURES D

0. Procedure Number Procedure Title 1 STS PE-021 A Train A Emergency Diesel Fuel Oil and Keep Warm System STSPE02 IA Pressure Test

/ STS PE-021 B Train B Emergency Diesel Fuel Oil and Keep Warm System E-02I B STS Pressure Test Train A Emergency Diesel FO, LO, J Wtr, lntclr, Roc Arm, STS PE-021C Crank Vac, Air In & Exh 0* STS PE.02 ID Train B Emergency Diesel FO, LO, J Wtr, Intclr, Roc Arm, Crank Vac, Air In & Exh 0 STS PE-021 E Train A Emergency Fuel Oil Transfer System Pressure Test

? STS PE-021 F Train B Emergency Fuel Oil Transfer System Pressure Test STS PE-021 G Train A Emergency Diesel Air Start System Pressure Test STS PE-021 H Train B Emergency Diesel Air Start System Pressure Test STS PE-040A Reactor Coolant System Pressure Test STS PE-040C Reactor Coolant Sys:em Pressure Test (10 Year)

STS PE-040E RPV Head Bare Metal Inspection STS PE-04 IA Steam Generator System Pressure Test (Ctmt)

STS PE-041 D Steam Generator System Pressure Test (Non-Ctmt)

STS PE-042A CVCS Normal Ops (Ctmt)

STS PE-042B CVCS VCT Tank Room STS PE-042C Chemical and Volume Control System NCP Discharge Header STS PE042 HeaPressure Test STS PE-042D Chemical and Volume Control System CCP A Discharge STSP-042D Header Pressure Test STS P-042E Chemical and Volume Control System CCP B Discharge Header STSP.042E Pressure Test STS PE-042F CVCS Normal Ops (Aux Bldg)

STS PE-042G L/D Reheat Heat Exchanger STS PE.042H CVCS Excess Letdown Piping Pressure Test STS PE-0421 CVCS Boric Acid Tank A and Boric Acid Transfer Pump A STSPressure Test STSP-042J CVCS Boric Acid Tank B and Boric Acid Transfer Pump B STSP-0423 Pressure Test STS PE-042K CVCS Immediate Borate Test STS PE-043A RHR Train A STS PE-043B Residual Heat Removal System Hot Leg Discharge and CCP/SI T EPump Cross Connection Pressure Test STS PE-043C RHR Train B Normal Ops STS PE-043D RHR L/D and Hot Leg Cross-tie STS PE-044A High Pressure Safety Injection System Pressure Test STS PE-044C High Pressure Safety Injection System Pressure Test STS PE-044D High Pressure Safety Injection System Pressure Test STS PE-044E SI Cold Leg Inj, P-518, P-92 STS PE-044F SI Pump A STS PE-044G SI Pump B STS PE-045A Containment Spray Train A STS PE-045B Containment Spray 1'rain B STS PE-046 Safety Injection Accumulator Pressure Test STS PE-047A Compressed Air System Auxiliary Feedwater Control/Main Steam Atmosphere Relief Valves Accumulator Pressure Test WCRE-16 4.2 Systems Subject to Section XI Pressure Testing Only Revision 0 Page 2 of 3

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN TABLE 4.2-1 SYSTEM PRESSURE TESTING PROCEDURES (Continued)

STS PE-048A Fuel Pool Cooling Train A STS PE-048C Refueling Pool Skimmer System Pressure Test STS PE-048D Fuel Pool Cooling Train B STS PE-049A Essential Service Water System A Train Pressure Test STS PE-049B Essential Service Water System B Train Pressure Test STS PE-049C A Train Underground Essential Service Water System Piping

_____ ____ Flow Test STS PE-049D B Train Underground Essential Service Water System Piping PCo _ Test onClgaryeP PeeFlow STS PE-050A Component Cooling Water System PEGOIA Pressure Test STS PE-050B Component Cooling Water System PEGOIC Pressure Test STS PE-050C Component Cooling Water System PEGOIB Pressure Test STS PE-0501) Component Cooling Water System PEGOID Pressure Test STS PE-050E Pressure Test of CCW1 System RHR Heat Exchangers, and in Containment Service Loop STS PE-051 Borated Refueling CWater Storage Pressure Test STS PE-052A Auxiliary Feedwater Pump Turbine Pressure Test STS PE-053A A Train Auxiliary Feedwater Pressure Test STS PE-053B Auxiliary Feedwater Pressure Test Using Turbine Driven AFW Pump STS PE-053C Essential Service Water To Auxiliary Feedwater Pressure Test STS PE-053D Auxiliary Feedwater Pressure Test Using Condensate Storage Tank STS PE-053E B Train Auxiliary Feedwater Pressure Test STS PE-055E Containment Hydrogen Analyzer A Piping through P-101 and P-97 Pressure Test STS PE-055F Containment Hydrogen Analyzer B Piping Through P-99 and P-56 Pressure Test STS PE-055G Pressure Test of Containment Hydrogen Control Piping Through P-101 and P-97 STS PE-055H Pressure Test of Containment Hydrogen Control Piping Through STS P.055H P-99 and P-56 STS PE-055Q Pressure Test of Flocr and Equipment Drain Piping Between LF HV-105 and LF HV-106 STS PE.055W

_____PE__055W __and P-93 Test of Nuclear Sampling Piping through P-64, P-69, Pressure WCRE-16 4.2 Systems Subject to Section Xi Pressure Testing Only Revision 0 Page 3 of 3

WOLF CREEK GENERATING STATION THIRD INTERVAL ISI PROGRAM PLAN 4.3 WCGS SYSTEMS EXCLUDID FROM SECTION XI PRESSURE TESTING PER IWA-51I10(c)

A. Applicable Components The following ASME Class 2 components are excluded from Section XI System Pressure Testing per IWA-5 1 0(c):

P&ID Number Line Number(s) Penetration M-12BB302 BB-103-liCB-1" P-62 M-1 2BLOI BL-028-l3CB-3" P-25 M-12BMOI BM-053-HBB-3" P-78 M-12EC02 EC-067-HCB-6" P-53 M-12EC02 EC-072-IICB-6" P-54 M-12EC02 EC-081-11CB-3" P-55 M-12EMOI EM-071 -BCB-314" P-92 M-12GPOI GP.00 I -I0BB-6" P-34 M-12GPOI GP-003-HBB-I " P-51 M-12GPOI GP-005-HBB-I" P-51 M-1I20SO I GS-025-11BB-6" P-65 M-12GTOI GT-007-HBB-36" V-160 M-12GTOI GT-004-HBB-36" V-161 M-12GTOI GT-029-HBB-18" V-161 M-12GTOI GT-034-HBB-18" V-160 M-1 2GTOI GT-033-.IBB-1 8" V-160 M-1 2GTOI GT-030-I IBB-18" V-161 M-12HBOI30 HB-015-]iCB-3" P-26 M-12HBOI HB-025-liBB-3/4" P44 M-121-DOI HD-015-liBB-2" P43 M-12KAOI KA-244-l-ICB-1 1/2" P-30 M-l12KAOI KA-259-1iCB-I 1/2" P-30 M-12KA02 KA-051-IB-I34" P-63 M-12KA02 KA-261 --IBB-I" P-63 M-12KAOS KA-732-IBB-I" Personnel Hatch M-12KA05 KA-7334IIBB-1" Personnel Hatch M-12KBOI KB-00l-HCB-2" P-98 M-12KC02 KC-560-1BB34" P-67 M-12LF09 LF-842-HCB-6" P-32 B. Classification Of Components Details of the classification of the components that are excluded from Section XI System Pressure Testing Per IWA-51 10(c)are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

C. ASME Class Components A listing of the ASME Class 2 components excluded from Section XI System Pressure Testing Per IWA-51 10(c) is included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 3".

WCRE-16 4.3 WCGS Systems Excluded From Section XI Pressure Testing Revision 0 Per IWA-5I 10(c)

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