View source for ET 16-0005, Inservice Inspection Plan and 10 CFR 50.55a Requests 14R-01 and 14R-02 for the Fourth Inservice Inspection Program Interval

{{Adams
| number = ML16061A072
| issue date = 02/23/2016
| title = Inservice Inspection Plan and 10 CFR 50.55a Requests 14R-01 and 14R-02 for the Fourth Inservice Inspection Program Interval
| author name = Mccoy J
| author affiliation = Wolf Creek Nuclear Operating Corp
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000482
| license number = 
| contact person = 
| case reference number = ET 16-0005
| document type = Inservice/Preservice Inspection and Test Report, Letter type:ET
| page count = 243
}}

=Text=
{{#Wiki_filter:W~FCREEK      SNUCLEAR OPERATING CORPORATION February 23, 2016 Jaime H. McCoy Vice President Engineering ET 16-0005 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

==Subject:==
Docket No. 50-482: Wolf Creek Generating Station Inservice Inspection Plan and 10 CFR 50.55a Requests 14R-01 and 14R-02 for the Fourth Inservice Inspection Program Interval.
Gentlemen:
Pursuant to American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code Section XI, IWA-1400(c), Wolf Creek Nuclear Operating Corporation (WCNOC) is submitting, for information only, the Inservice Inspection (ISI) Program Plan for the fourth 10-year ISI interval at Wolf Creek Generating Station (WCGS). The ISI Program Plan is included as Enclosure I of this submittal. The fourth 10-year ISI interval began September 3, 2015.
Pursuant to 10 CFR 50.55a(z)(1), WCNOC hereby requests approval by the Nuclear Regulatory Commission (NRC) of 10 CFR 50.55a Request 14R-01 for the fourth 10-year inspection interval of WCNOC's ISI Program, which is included as Attachment I to this submittal. Request 14R-01 requests the continued application of an alternative risk-informed methodology in selecting Class 1 and Class 2 piping welds for examination during the fourth inspection interval. To support this request, Enclosure II of this submittal contains the gap assessment completed by Westinghouse on the WCGS internal events probabilistic risk assessment.
Pursuant to 10 CFR 50.55a(z)(2), WCNOC hereby requests NRC approval of 10 CFR 50.55a Request 14R-02 for the fourth 10-year inspection interval of WCNOC's ISI Program, which is included as Attachment II to this submittal.                        Request 14R-02 requests relief from the requirements of ASME Code Section XI, 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.
WCNOC requests approval of 10 CFR 50.55a Requests 14R-01 and 14R-02 prior to February 28, 2017.
P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831            1ji  .
An Equal Opportunity Employer M/F/HCNVET

ET 16-0005 Page 2 of 2 This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4156, or Cynthia R. Hafenstine (620) 364-4204.
Sincerely, Jaime H-.McCoy JHM/rlt Attachments: II 10 CFR 50.55a Request Number 14R-01 10 CFR 50.55a Request Number 14R-02 II

==Enclosures:==
Wolf Creek Generating Station Inservice Inspection Program Plan Wolf Creek Unit 1 Internal Events PRA Gap Assessment to Support RI-ISI cc:   M. L. Dapas (NRC), wia, wie C. F. Lyon (NRC), wla, wie N. H. Taylor (NRC), w/a, wie Senior Resident Inspector (NRC), w/a, wie

Attachment I to ET 16-0005 Page 1 of 11 Wolf Creek Nuclear Operating Corporation 10 CFR 50.55a Request 14R-O1 Request for Alternative to Selection and Examination Requirements for Class 1 and 2 Piping Welds.

Attachment Ito ET 16-0005 Page 2 of 11 10 CFR 50.55a Request Number l4R-O1 Proposed Alternative In Accordance with 10 CFR 50.55a(z)(1)
Alternative Provides Acceptable Level of Quality and Safety
: 1. ASME Code Component(s) Affected All Code Class I and 2 piping welds previously subject to the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section Xl, Table IWB-2500-1 (Examination Categories B-F and B-J) and Table IWC-2500-1 (Examination Categories C-F-I and C-F-2).
: 2. Applicable Code Edition and Addenda ASME B&PV Code, Section Xl 2007 Edition with 2008 Addenda.
: 3. Applicable Code Requirement ASME Section Xl, Tables IWB-2500-1 and IWC-2500-1 for Examination Categories B-F, B-J, C-F-I and C-F-2 stipulate the selection and examination requirements for Class I and 2 piping welds.
: 4. Reason for Request ASME Section X1 Examination Categories B-F, B-J, C-F-I, and C-F-2 originally contained the requirements for the nondestructive examination of Class I and 2 piping welds. In 2001, a risk-informed (RI) methodology for the inservice inspection (ISI) of Class I and 2 piping welds was applied at the Wolf Creek Generating Station (WCGS).
The RI-ISI process used in this application is described in Electric Power Research Institute (EPRI) Topical Report (TR) 112657, Revision B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure" (Reference 1). 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" (Reference 2).
This RI 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" (Reference 3) and Regulatory Guide 1.178, "An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping" (Reference 4).
The original RI-ISI template, "Risk-Informed Inservice Inspection Program Plan - Wolf Creek Generating Station (Revision 1)" was submitted to the NRC for approval for use during the second ISI interval. The approval was documented in a letter dated December 13, 2001 (ADAMS Accession No. ML013200130).

Attachment I to ET 16-0005 Page 3 of 11 A request to continue to use the RI-ISI methodology on Class 1 and 2 piping welds for the third ISI interval was submitted to the NRC for approval in WCNOC Letter ET 06-0010 dated March 2, 2006 (ADAMS Accession No. ML060720142). This request was approved by the NRC in a letter dated February 21, 2007 (ADAMS Accession No. ML070260538). The purpose of this current request is for the continued application of the RI-ISI methodology on Class 1 and 2 piping welds during the fourth IS1 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 RI-ISI criteria of EPRI TR-112657 during the fourth 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-I and C-F-2).
When WCNOC submitted the 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, Nuclear Energy Institute (NEI) 04-05, "Living Program Guidance To Maintain Risk-Informed Inservice Inspection Programs For Nuclear Plant Piping Systems" (Reference 5) has been developed. As part of the ISI Program Update for the fourth ISI interval at WCGS, an 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 WCGS RI-ISI application as it enters the fourth 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

Attachment I to ET 16-0005 Page 4 of 11
            - Programmatic Changes
            - Procedural Changes
* Changes in Postulated Conditions
            - Physical Conditions
            - Programmatic Conditions The RI-ISI Living Program Evaluation at the end of the third 1SI interval noted the following issue being addressed in the RI-ISI application:
         *In 2015, the Wolf Creek Consequence Evaluation was revised. In the resulting revision, several segments changed consequence rank, causing many welds to change Risk Category and, in most cases, Risk Rank. Table 1 shows a brief summary how many welds changed Risk Rank, and how the Element Selection was updated.
_____ ____       Table_        __  _ _   _ _ _ _  _  _
Change in Risk Rank         Weld Count         Element Selection Low to Medium                259                28 added Medium to High                 16                 2 added Medium to Low                 17                1 removed During the update of the WCGS ISI Program in preparation for the fourth 1SI interval, various 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 Consequence Evaluation revision described above and other minor corrections using the applicable portions of the same RI process that originally established the RI 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 remained within the allowable bounds after incorporating 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.
A summary table of the welds in the RI-ISI Program showing all changes since the original RI-ISI application is provided in Table 2. A summary of the current WCGS PRA update is included in the Appendix to this Request.
Enclosure II to this submittal contains the completed gap assessment on the WCGS internal events probabilistic risk assessment. This assessment determined whether the current model of record meets the supporting requirements in Table 2-2 of EPRI TR 102467-A to support the WCGS 10-year RI-ISI update.

Attachment I to ET 16-0005 Page 5 of 11
: 6. Duration of Proposed Alternative This 10 CFR 50.55a Request is being proposed for use during the fourth inspection interval for WCGS that began on September 3, 2015 and ends on September 2, 2025.
: 7. Precedents The proposed alternative in this 10 CFR 50.55a Request was submitted to the NRC for approval for WCGS' third 10-year ISI interval as Request 13R-01 in WCNOC letter ET 06-0010, dated March 2, 2006 (ADAMS Accession No. ML060720142). This was supplemented by letters dated October 5 and December 20, 2006 (ET 06-0043 and ET 06-0058) (ADAMS Accession Nos. ML062910125 and ML063620090). NRC Approval was documented in a letter from D. Terao, USNRC, to R. A. Muench, WCNOC, 'Third 10-Year Interval Inservice Inspection Program Relief Request 13R-01 (TAC No.
MD0297)," February 21, 2007 (ADAMS Accession No. ML070260538).
: 8. References
: 1. Electric Power Research Institute (EPRI) Topical Report, TR-1 12657, Revision B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure," Final Report, December 1999.
: 2. ASME Code Case N-578-1, "Risk-Informed Requirements for Class 1, 2, and 3 Piping, Method B," Approved March 28, 2000.
: 3. NRC Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions On Plant-Specific Changes to the Licensing Basis,"
Revision 2, May 2011.
: 4. NRC Regulatory Guide 1.178, "An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping," Revision 1, September 2003.
: 5. NEI 04-05, "Living Program Guidance To Maintain Risk-Informed                Inservice Inspection Programs For Nuclear Plant Piping Systems," April 2004.

Attachment I to ET 16-0005 Page 6 of 11 Table 2 Inspection Location Selection Comparison Between ASME Section Xl Code and EPRI TR-112657 by Risk Category System
()   Category Risk Rank Consequence Rank     IDMs Failure Potential Rank IfCode Category 1 st Weld Approved RI-ISI Interval RI-ISI     Other (2) Weld New RI-ISI Interval ISIOhr2 2
Count                               Count        RISI        Ohr AB           4          Medium        High         None          Low       C-F-2      ---                              155            16              -
AB          6a            Low       Medium        None          Low      C-F-2    154              0-                                 --
AE AE(1) 2           High (High)      High TASCS (FAC)
Medium (High)
OF2 CF21
                                                                                         ---                               1 AE            2           High        High        TASCS        Medium     C-F-2    0              0()9          -                      6-AE            2           High        High           "1-T      Medium     C-F-2    0 (3           0~            -3       8             2-AE AE(1)     4         Medium (High)       Hih Hih(FAG)     None          Low (High)    CF2 CF2141      ---                              14             1 AE           4          Medium        High         None          Low      C-F-2    0-             0()4                                 1-AE       5a         Medium       Meim         TASCS        Medium     CF2       1 (3)         (High)                    (FAC)        (High)
AE       6a            Low (3AHih                  Medium        None          Low      C-F-2    108              0                    ----
AL          6a            Low       Medium        None          Low      C-F-2    0              o3)           -*     126             0-BB           2           High        High        TASCS,       Medium       B-J     11              3           -11                    3-
________              ___________         T                                                     ________              _______       ___l-r_
BB           2           High        High        TASCS        Medium       B-J      6              2           -6                     2-BB2                   High                      "I-,       Medium0                  40()0(40                                          4 BB(2)                (High)       High       (PWSCC)      (Medium)      B-F      ()0'-                                                           -
B-F    11(41          01(4)-
BB           2High                   High           "1-1      Medium                                                   19             6-B-J     20              6-BB4 BB(2)
Medium (High)
HihNone, Hih       (PWSCC)
Low (Medium)
B-F4)
B-3 0~            -(83

Attachment I to ET 16-0005 Page 7 of 11 Table 2 Inspection Location Selection Comparison Between ASME Section Xl Code and EPRI TR-112657 by Risk Category Risk                           Failure Potential              1 st  Approved RI-ISI Interval                  New Ri-ISI Interval Syst~em                          Con sequence                         Code                              _ _   _   _ _ _  _  _   _ _I 2
Iaeoy Rak          Rn          DMs         Rank   Category    onWeld       RI-ISI      Other( )       ConWeld      RISI         Ohr2 B-F     13(4           5 (4)-
BB          4        Medium         High       None         Low                                                        261            25 B-J     268             21-BB         6a         Low         Medium       None         Low      B-J       18             0----
BB         7a         Low           Low        None         Low      B-J        ---                                      18            0-BG          2         High          High      TASCS       Medium     B-J        9             2            -9                          3-BG          2         High          High        TT        Medium     B-J       9              3            -9                          2-B-J      26              3           -26                          3-BG          4        Medium         High       None         Low C-F-1     72              9            -73                         9-BG         5a        Medium       Medium        TTF      Medium      B-J       7              2----
B-J       12             0           -0                           0-BG         6a         Low         Medium       None        Low C-F-l     39              0           -39                          0-BG         6b         Low           Low         "1-1     Medium      B-J        -             -           -7                           0-B-J       0             0            -12                          0-BG        7a          Low           Low        None        Low C-F-i     18                                         16            0 BN          4        Medium         High       None        Low      C-F-i      3             0            -5                           0-BN         6a         Low         Medium       None        Low      C-F-i    122             0            -122                         0-EF        6a         Low         Medium       None        Low      C-F-2     26              0            -26                         0-

Attachment I to ET 16-0005 Page 8 of 11 Table 2 Inspection Location Selection Comparison Between ASME Section Xl Code and EPRI TR-112657 by Risk Category Risk                             Failure Potential            1 st Approved RI-ISI Interval         New RI-ISI Interval Syst~em             1           1Consequence                            Code Category       Rank           Rank        DMs         Rank   Category Weld         RI-ISI     Other (2) Weld      R-S             te     2 2
__   _   _- gyIIICount                                                                       Count     R-SI           ter EJ2Hg                      ihTASCS,             Medium     B-J      2           0              -2               0-EJ         2         High           High       TASOS       Medium     B-J      8           2             -8                2               -
B-J      4           1             -4                1               -
EJ         2High                    High         "U        Medium C-F-I    4            3             -5                3               -
B-J    22            3             -22               3               -
EJ         4        Medium          High        None         Low C-F-i  434            44            -432             44               -
B-J      2           0             -2                0               -
EJ        6a          Low          Medium       None         Low C-F-I     1           0             -1                0-EJ        7a         Low            Low         None         Low     C-F-1   47            0             -47               0-EM          2         High           High         Ui       Medium      B-J      8           0            -8                 0-B-J    20            3            -20                3-EM          4        Medium          High        None        Low C-F-i    2            0            -2                 0-EM         5a        Medium         Medium      IGSCC      Medium      B-J    20            2             -10               2-B-J   104            0             -82               0-EM         6a         Low           Medium       None        Low C-F-i  205            0             -220              0-EM         6b         Low            Low        IGSCC      Medium     C-F-I     0           0             -10               0-EM         7a         Low            Low         None         Low      B-J     0            0             -22               0-

Attachment I toET 16-0005 Page 9 of 11 Table 2 Inspection Location Selection Comparison Between ASME Section Xl Code and EPRI TR-112657 by Risk Category Systemn
()    Category Risk Rank Consequence Rank Failure Potential DMs          Rank J   Code Category 1 st Weld Approved RI-ISI Interval RI-ISI     Other  1 21 Weld New RI-ISI Interval RISI       Ohr2
                                             ~"I_____IjCount                                                                                  Count        RISI       Oer   2 C-F-1   38            0                        26             0 EN               6a            Low           Medium             None          Low          C-F-i   93            0            -128                       0-EN               7a            Low             Low              None          Low          C-F=-i   0             0           -9                         0-EP               4           Medium           High              None          Low           B-J    20            2            -20                        2-EP               5a          Medium          Medium            IGSCC        Medium          B-J    12            2            -12                        2-EP               6a            Low           Medium             None          Low           B-J    83            0            -89                        0-GS               7a            Low             Low              None          Low          C-F-2    2            0            -2                         0-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.

Attachment I to ET 16-0005 Page 10 of 11
: 3. Due to a change in ASME Section Xl 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 Code Case N-770-1 (MRP-1 39) as an augmented examination program.
PWSCC       = pressurized water stress corrosion cracking TASCS       = thermal stratification, cycling, and striping TT          = thermal transient FAC         = flow-accelerated corrosion

Attachment Ito ET 16-0005 Page 11 of 11 Appendix to 10 CFR 50.55a Request 14R-01 Wolf Creek Generating Station (WCGS) PRA Summary The WCGS probabilistic risk assessment (PRA) model used to evaluate the consequences of pipe rupture for the Risk-Informed Inservice Inspection (RI-ISI) Program assessment was the most current PRA model update. The WCGS PRA was originally developed to satisfy the requirement of Nuclear Regulatory Commission (NRC) Generic Letter 88-20 that each licensee perform an Individual Plant Examination (IPE) to search for plant specific severe accident vulnerabilities. The results of the WCGS PRA were submitted to the NRC, pursuant to this requirement, in September of 1992. The NRC issued a Staff Evaluation Report (SER) on the WCGS IPE Submittal in November of 1996. The SER on the IPE concluded that the WCGS PRA has met the intent of Generic Letter 88-20. Since completion of the WCGS IPE, the PRA model has been used to support numerous risk-informed applications. These include the following Technical Specification changes:
* Amendment No.155 "Increasing Flexibility in Mode Restraints (TAC No. MC2040)", issued October 7, 2004.
* Amendment No. 163 "Extended Diesel Generator Completion Times (TAC No. MC1257)",
issued April 26, 2006.
* Amendment No. 167 "Extended Containment Isolation Valve Component Times (TAC No.
MC3944)", issued September 28, 2006.
* Amendment No. 173 "Adopting TSTF-372 on Limiting Condition for Operation 3.0.8, Inoperability of Snubbers (TAC No. MD3816)", issued April 17, 2007.
In addition, the PRA model was used to support the Severe Accident Mitigation Alternatives Analysis performed as part of the Environmental Report submitted in WCGS' License Renewal Application (LIRA). This LRA was submitted on September 27, 2006. Renewed facility operating license No. NPF-42 was issued for WCGS on November 20, 2008.
In order to continue to use the PRA model as a tool to support plant programs, periodic updating of the model is necessary. The WCGS PRA model was recently updated in 2013 and again in 2015. These updates included numerous changes to the PRA model to reflect plant modifications, changes to plant specific and generic initiating event frequencies, import of initiating event frequencies for special initiators as fault tree solution files, changes to plant specific component failure rates and test and maintenance unavailability data, an in depth human reliability assessment, and expansion of the modeling scope for a number of systems previously modeled as single failure events.
The following WCGS PRA results were obtained with the updated model:
* Core Damage Frequency (CDF) = 2.98E-06/yr (excludes internal floods)
* Large Early Release Frequency (LERF) = 2.45E-07/yr As a result of the updates to the PRA model, both CDF and LERF lowered significantly.
However, the consequence rank of several individual segments did change, which resulted in an impact to the RI-ISI Program.

Attachment II to ET 16-0005 Page 1 of 6 Wolf Creek Nuclear Operating Corporation 10 CFR 50.55a Request 14R-02 Request for Relief from ASME Code Requirements Regarding Visual Examinations of Class I Supports, Other than Piping Supports

Attachment II to ET 16-0005 Page 2 of 6 10 CFR 50.55a Request Number 14R-02 Proposed Alternative In Accordance with 10 CFR 50.55a(z)(2)
Hardship or Unusual Difficulty Without a Compensating Increase in the Level of Quality or Safety
: 1. ASME Code Component(s) Affected ASME Code Class:           Code Class 1 Components:                Reactor Vessel Supports Component IDs:             RBB01-01 RBB01 -02 RBB01 -03 RBB01 -04
: 2. Applicable Code Edition and Addenda ASME B&PV Code, Section Xl 2007 Edition with 2008 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 percent of Class 1 supports, other than piping supports, be subject to a visual VT-3 examination once every inspection interval.
: 4. Reason for Request Pursuant to 10 CFR 50.55a(z)(2), relief is requested on the basis that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. Conformance with the applicable inservice inspection requirements would necessitate a design modification to the reactor pressure vessel supports and associated insulation/walk plate to allow 100 percent 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.

Attachment II to ET 16-0005 Page 3 of 6 The Wolf Creek Generating Station (WCGS) 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 these 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.
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.
A design change to the reactor pressure vessel supports and associated insulation/walk plate to allow 100 percent visual examination of the subject supports would be an extensive and costly modification. 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 a hardship without a commensurate increase in quality or safety.
: 5. Proposed Alternative and Basis for Use In lieu of implementing the requirements of Table IWF-2500-1, Category F-A, Item No.
Fl1.40, 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.
: 6. Duration of Proposed Alternative This 10 CFR 50.55a request is being proposed for use during the fourth inspection interval for WCGS that began on September 3, 2015 and ends on September 2, 2025.
: 7. Precedents Previous WCGS Approvals:
10 CFR 50.55a Request 12R-14 was submitted to the NRC for WCGS' second 10-year ISI interval in WCNOC letter WM 95-01 29, dated August 30, 1995. NRC approval was

Attachment II to ET 16-0005 Page 4 of 6 documented in a letter from W. H. Bateman, USNRC, to 0. L. Maynard, WCNOC, "Second Ten-Year Interval Inservice Inspection Program Plan and Associated Requests for Relief, Wolf Creek Generating Station (TAC No. M93381     )," dated  October 24, 1997.
10 CFR 50.55a Request 13R-04 was submitted to the NRC for WCGS' third 10-year ISI interval in WCNOC letter ET 06-0010, dated March 2, 2006 (ADAMS Accession No. ML060720142). NRC approval was documented in a letter from D. Terao, USNRC, to R. A. Muench, WCNOC, "Wolf Creek Generating Station           -  Related to Relief Request No. 13R-04 for the Third 10-Year Interval Inservice Inspection (TAC No. MD0299)," dated June 16, 2006 (ADAMS Accession No. ML061320061).
Other Nuclear Plants Approvals:
10 CFR 50.55a Request No. RR-20 was submitted to the NRC for the H.B. Robinson Steam Electric Plant, Unit 2 in a letter from Duke Energy, dated June 3, 2013 (ADAMS Accession No. ML1317A006). This submittal was supplemented by letter dated January 21, 2014 (ADAMS Accession No. ML14028A260). NRC approval was documented in a letter from L. M. Regner, USNRC, to W. G. Gideon, Duke Energy Progress, Inc., "H.B.
Robinson Steam Electric Plant, Unit 2    -  Request for Relief (RR-20) From ASME Code, Section Xl for the Fourth 10-Year Inservice Inspection Interval (TAC No. MF1967),"
dated June 23, 2014 (ADAMS Accession No. ML14162A094).
10 CFR 50.55a Request No. IR-2-58 was submitted to the NRC for the Millstone Power Station, Unit 3 in a letter from Dominion Nuclear Connecticut, Inc., dated April 19, 2010 (ADAMS Accession No. ML101130187). This submittal was supplemented by letter dated January 20, 2011 (ADAMS Accession No. 110250259).                  NRC approval was documented in a letter from H. K. Chernoff, USNRC, to D. A. Heacock, Dominion Nuclear Connecticut, Inc., "Millstone Power Station, Unit No 3        -  Issuance of Relief Requests IR-2-51 through IR-2-60 Regarding Second 10-Year Interval Inservice Inspection Program Plan (TAC. Nos. ME3809 through ME3818)," dated April 26, 2011 (ADAMS Accession No. ML110691154).

Attachment II to ET 16-0005 Page 5 of 6 (SEE FIGURE 2)
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Attachment I1to ET 16-0005 Page 6 of 6 WAUCWA'Y OVER cue INgJLA ,'lION Rv S
                                    ,'PO0 --
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Enclosure I Wolf Creek Generating Station Inservice Inspection Program Plan (200 Pages)

WCRE-3 0 REVISION 0 INSERVICE INSPECTION PROGRAM PLAN WOLF CREEK GENERATING STATION INTERVAL 4 Prepared By:     f*                                    /         11/12/15 Ralph Connell - ISI Coordinator                          Date Technical Review By:                                     /          11/12/15 Dennis Tougaw - 1ST Coordinator                         Date ANTI Review:                                   "                    11/16/15 Adam Grundleger - ANTI                                  Date Approval By:                           -~/                                   11/16/2015 Brian Dorathy - Supervisor                              Date Kay L Smith
                                                     * .*-.+.        Released by Document
                                                              *"''"*"Services. Release Date:
2015.11.23 16:49:09 -0600'

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN REVISION STATUS SHEET REVISION  AFFECTED PAGES             DESCRWPTION/COMMENTS 0           All                   Interval 4 Draft Issued For Final WCGS Review and Comment WCRE-30                ~~Page WCRE-30 1 of 41                                 Revision 0 Rvso

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE OF CONTENTS Section                                            Description                                                Pare REVISION STATUS SHEET................................................................................. 1 TABLE OF CONTENTS ...................................................................................... 2

==1.0     INTRODUCTION AND BACKGROUND==
 .................................................................. 4 1.1     Introduction 1.2     Background 2.0     BASIS FOR INSERVICE INSPECTION PROGRAM PLAN............................................. 7 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 Component/Component Support Scheduling 3.0      INSERVICE INSPECTION PROGRAM DESCRIPTION................................................ 22 3.1     ASME Section XI Requirements 3.2     Augmented ISI Requirements 3.3     ASME Section XI 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-30                                            ~Page WCRE-30 2 ofl                                            Revision 0 Reiio1

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE OF CONTENTS (Cont'd)
Effective Number Section                                        Description                                   of Pages in Section 4.0     WCGS SYSTEM INSERVICE INSPECTION PROGRAM PLANS...................................... 1 4.1     WCGS Systems Subject To Section XI NDE or Augmented NDE ............................... 1 4.1.1  Main Steam System (AB)................................................................... 7 4.1.2  Feedwater System (AE)..................................................................... 7 4.1.3  Auxiliary Feedwater System (AL) ......................................................... 6 4.1.4  Reactor Coolant System (BB)............................................................. 46 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) ..................................................... 14 4.1.11 High Pressure Coolant Injection System (EM)........................................... 11 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 TWA-S5110(c)................ 1 Tables Table 4.2-1    System Pressure Testing Procedures Attachments Attachment A Assessment of the Surface Condition of Dissimilar Metal Welds ....................... 3 WCRE-30                                          ~~Page WCRE-30 3 ofl                                                Revision 0 Reiio1

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN

==1.0   INTRODUCTION==
AN]) BACKGROUND

==1.1      INTRODUCTION==

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 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.
The 1S1 Program Plan was developed and is controlled by Wolf Creek Administrative Procedure AP 29A-002. This 1S1 Program Plan is effective from September 3, 2015 through September 2, 2025, which represents Wolf Creek's Fourth 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 the Containment Inservice Inspection Program Plan which is in accordance with Wolf Creek Administrative Procedure AP 29A-005.

==1.2     BACKGROUND==

A Construction Pernit 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, NPF-42, was issued on June 4, 1985 anid 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 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 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 10OCFR 50.55a in effect at that time referenced ASME Section XI, 1980 Edition with Addenda through the Winter 1981 Addenda (Section XI 80/W81) in paragraph (b)(2). The extent of the application of Section XI 80/W8 1 was limited by paragraph (2)(iv)(A) such that Section XI, 1974 Edition with Addenda through Summer 1975 Addenda (Section X1 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 X1 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.
Based on these 10 CFR 50.55a mandatory and optional requirements, the WCGS Section XI ISI Program Plan for the initial ten year interval was developed and documented in WCRE-07, Wolf Creek Generating Station ISI Program Plan Document.
WCRE-30                                1.0 Introduction and Background                             Revision 0 Page 4of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 1.2.2    Second Interval 1SI Program Pursuant to the Code of Federal Regulations, Title 10, Part 50, Section 55a, Codes and standards, (10CFR 50.55a), WCGS 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 XI, 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 XI174/S75 to examine ASIME Code Class 1 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 and documented in WCRE-1 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 1 and 2 piping welds. The RM-SI 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 1 and 2 piping welds (i.e., Examination Categories B-F, B-J, C-F-l and C-F-2 only). The RI-SI 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 was addressed in WCGS Basis Document No. WCRE-12.
1.2.3    Third Interval ISI Program Pursuant to the Code of Federal Regulations, Title 10, Part 50, Section 55a, Codes and standards,(10CFR 50.55a), WCGS 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, 2004 referenced ASME Section XI, 1998 Edition with Addenda through 2000 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 1 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 third ten year interval was developed and documented in WCRE-l16, Wolf Creek Generating Station Third Interval ISI Program Plan.
During the third interval, WCGS continued the implementation of a Risk Informed ISI (RI-ISI) Program Plan for ASME Code Class 1 and 2 piping welds.
WCRE-30                        1.0 Introduction and Background                             Revision 0 Page 5 of4l

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN The RI-ISI template submittal was approved by the NRC in the safety evaluation contained in a letter dated February 21, 2007 from the USNRC to Rick Muench (incoming correspondence 07-00115).
The scope of the RI-ISI program is limited to ASME Code Class 1 and 2 piping welds (i.e., Examination Categories B-F, B-J, C-F-i and C-F-2 only). The RM-SI program was developed in accordance with the methodology contained in the Electric Power Research Institute (EPRI) Topical Report (TR) EPRI TR-l112657, Revision B-A. Application of the R1-IS1 methodology was addressed in the WCGS Risk Informed Inservice Inspection Basis Document, WCRE-12.
1.2.4    References To The ISI Program Plan In Other WCGS Programs The examinations and tests performed in accordance with this 1S1 Program Plan and previous interval ISI program Plans support other WCGS Programs as follows:
1.2.4.1 USAR Section 18.3.4, Integrity of Systems Outside of Containment This USAR Section addresses the WCNOC Response to the NRC's Guidance Per NUREG-0737. The WCNOC response is included in Section 18.3.4.2, which references the ASME Section XI Inservice Inspection Program in Item 3.
1.2.4.2 USAR Chapter 18 Appendix A, License Renewal Commitments This USAR Appendix includes references to the ASME Section XI Inservice Inspection Program in Sections AI.l, A1.3, A1.7, A1.19, and A1.29.
1.2.4.3 Technical Requirements Manual The Technical Requirements Manual includes a reference to the Inservice Inspection Program in Section 5.5.6.
WCRE-30                         1.0 Introduction and Background                        Revision 0 Page 6 of 41

WOLF CREEK GENERATING STATION FOURTH 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 Fourth 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 Fourth Interval 1SI Program Update include the 10CFR50.55aFinal Rules published November 5, 2014 (79FR65776), and December 11, 2014 (7973461). The Final Rule published November 5, 2014 was effective December 5, 2014 and incorporated by reference ASME Section XI, 2007 Edition with the 2008 Addenda in paragraph (b)(2); this Final Rule included a maj or reformatting of 10CFR50.55a and also incorporated by reference Regulatory Guide 1.147, Revision 17. The Final Rule published December 11, 2014 was effective December 11, 2014 and included minor technical corrections.
Twenty nine (29) conditions are included in 10OCFR50.55a(b)(2) and are numbered (i) to (xxix).
In addition, six (6) conditions are included in 10OCFR50.55a(b)(3)(v). Each of these conditions were 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 XI 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 4", WCRE-32.
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) ISI program for WCGS once every ten year interval. The ISI 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 Fourth ISI Interval is defined to be from September 3, 2015 to September 2, 2025. Accordingly, based on a "lock in" date of September 3, 2014, the 2007 Edition with the 2008 Addenda of ASME Section XI is the version of Section XI that WCGS must meet for Fourth Interval.
Note that on the "lock in" date, September 3, 2014, the Final Rules listed in 2.1 above were not published. Accordingly, the version of 10CFR50.55a published in the Code of Federal Regulations on January 1, 2014 was utilized to determine the Fourth Interval Code of Record for WCGS, the 2007 Edition with the 2008 Addenda of ASME Section XI. This version of the Code of Federal Regulations included all Final Rules published up to and including September 3, 2014.
WCRE-30                         2.0 Basis For Inservice Inspection Program Plan                    Revision 0 Page 7 of 4l

WOLF CREEK GENERATING STATION FOURTH IThfERVAL ISI PROGRAM PLAN 2.1.3     ASME Section XI Code Cases Per 10 CFR 50.5 5a(g), ASME Section XI 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 "inser-vice Inspection Code Case Acceptability-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(z). The ASME Section XI Code Cases incorporated into the WCGS IST Program Plan are listed and discussed in Section 3.3.
2.1.4     Requests For Relief and Requests For Alternatives In cases where WCNOC has determined that ASMiE Section XI requirements are impractical to implement or has determined an altemnative 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(z)(l) or 10 CFR 50.55a(z)(2), as applicable.
Guidance for the preparation of 10 CFR 50.55a Requests was taken from Nuclear Energy Institute (NEI) White Paper "StandardFormatfor Requests from CommercialReactor Licensees Pursuantto J0 CFR 50.55a", Revision 1 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 CER 50.55a(g)(5)(iii). The submittal of this information will be referred to in this document as a Request for Relief.
The NET 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 altemnatives 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(z)(1) and 10 CFR 50.55a(z)(2), respectively. The submittal of this information will be referred to in this document as a Request for Alternative.
Per 10 CER 50.55a paragraphs and (g)(6)(i) and (z), the Director of the Office of Nuclear Reactor Regulation will evaluate Requests for Relief and Requests for Altemnatives per Paragraph (g)(5) and "..may grant such relief and may impose such altemnative 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 4 Requests for Relief and Requests for Altemnatives are included in Section 3.4.
WCRE-30                 2.0 Basis For Inservice Inspection Program Plan                   Revision 0 Page 8 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 2.2      Augmented ISI Requirements In accordance with 10 CFR 50.55a(g)(6)(ii), the NRC may require a licensee to follow an augmented inservice inspection program for systems and components for which they deem an added assurance of structural reliability is necessary.
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 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 Condition Report (CR) 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 The following text provides 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 4 is addressed by Request for Alternative No.
I4R-0 1. The 4 th Interval Risk-Informed Program Plan is presented in WCRE-3 1.
2.3.1    Initial RI-ISI Application ASME Section XI Examination Categories B-F, B-J, C-F-1, and C-F-2 originally contained the requirements for the nondestructive examination (NDE) of Class 1 and 2 piping welds. In 2001, a risk-informed methodology for the inservice inspection of Class 1 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."
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 Decision making Inservice Inspection of Piping".
WCRE-30                        2.0 Basis For Inservice Inspection Program Plan                   Revision 0 Page 9 of 41

WOLF CREEK GENERATING STATION FOURTH TINTERVAL ISI PROGRAM PLAN The original RI-ISI template, "Risk-Informed Inservice Inspection Program Plan - Wolf Creek Generating Station (Revision 0)" was submitted to the NRC for approval per 10CFR50.55a(a)(3)(i) in Letter No. ET 01-0009, dated February 15, 2001. 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 in Letter No. 01-00965, dated December 13, 2001 (TAC No. MB 1206). 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- 112657 provides the requirements for defining the relationship between the RI-ISI program and the remaining unaffected portions of ASME Section XI.
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 I tasks are provided in the following paragraphs.
Task 1: Scope and Exemption Determination Per EPRI TR-l112657 and ASME Code Case N-578, the EPRI risk-informed 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 and 2 systems. This corresponded to ASME Section XI Examination Categories B-F, B-J, C-F-l, 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 addressed in 1WB-1220 and IWC-1220, were not affected. Therefore, piping that was previously exempted per ASME Section XI remained exempt in the RI-ISI application.
Task 2: Conseqiuence 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).
WCRE-30                2.0 Basis For Inservice Inspection Program Plan                    Revision 0 Page 10 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Results of the consequence evaluation were ultimately summarized in the risk ranking tables that are discussed in Task 5.
Task 3: Deuradation 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- 112657. Once the degradation mechanisms were assigned to each piping segment in accordance with the EPRJ 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 checklist 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.
TABLE 2.3-1 DEGRAIDATION MECHANISM CATEGORIES Flow Accelerated Corrosion (FAG)
HIGHargeWater                                Hammer<'&deg; Thermal Fatigue (TASCS, Thermal Transients)
Stress Corrosion Cracking (IGSCC, TGSCC, MEDIUMSmallPWSCC,                                 ECSCC)
Localized Corrosion (MIC, Crevice Corrosion and Pitting)
Erosion-Cavitation No Degradation Mechanisms LOW                 None                                  Present (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 hanmmer events. Various plant documents were reviewed as part of this effort including Outage Summary Reports, Licensee Event Reports (LERs), and corrective action documents.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 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.
TABLE 2.3-2 RI-ISI RISK MATRIX Consequence Assessment                                    CONSEQUENCE CATEGORY
                                          ~CCDP                     and CLERP Potential Failure Potential                                  NONE          LOW        MEDIUM         HIGH Assessment                             f r* *HGH             LOW        MEDIUM           *.i'     _____"G.".
o           IH           (Cat. 7)      (Cat. 5)     ,          ___
uJ                       _    _     _  _     _    _ _        _ _  _
z    2       EDU            LOW           LOW        MEDIUM         HG OEDIU                (Cat. 7)      (Cat. 6)     (Cat. 5)    *.L2
                                      ,ow2           ,ow           Low            Low     MEDIUM O    ..      LO            (Cat. 7)      (Cat. 7)     (Cat. 6)    (Cat. 4) w*
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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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Task 7: Risk Impact Evaluation Once the element selection under Task 6 was completed, the new set of locations that will be inspected under the RI-ISI program were compared to the locations that were inspected per ASME Section XI prior to the application of the RI-S I methodology. A 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 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 inspection program result in either negligible increases in Core Damage Frequency and Large Early Release Frequency or actual decreases in the risk measurements. The risk impact evaluation was performed using a simplified risk quantification method as described in EPRI TR-l112657, 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: Program Submittal/Risk-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 recomimendations as determined by the RI-ISI application, and was prepared in accordance with a template for risk-informed inservice 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- 112657. 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-S I examinations in accordance with the Topical Report for Class 1 and 2 piping welds.
2.3.3    Examination Categories and Code Item Numbers As previously discussed, the requirements of EPRI Topical Report No. TR-1 12657 supersedes those of ASIME Section XI for Class 1 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-I1, and C-F-2) have been superseded. Since TR-1 12657 does not provide new Examination Category and Code Item Numbers, the format from ASME Section XI Code Case N-578-1 (now incorporated into ASME Section XI, Nonmandatory Appendix R) is utilized for the assignment of these new numbers. As such, Class 1 and 2 piping welds have been reassigned to Examination Category R-A and Code Item Nos. R1 .10 through R1 .20, as applicable.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 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 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" was developed. As part of the ISI Program Update for Interval 4, a RI-ISI Living Program Evaluation was performed.
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 WCRE-30                     2.0 Basis For Inservice Inspection Program Plan                       Revision 0 Page 14 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN During the update of the Wolf Creek 1S1 program in preparation for the fourth 151 interval, changes to the PRA, as documented in PSA-15-001, were identified. A number of these changes were in the conservative direction (i.e., Medium Consequence to Low Consequence), the rest of the changes involved moving from Low Consequence to Medium Consequence and from Medium Consequence to High Consequence.
Welds within Risk Segments which changed from Low to Medium Consequence went from a 0% required selection regime to a 10% required selection regime. Similarly, welds within Risk Segments which changed from Medium to High Consequence went from a 10% required selection regime to a 25% required selection regime. Finally, Risk Segments which changed from Medium to Low Consequence went from a 10%
required selection regime to a 0% required selection regime.
As a result of these identified changes, an Element Selection was held to select additional welds for examination as required. More information about these required changes can be obtained in WCRE-3 1.
No other programmatic changes were identified which resulted in the need to change the examination selection.
2.3.4.1 RI-ISI Program Ongoing Commitment In the response to an RAI to the initial RM-SI application, Wolf Creek conmmitted 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 RM-SI 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.
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WOLF CREEK GENERATING STATION FOURTH 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 pennitted. 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 the different methods of: VT-l, VT-2, VT-3, and VE.
The VT-1 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 affect operability or functional adequacy of constant load and spring type supports.
The VE examination is conducted per the augmented requirements of Code Cases N-722-1, N-729-1 and N-770-1, with the conditions of 10 CFR 50.55a(g)(6)(ii)(D), (E) and (F).
All Visual examinations are conducted per Article 9 of ASME Section V and the additional requirements of 1WA-22 10, or as required by the augmented program.
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 1S1 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 XI, paragraph IWA-2221. The examination of coated materials is conducted in accordance with Appendix I of Article 7 of ASME Section V.
Liquid penetrant examinations are conducted per Article 6 of ASME Section V, as required by ASME Section XI, paragraph 1WA-2222.
Eddy current examinations are conducted per Appendix lV, as required by ASME Section XI, paragraph IWA-2223, or as required by the augmented program.
Volumetric 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, or as required by the augmented program.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN For welds in the RI-ISI program, the volume inspected shall be per the recommendations of EPRI TR-l112657 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.
Examination 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 VIII. 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 (Note 1 and Note 2)
Procedure Number          J          Procedure Title QCP 20-50 1                    Solvent Removable Visible Dye Liquid Penetrant Examination QCP 20-502                     Magnetic Particle Examination AC/DC Yoke and AC Coil Techniques 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 QCP 20-541                     VT-3 Visual Examination PDI-UT-1                      PDI Generic Procedure for the Ultrasonic Examination of Ferritic Pipe Welds PDI-UT-2                      PDI Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds PDI-UT-3                      PDI Generic Procedure for Ultrasonic Through Wall Sizing in Pipe Welds PDI-UT-4                      PDI Generic Procedure for Ultrasonic Examination of Studs and Bolts From the Bore PDI-UT-5                      PDI Generic Procedure for Straight Beam Ultrasonic Examination of Bolts and Studs PDI-UT-6                      PDI Generic Procedure for the Ultrasonic Examination of Reactor Pressure Vessel Welds PDI-UT-7                      PDI Generic Procedure for the Manual Ultrasonic Through Wall and Length Sizing of Ultrasonic Indications in Reactor Pressure Vessel Welds WCRE-30                      2.0 Basis For Inservice Inspection Program Plan                         Revision 0 Page 17 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL IS1 PROGRAM PLAN TABLE 2.4-1 (Continued)
EXAMINATION PROCEDIJRES
[Procedure   Number                 Procedure Title PDI-UT-8                     PDI Generic Procedure for the Ultrasonic Examination of Weld Overlaid Similar and Dissimilar Metal Welds PDI-UT-l10                    PDI Generic Procedure for the Ultrasonic Examination of Dissimilar Metal Welds PDI-UT-1 1                    PDI Generic Procedure for the Ultrasonic Detection and Sizing of Reactor Pressure Vessel Nozzle to Shell Welds and Nozzle Inner Radius MT-7                      Magnetic Particle Examination PT-li                      Liquid Penetrant Examination UT-3                      Ultrasonic Examination of Nozzle Inner Radius Areas UT-il                      Ultrasonic Examination of Reactor Vessel Stud Hole Threads UT-92                      Ultrasonic Examination of Weld Overlaid Austenitic Pipe Welds UT-94                      Ultrasonic Examination of Ferritic Pipe Welds UT-95                      Ultrasonic Examination of Austenitic Piping Welds UT-96                      Ultrasonic Through Wall Sizing in Piping Welds UT-97                      Straight Beam Ultrasonic Examination of Bolts and Studs UT-98                      Ultrasonic Examination of Reactor Pressure Vessel Closure Head Welds and Adjacent Base Metal UT-99                      Manual Through Wall and Length Sizing of Ultrasonic Indications in Reactor Pressure Vessel Welds UT-100                     Ultrasonic Thickness Measurements and Surface Contouring UT-101                     Ultrasonic Examination of Reactor Coolant Pump Flywheels UT-103                     Ultrasonic Examination of Dissimilar Metal Piping Welds UT-105                     Ultrasonic Examination of Nuclear Coolant System Cast Austenitic Piping UT-i110                    Ultrasonic Examination of Vessel Welds and Adjacent Base Metal >
2.0" in Thickness UT-i1i2                    Ultrasonic Examination of Vessels Less Than 2" in Thickness PDI-ISI-254-SE-NB                Remote Inservice Examination of Reactor Vessel Nozzle to Safe End, Nozzle to Pipe, and Safe End to Pipe Using the Nozzle Scanner WDI-STD-101                    Head Vent J-Weld Eddy Current Inspection Procedure WDI-STD-1 14                   Head Vent ID Eddy Current Inspection Procedure WDI-STD-1 040                   Procedure for Ultrasonic Examination of Reactor Vessel Head Penetrations WDI-STD- 1041                   Reactor Vessel Head Penetration Ultrasonic Analysis Guidelines WCRE-30                    2.0 Basis For Inservice Inspection Program Plan                        Revision 0 Page 18 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE 2.4-1 (Continued)
EXAMINATION PROCEDURES
[Procedure Number         [Pr       ocedure Title WDI-STD-1042                     Procedure for Eddy Current Examination of Reactor Vessel Head Penetrations WDI-STD-146                     ET Examination of Reactor Vessel Pipe Welds Inside Surface WCAL-002                       Pulser / Receiver Linearity Procedure WDI-CAL-102                     Calibration Procedure for PCI Eddy Current Card LMT-07-PAUT-005                    Performance of Phased Array Instrument Screen Height and Amplitude Control Linearity Checks LMT-10-PAUT-002                    Manual Phased Array Ultrasonic Examination of Austenitic and Ferritic Piping Welds Notes:
: 1. The above Table is a list of currently approved procedures utilized for 1S1 examinations at WCGS. Each examination data record has the procedure and revision documented on that record.
In addition, the vaulted surveillance procedures (i.e. STS PE-300, STS PE-040-H) have a list of the examination procedures attached. These vaulted records and previous revisions of this document may be referenced to obtain historical information on examination procedures utilized.
: 2. The 1SI Engineer shall verify that the procedures utilized are the current revision.
2.5      Personnel Qualification Requirements Personnel performing nondestructive (NDE) examinations shall be qualified and certified using a written practice prepared in accordance with ANSI!ASNT CP-l189, dated 1995, as required by IWA-2300 of Section XI and as modified by 10 CFR50.55a(b)(2)(xviii).
Personnel performing Appendix VIII ultrasonic examinations shall meet the qualification requirements of Appendix VIII as modified by 10CFRS0.55a(b)(2)(xiv).
Personnel performing visual examinations or using other NDE methods not addressed in ANSI/ASNT CP-1 89, shall be qualified as defined in ANSI/ASNT CP-1 89 or the ASNT Central Certification Program (ACCP) and the Employer's written practice.
2.6      Inspection Intervals and Inspection Scheduling Inspection Intervals Per IWA-2430(a) of ASME Section XI, the inservice examinations and system pressure tests required by IWB, ]IWC, IWD and the inservice examinations and tests of LWF shall be completed during each of the inspection intervals for the service lifetime of the plant. The inspections shall be performed in accordance with the schedule of the Inspection Program of IWA-243 1.
Per IWA-2430(b), the inspection interval shall be determined by calendar years following placement of the plant into commercial service.
WCRE-30                      2.0 Basis For Inservice Inspection Program Plan                      Revision 0 Page 19 of4l

WOLF CREEK GENERATING STATION FOURTH INTERVAL IST PROGRAM PLAN Per IWA-2430(c), for components inspected under the Inspection Program of LWA-243 1, the following shall apply:
(1) Each inspection interval may be reduced or extended by as much as 1 year. Adjustments shall not cause successive intervals to be altered by more than one year from the original pattern of intervals. If an inspection interval is extended, neither the start and end dates nor the inservice inspection program for the successive interval need be revised.
(2) Examinations may be performed to satisfy the requirements of the extended period or interval in conjunction with examinations performed to satisfy the requirements of the successive period or interval. However, an examination performed to satisfy requirements of either the extended period or interval or the successive period or interval shall not be credited to both periods or intervals.
(3) That portion of an inspection interval described as an inspection period may be reduced or extended by as much as 1 year. This adjustment shall not alter the requirements for scheduling inspection intervals.
(4) The inspection interval for which an examination was performed shall be identified on examination records. Adjustments shall not cause successive intervals to be altered by more than one year from the original pattern of intervals.
Per IWA-2430(d), in addition to the interval adjustment allowed per IWA-2430(c), 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 IWA-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 1 components, Class 2 components, Class 3 components, and Class 1, 2, and 3 component supports, respectively.
Per IWB-24 10, inservice examinations and system pressure tests of Class 1 components may be performed during plant outages such as refueling shutdowns or maintenance shutdowns.
The term"ma" allows the examinations and system pressure tests to be performed during system operation. Per IWC-24 10, IWD-24 10, and IWF-24 10, 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-24 11, IWC-24 11, IWD-24 11, and IWF-2410. These paragraphs reference Tables IWB-241 1-1, IWC-241 1-1, IWD-241 1-1, and IWF-24 10-1, which include minimum and maximum percentages of examinations required to be completed by inspection period. Table 2.6-1 summarizes this information for Interval 4 at Wolf Creek.
Per IWB-241 1, examinations listed in IWB-241 1(a)(1) to IWB-241 1(5) as specified in Table TWB-2500-1 are not required to meet the criteria in Table IWB-241 1-1.
Per IWC-241 1, examinations listed in IWC-241 1(a) as specified in Table 1WC-2500-1 are not required to meet the criteria in Table IWC-24 11-1.
Per IWD-24 11, examinations listed in IWD-24 11(a) as specified in Table IWD-2500-1 are not required to meet the criteria in Table IWD-24 11-1.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Per IWB-241 1, 1WC-24 11 and IWD-24 11, 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 in any one period if there is only one item or component, in lieu of the requirements of Tables IWB-24 11-1, Tables IWC-24 11-1 and Tables 1WD-24 11-1, respectively.
TABLE 2.6-1 INSPECTION PROGRAM COMPONENT/COMPONENT SUPPORT SCHEDULING INSPECTION          INSPECTION PERIOD,           I       MINIMUM           I      MAXIMUM INTERVAL            CALENDAR YEARS OF IEXAMINATIONS                           EXAMINATIONS PLANT SERVICE             jCOMPLETED, % [COMPLETED, %1 4             316                                                 50 4                        37                           501                      75 4                        40                           100                      100 1If 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 2007 Edition with the 2008 Addenda of Section XI, Tables IWB-2500-1, IWC-2500-1, IWD-2500-l and IWF-2500-1, respectively, except for Categories B-F, B-J, C-F-l1, and C-F-2 welds which were selected in accordance with the RI-ISI Program requirements. The basis for selection of RM-SI welds is documented in 10 CFR 50.55a Request Number I4R-0 1.
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, 2007 Edition with the 2008 Addenda of Section XI. 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 IWA-4000 of ASMvE Section XI, 2007 Edition with the 2008 Addenda. XI and are implemented by WCGS Procedure AP 16A-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, repairs and replacements will be in accordance with Article IWA-6000 of ASME Section XI, 2007 Edition with the 2008 Addenda as modified by Code Case N-532-5.
WCRE-30                       2.0 Basis For Inservice Inspection Program Plan                       Revision 0 Page 21 of41

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 3.0     INSERVICE INSPECTION PROGRAM DESCRIPTION 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.
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 sunmnary of the IS1 Program Plan. Sections 3.3 and 3.4 include supporting details for ASME Section XI Code Cases and Requests for Relief and Requests for Alternatives Requests From ASME Section XI Requirements, respectively. Sections 3.5 through 3.11 provide additional information that describe and support this 181 Program Plan.
3.1       ASME Section XI Requirements Based on an ASME Section XI Code of Record "lock-in" date of September 3, 2014 (one year prior to the 4th Interval start date) and 10CFR50.55arequirements in effect at that time, this 1S1 Program Plan was developed in accordance with the requirements in the 2007 Edition with the 2008 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Subsections IWA, IWB, IWC, IWD, IWE, Mandatory Appendices, and the Inspection Program of IWA-243 1, except as follows:
NOTE: As delineated in AP 29A-002, the requirements for implementation of ASME Section XI, 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, that is governed by administrative procedure AP 29A-005.
3.1.1    Code of Federal Regulations Conditions The following mandatory and optional Code of Federal Regulations Conditions were included in 10CFR50.55a as of September 3, 2015. Only those 10CFR50.55a Conditions applicable to the 2007 Edition with the 2008 Addenda of Section XI are listed. These Conditions were reviewed for inclusion in the 1S1 Program and dispositioned as follows:
3.1.1.1     WCGS will not utilize the option in 10CFR50.55a(b)(2)(ii) to examine Class 1 piping per ASME Section XI, 1974 Edition with the Summer 1975 Addenda.
3.1.1.2     As required by 10CFR50.55a(b)(2)(x), WCGS will apply the station 10OCFR50 Appendix B Quality Assurance Program to Section XI activities.
3.1.1.3     As allowed by 10CFR50.55a(b)(2)(xiv), WCGS will use the annual practice requirements in VII-4240 of Appendix VII of Section XI in place of the 8 hours of annual hands-on training discussed in the first sentence of 10OCFR50.55a(b)(2)(xiv). As required by 10OCFR50.55a(b)(2)(xiv), if implementing the option in the first sentence, the annual practice requirements at WCGS will be performed on material or welds 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.
3.1.1.4     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-23 14(a) and IWA-23 14(b) of the 2007 Edition with the 2008 Addenda of Section XI WCRE-30                                    3.0 - 1S1 Program Description                             Revision 0 Page 22 of 4l

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 3.1.1.5      As required by 10CFR50.55a(b)(2)(xix), the provisions in LWA-4520(b)(2) and IWA-4521of the 2008 Addenda will not be used by WCGS.
3.1.1.6      As required by 10CFR50.55a(b)(2)(xx)(B), WCGS will apply the rules in IWA-4540(a)(2) of the 2002 Addenda of Section XI when performing system leakage tests after repair and replacement activities performed by welding or brazing on a pressure retaining boundary 3.1.1.7      As required by 10CFR50.55a(b)(2)(xxi)(A), the provisions of Table 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, Steam Generator Nozzle Inside Radius Section, of Inspection Program B in the 1998 Edition will be applied by WCGS. As allowed by 10CFR50.55a(b)(2)(xxi)(A), a visual examination with magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria in Table IWB-35 12-1, 2007 Edition with the 2008 Addenda, with a limiting assumption on the flaw aspect ratio (i.e., a/l=0.5), may be performed in place of an ultrasonic examination.
3.1.1.8      As required by 10CFR50.55a(b)(2)(xxii), WCGS will not apply the rules in IWA-2220, "Surface Examination," of Section XI, 2007 Edition with the 2008 Addenda that allow use of an ultrasonic examination method.
3.1.1.9      As required by 10CFR50.55a(b)(2)(xxvii), When performing visual examination in accordance with 1WA-5241 of Section XI of the ASME B&PV Code, 2007 Edition with the 2008 Addenda WCGS will remove insulation from 17-4 PH or 410 stainless steel studs or bolts aged at a temperature below 1100 0F or having a Rockwell Method C hardness value above 30, and from A-286 stainless steel studs or bolts preloaded to 100,000 pounds per square inch or higher.
3.1.1.10 As required by 10CFR50.55a(b)(2)(xxviii) WCGS will implement the following conditions when implementing Equation (2) of A-4300(b)(l) of Appendix A:
For R < 0, AKI depends on the crack depth (a), and the flow stress (of). The flow stress is defined by of= 1/2(o-ys + oult), where o-ys is the yield strength and oult is the ultimate tensile strength in units ksi (MPa) and a is in units in. (mam). For -2
        < R <0and Kmax -Kmin <0.8 x 1.12 of'1(xa), S~ l1and AKI =Kmax. For R<
        -2 and Kmax -Kmin < 0.8 x 1.12 of4*(na), S = 1 and AKI = (1 - R) Kmax/3.
For R< 0 and Kmax -Kmin > 0.8 x 1.12 of4l(2a), S5 1 and AKIl=Kmax -
Kmin.
3.1.1.11 As required by 10CFR50.55a(b)(2)(xxix), when implementing Nonmandatory Appendix R, "Risk-Informed Inspection Requirements for Piping," of Section XI, 2007 Edition with the 2008 Addenda, WCGS will request and receive prior NRC authorization of this proposed altemnative in accordance with paragraph 10CFR50.55a(z)(1).
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 3.1.2    ASMIE Section XI Code Cases Incorporated In The ISI Program Alternatives to ASME Section XI that are provided in Code Cases may be incorporated into the 1S1 Program as described below.
3.1.2.1 Section XI Code Cases Approved and Conditionally Approved in 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 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 10 CFR 50.55a(z). Code Cases being incorporated by WCGS during the fourth 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 1SI Program via a Request for Alternative or Request for Relief submitted to the NRC in accordance with 10 CFR 50.55a(z) or 10CFR50.55a(g)(5), respectively. Those alternatives being incorporated by WCGS during the fourth interval by a 10CFR50.55a Request are addressed in Section 3.4.
3.2     Augmented 1SI Requirements Augmented inservice inspection programs address examinations that go beyond what is required by ASME Section XI. 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 XI. Described below are the augmented ISI commitments at WCGS for the fourth 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.
3.2.1.1 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 These USAR Sections describe that WCGS complies with either USNRC Branch Technical Position MEB 3-1, or as required per the Risk-Informed 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. 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.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN The applicable welds are shown on the Main Steam (AB), Feedwater (AE),
Reactor Coolant (BB), Chemical and Volume Control (BG), Steam Generator Blowdown (BM), and Auxiliary Feedwater Pump Turbine (FC) System Isometrics listed in Sections 4.1.1, 4.l.2, 4.l.4, 4.1.5, 4.1.6, and 4.l.14, respectively, within the "No Break Zone" and included in the respective Component and Component Support Selected/Scheduled for Examination Tables.
Wolf Creek has implemented a Risk-Informed High Energy Line Break Program.
This program is maintained in WCRE-33, 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 Inteigrity 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 Item 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 0-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 XI or an approved alternative (e.g., approved Code Case or Request for Alternative). For the fourth interval, examinations on the Reactor Vessel Closure Studs will be conducted in accordance with Examination Category B-G-l, 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-l, BB-2 and BB-3.
3.2.1.4 USNRC Regulatory Guide 1.137, Revision 0 - Fuel-Oil Systems for 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 implementation of the testing and VT-2 examinations required by Articles 1WD-2000 and IWD-5 000 of ASME Section XI, 2007 Edition with the 2008 Addenda.
3.2.1.5 USNRC Regulatory Guide 1.150, Revision 1-Ultrasonic Testin2 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. 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 XI for those reactor vessel components that are examined in accordance with Article 4 of Section V.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN However; 10OCFR50.55a requires that, with the exception of the shell-to-flange weld and the head-to-flange weld, that the examination of the Reactor Vessel Welds be conducted in accordance with Appendix VIII. Although this Regulatory Guide was withdrawn by the NRC on February 11, 2008 based on full implementation of Appendix VIII (see Federal Register Volume 73, No. 28, Page 7766), this withdrawal does not, in and of itself, alter any prior or existing licensing commitment based on its use. Since the prescriptive guidance in Regulatory Guide 1.150 is not in total agreement with the Appendix VIII requirements, Regulatory Guide 1.150 remains applicable for the examination of the reactor vessel components that are not examined in accordance with Appendix VIII.
3.2.2    WCGS Augmented ISI Requirements The following augmented inservice inspection requirements are those resulting from WCGS commitments other than 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 Pressurizer Nozzle Weld Overlays In Interval 3, a full structural weld overlay was performed on the pressurizer nozzles-to-safe end dissimilar metal (DM) welds and the adjacent stainless steel (SS) safe end-to-piping welds. WCNOC revised the original commitment made in I3 R-05 as follows: Subsequent inservice examination of full structural repair weld overlays on the Pressurizer nozzle welds will be in accordance with the 2004 Edition with 2005 Addenda of ASME Section XI, Appendix Q, Q-4300 as prescribed in WCNOC Request I3R-05, Rev. 1 Table 5, page 27 of 28, attached to WCNOC letter ET 06-0044 dated October 2, 2006. Subsequent inservice examinations of preemptive full structural weld overlays on the Pressurizer nozzle welds will be as prescribed in WCNOC Request I3R-05, Rev. 1 Table 5, page 27 of 28, attached to WCNOC letter ET 06-0044 dated October 2, 2006.
Regulation 10 CFR 50.55 a requires that Class 1 DM welds be examined in accordance with Code Case N-770-
: 1. This includes welds mitigated by WOL. The examinations performed in accordance with I3R-05 also meet the examination requirements of Code Case N-770-l, Items C and F, as applicable.
Table 3.2.2.3-1 provides a listing of the location and designation of each of the overlaid welds. Table 3.2.2.3-2 lists the welds broken out into "Repair" or "Preemptive" categories. The Notes below are applicable to both tables.
Notes:
: 1. Full structural REPAIR weld overlay due to indications found.
: 2. Full structural REPAIR weld overlay due to <90% of required examination volume coverage.
: 3. PREEMPTIVE full structural weld overlay.
Table 3.2.2.3-1 Pzr location                          DM Weld!                          Associated Stainless weld!
Overlay Weld#                              Overlay weld#
Surge nozzle                       TBB03-1-W (1)                             BB-01-F004B (3)
_________                       MW7090-WOL-DM                             MW7090-WOL -SS Spray nozzle                       TBB03-2-W (3)                              BB-04-F001 (3)
MW7089-WOL-DM                              MW7089-WOL-SS "A" Safety nozzle                     TBB03-3-A-W (3)                            BB-02-F001A (2)
__________                      MW7086-WOL-DM                              MW7086-WOL-SS "B" Safety nozzle                     TBB03-3-B-W (3)                            BB-02-F005A (2)
MW7087-WOL-DM                              MW7087-WOL-SS "C" Safety nozzle                     TBB03-3-C-W (1)                            BB-02-F006A (2)
_________                      MW7088-WOL -DM                             MW7088-WOL -SS Relief nozzle                       TBB03-4-W (1)                              BB-02-F008 (2)
_________                       MW7085-WOL-DM                              MW7085-WOL-SS WCRE-30                                     3.0 - ISI Program Description                                 Revision 0 Page 26 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Table 3.2.2.3-2 Repair locations                                          Pre-emptive locations Examine 25% sampling                                         Examine 25% sampling TBB03-l-W (1)                                               TBB03-2-W (3)
MW7090-WOL-DM                                               MW7089-WOL-DM TBB03-3-C-W (1)                                             TBB03-3-A-W (3)
MW7088-WOL-DM                                               MW7086-WOL-DM TBB03-4-W (1)                                             TBB03-3-B-W (3)
MW7085-WOL-DM                                                MW7087-WOL-DM BB-02-F00 1A (2)                                             BB-01-F004B (3)
MW7086-WOE- SS                                              MW7090 -WOE- SS BB-02-F005A (2)                                               BB-04-F001 (3)
MW7087-WOL-SS                                               MW7089-WOL-SS BB-02-F006A (2)
MW7088-WOL-SS                           ______________________
BB-02-F008 (2)
MW7085-WOL-SS                           _______________________
As noted in Table 3.2.2.3-2, there are 3 "Repair" category locations for the DM welds, 4 "Repair" category locations for the SS welds, 3 "Preemptive" category locations for the DM welds, and 2 "Preemptive" category locations for the SS welds. Table 3.2.2.3-3 contains the information from Table 5 of letter ET 06-0044 as discussed above.
Table 3.2.2.3-3: Weld Overlay Inservice Examination Requirements Examination Description*                   Method          Technique         Reference         Acceptance Standards Full Structural Repair WOL: Weld             Volumetric       UT angle beam     ASME Section         Q-4300 overlay and outer 25% of the original DM                              per PDI       XI and Q-4300 weld thickness at least 0.5 inches beyond                           procedure the toes of the original DM weld and butter, and at least 0.5 inches beyond any as-found flaw, will be examined within the next two refueling outages. Re-examination will be on a sampling basis in accordance with Q-4300(b) through (f) and Q-43 10. These examination will be added to the ISI Program Plan in accordance with IWB-2412(b)(l).
Full Structural Repair WOL: Weld             Volumetric       UT angle beam     ASME Section         Q-4300 overlay and outer 25% of the original SS                              per PDI       XI and Q-4300 weld thickness at least 0.5 inches beyond                           procedure the toes of the original SS weld, and at least 0.5 inches beyond any as-found flaw, will be examined within the next two refueling outages. Re-examination will be on a sampling basis in accordance with Q-4300(b) through (f) and Q-431 0.
These examination will be added to the ISI Program Plan in accordance with IWB-2412(b)(1).
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Preemptive Full Structural WOL: If             Volumetric       UT angle beam   ASME Section       Q-4300 greater than or equal to 90% coverage of                              per PDI      XI and Q-4300 the original DM weld is achieved with                               procedure PDI qualified procedures and no service related indications are identified the weld overlay and outer 25% of the original DM weld thickness at least 0.5 inches beyond the toes of the original DM weld and butter will be examined on a sampling basis in accordance with Q-4300(b) through (f) and Q-43 10. These examination will be added to the ISI Program Plan in accordance with IWB-2412(b)( 1).
                                               +                 +                F               I Preemptive Full Structural WOL: If              Volumetric      UT angle beam   ASME Section       Q-4300 greater than or equal to 90% coverage of                              per PDI      XI and Q-4300 the original SS weld is achieved with PDI                             procedure qualified procedures and no service related indications are identified the weld overlay and outer 25% of the original SS weld thickness at least 0.5 inches beyond the toes of the original SS weld will be examined on a sampling basis in accordance with Q-4300(b) through (t) and Q-43 10. These examination will be added to the ISI Program Plan in accordance with IWB-2412(b)(I).
*This is a general examination description to be performed; it does not identify all requirements for performing the examinations. As noted on page 6 of 28 of 10 CFR 50.55a Request I3R-05, Revision 1, submitted by letter ET 06-0031, the examination requirements comply with non-mandatory Appendix Q except as noted.
3.2.2.2 MR!P-192 The MRP issued letter MRP 2007-04 1, which contains document MRP-192, "Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants". This document contains recommendations classified as "good practice" as defined by NEI 03-08 Implementation Protocol. The recommendations of this document were evaluated and documented in Condition Report 2007-000979. The initial examinations were performed in RE-i16, and re-performed on a 6 year frequency.
In 2015, the MIRP issued letter 2015-019 that contains a good practice per NEI 03-08. This good practice is to include the welds of the mixing tee to the upstream piping. The evaluation of this recommendation is documented in CR 96696. The following criteria apply for performing the examinations:
* The inspection zone of the RH-R mixing tees should include all welds within at least four intemnal pipe diameters downstream from the mixing tee junction point, including the mixing tee downstream weld.
* The inspection zone should also include the welds of the mixing tee to the upstream piping.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL 1ST PROGRAM PLAN
           *Personnel performing the examination should receive training on the EPRI-developed thermal fatigue detection technology using the computer-based training module for thermal fatigue cracking and crazing inspection, as referenced in MRP- 192.
3.2.2.3 Code Case N-729-1 In accordance with 10 CFR 50.55a(g)(6)(ii)(D), all PWR licensees shall augment their inservice inspection program with ASME Code Case N-729- 1 and the conditions specified in (g)(6)(ii)(D)(2) through (6) of 10 CFR 50.55 a by December 31, 2008. These requirements were initially implemented during Interval 3.
3.2.2.4 Code Case N-722-1 In accordance with 10 CFR 50.55a(g)(6)(ii)(E), all PWR licensees shall augment their inservice inspection program with ASME Code Case N-722 and the conditions specified in (g)(6)(ii)(E)(2) through (4) of 10 CFR 50.55a. It is required that for inspections to be conducted every refueling outage and inspections conducted every other refueling outage, the initial inspection shall be performed at the next refueling outage after January 1, 2009.
These requirements were initially implemented during Interval 3.
3.2.2.5 MVRP-146 The evaluation for Report MRP-146, Thermal Fatigue in Normally Stagnant Non-Isolable RCS Branch Lines is documented in WCRE-25, Program Plan for Management of Thermal Fatigue. There are four locations did not screen out for thermal fatigue degradation. These locations were required to be examined prior to the end of the next refueling outage beginning after January 31, 2009 (RF 17) per the original guidance of MRP-146. Revision 1 of MRP-146 gives the option of performing periodic inspections on locations that do not screen out per the MRP-146 guidance. Lines with the UH/H configuration that are screened as susceptible to thermal fatigue are to be inspected every refueling outage (RFO) beginning with the first RFO after January 31, 2012 (RF 19). Lines with the DH configuration that are screened as susceptible to thermal fatigue are to be inspected every other RFO beginning with the first REO after January 31, 2012 (RF 19). In 2015, the IvRP issued letter 2015-019 that contains a "Needed" requirement per NEI 03-08. This needed requirement is to perform a "One time" examination of UK configured piping greater than 2 NPS and not larger than 4 NPS and having the potential of previous cold in-leakage. This examination shall be performed not later than the first refueling outage commencing after June 1, 2016 (RF2 1). The evaluation of this "Needed" action is documented in CR 96696.
3.2.2.6 Dissimilar Metal Weld Surface Assessment Incoming correspondence 09-00324 documents the letter that provides notice that EPRI report 1018181, "Guideline for Conducting Ultrasonic Examinations of Dissimilar Metal Welds," has been issued. The purpose of this document is to provide guidance for nuclear power plant (NPP) owners in planning and executing welds examinations in a manner that will minimize the occurrence of significant human errors and to assure completion of the planned examination scope. This guideline is applicable to welds that are scheduled for examination WCRE-30                 3.0 - ISI Program Description                             Revision 0 Page 29 of 4l

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN The NPP owner is responsible for compliance with the one "Needed" requirement in the report that is in accordance with NEL 03-08. The "Needed" requirement is described as follows:
* Needed: The utility shallprepare, maintain, and execute a surface condition assessment and improvementprocess, as part of itsprogramfor dissimilar metal weld examinations.
Condition Report 18089 documents this requirement. Attachment A of this program plan provides the documentation of the required process.
3.2.2.7 Code Case N-770-1 In accordance with 10 CFR 50.55a(g)(6)(ii)(F), all PWR licensees shall augment their inservice inspection program with ASME Code Case N-770-l and the conditions specified in (g)(6)(ii)(F)(2) through (10) of 10 CFR 50.55a. Per the regulation, the Code Case and the applicable conditions shall be implemented by the first refueling outage after August 22, 2011, which for Wolf Creek was Refueling Outage RF 19.
The baseline examinations were required to be completed by the end of the next refueling outage after January 20, 2012; however, previous exams could be credited for baseline examinations if they were performed within the re-inspection period specified in Table 1 of the Code Case using Appendix VIII requirements and met the Code required examination of essentially 100 percent, or had NRC approval of alternative inspection requirements.
The previous exams performed under MIRP-1 39, along with the NRC approved Relief Request I3R-06, met the baseline requirements.
As noted in Section 3.2.2.1, the overlaid nozzle-to-safe end dissimilar metal welds on the pressurizer were examined in accordance with approved Relief Request I3R-05 during Interval 3. The examinations performed in accordance with I3R-05 also meet the requirements of Code Case N-770- 1, Items C and F, as applicable.
          *Note that the VE examinations required by this Code Case are encompassed by the VE examinations of Code Case N-722-1, 3.2.2.8 PWR Owners Group Operating Guidance OG-09-139              - Inspection of Pressurizer Heater Sleeves Based on guidance in PWR Owners Group Operating Guidance OG-09-1 39 and WCAIP-l1691 3-P, visual examinations of the Pressurizer Heater Sleeves for leakage are being performed during each refueling outage in accordance with Reactor Coolant System Pressure Test, STS-PE-040A.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 3.3      ASME Section XI Code Cases Incorporated Into The 1SI Program The use of ASME Section XI Code Cases is in accordance with 10CFR50.55a. ASME Code Cases that have been determined to be suitable for use in 1S1 Program Plans by the NRC are listed in Regulatory Guide 1.147, "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 1SI 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.
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 50.5 5a(z) via acceptance of the associated Request for Alternative.
Note that Code Cases N-729-l, N-722-1 and N-770-1 are not listed in Table 3.3-1, as they are implemented as augmented requirements as described in Section 3.2.
TABLE 3.3-1 CODE CASES INCORPORATED INTO THE ISI PROGRAM Code                       Title                        Regulatory           Extent of Use Case                                                    Guide 1.147 Status/Request for Alternative N-Si13-3     Evaluation Criteria For Temporary             Acceptable   To be used as needed for Acceptance of Flaws in Moderate                            temporary acceptance of Energy Class 2 or 3 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 1 and                      to the re-examination 2 Vessels                                                  requirements of IWB-2420(b) and IWC-2420(b) for vessel volumes containing subsurface flaws N-532-5      Alternative Requirements to Repair            Acceptable   Extent defined within the and Replacement Documentation                              Program Plan Requirements and Inservice Sunmnary Report Preparation and Submission N-586-1      Alternative Additional Examination            Acceptable   To be used as an alternative Requirements for Class 1, 2, and 3                         to the requirements of IWB-Piping, Components, and Supports                           2430(a), IWC-2430(a),
IWD-2430(a), IWF-2430(a)
WCRE-30                                3.0 - 1SIPage Program                                       Revision 0 31 ofDescription 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE 3.3-1 CODE CASES INCORPORATED INTO THE ISI PROGRAM Code                     Title                      Regulatory    1        Extent of Use Case                                               Guide 1.147 Status/Request for Alternative{
N-613-1   Ultrasonic Examination of Full              Acceptable     Extent defined within the Penetration Nozzles in Vessels,                            Program Plan Examination Category B-D, Item No's B3.l0 and B3.90, Reactor Nozzle-to-Vessel Welds, Figures IWB-2500-7(a), (b), and (c)_____________
N-639     Alternative Calibration Block              Conditionally   To be used if needed as an Material                                     Acceptable    alternative to the requirements of Appendix I, Supplement 1 and Section
________V,                                               Article 4 N-648-l  Alternative Requirements for Inner         Conditionally   Extent defined within the Radius Examinations of Class 1               Acceptable    Program Plan Reactor Vessel Nozzles N-705    Evaluation Criteria for Temporary            Acceptable    For use in temporary Acceptance of Degradation in                               evaluation of degradation in Moderate Energy Class 2 or 3                               moderate energy Class 2 or Vessels and Tanks                                          3 vessels and tanks N-706- 1 Alternative Examination                      Acceptable    These alternative Requirements of Table IWB-2500-1                           examination requirements and Table IWC-2500-1 for PWR                               will be applied to the Stainless Steel Residual and                               Residual Heat Removal heat Regenerative Heat Exchangers                               exchangers. The extent is defined in Section 4.1.10.
N-73 1   Alternative Class 1 System Leakage           Acceptable     To be used as an alternative Test Pressure Requirements                                  to the requirements of JWB-5221 (a).
N-735     Successive Inspections of Class 1 and       Acceptable     To be used as an alternative 2 Piping Welds                                              to the requirements of IWB-2420 or JWC-2420.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 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 accordance with I10CFRS0.55a(a)(3) and (g)(5) when specific ASME Section XI 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 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 10OCFR50.55a(z) and (g)(5). The status of each Request For Alternative and Request For Relief (Submitted, Granted, or Denied) is also included in Table 3.4-1.
TABLE 3.4-1 REQUESTS FOR RELIEF AIND REQUESTS FOR ALTERNATIVES FROM ASME SECTION XI REQUIREMENTS Relief Request                              Summary                                      Status 14R-0 1       Request to Continue Implementation of the Risk-                   Pending Informed Inservice Inspection Application on Class 1 and 2 Piping Welds I4R-02        Request to Perform a Limited VT-3 Examination                     Pending of the Reactor Vessel Supports                        ___________
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 4".
3.6       WCGS Nonexempt ASMIE Class Components and Component Supports The WCGS ASME Class 1, 2, and 3 components which are not exempt from the examination per Section XI, 1WB-1220, IWC-1220, and IWD-1220 are listed in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4,WCRE-3 2". This document provides a cross-reference to the applicable ISI Isometric or 1S1 Equipment Drawing.
An index of the WCGS ISI Isometrics and Equipment Drawings is included in Section 3.11. A list of applicable Isometrics and Equipment Drawings is also included in each of the System Program Plans of Section 4.1.
The supports of nonexempt components are subject to examination per Section XI, IWF-1200.
Nonexempt component supports are shown on the ISI Isometrics and ISI Equipment Drawings listed in Section 3.11.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL 1ST PROGRAM PLAN 3.7       ISI Isometrics and Equipment Drawings 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 XI. An index of these isometrics and equipment drawings is included on Inservice Inspection Drawing Cross Reference, ISI-REF, Sheets 1 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 1SI Isometrics and Equipment Drawings is included in the ISI Database. The ISI-REF Sheets, Isometrics and Equipment Drawings are stand alone drawings. They are listed as M-1 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, sub-sub articles IWB-1220, IWC-1220, and IWD-1220.
Component supports which meet the criteria of IWF-l1230 are also exempt from examination.
Exempt components are listed in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4". This document details the specific exemption criteria applicable to each component.
3.9       System Pressure Testing System Pressure 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, IWB-5000, IWC-5000, and IWD-5000, as modified by Code Case N-73 1 (applicable to IWB-5 000 only), and 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.
3.10      Calibration Blocks Table 3.10-1 lists the calibration blocks required for the ultrasonic (UT) examinations scheduled in this program plan. The calibration block design and material selection is in accordance with ASME Section XI.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE 3.10-1 WCGS CALIBRATION BLOCKS
[BLOCK   [DESCRIPTION/TITLE                           DRAWING   [APPLICABLE
[NUMBER                                              jNUMBER     [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-             80C41 92       BB 2-CSCL-1 01 102     WC-03-SG-03 .000-SA533-GR.A-                80C41 93        BB CL-2-CS-102 104     WC-5.0-SG-05 .035-SA21 6-WCCA-              80C41 95       BB CSCL-104 105     WC-29-XXX-02.33-SA351-CF8A-                 80D4896        BB CCSS-105 106     WC-27 1/2-XXX-02.21-SA351-                  80D4895        BB CF8A-CCSS-106 112     WC-03-1 60-00.438-SA3 12-TP304-             80D4894        BG SS-112 114     WC-04-1 60-00.531 -SA3 12-TP304-            80C4891        BB SS-114 117     WC-06-160-00.719-SA312-TP304-               80C4891   EJ, EP, EM, BB SS5-117 122     WC-1 0-140-01 .000-SA358-TP304-             80C4891       EJ, EP CL.1-SS-122 126     WC-12-140-01.125-SA376-TP304-               80D4892         EJ SS-126 127     WC-14-120-01 .094-SA508-CL. 1-CS-           80D4892        AE 127 128     WC-1 2-80S-00.500-SA3 12-TP304-             80C4891         EJ SS-128 130     WC-14-1 60-01 .406-SA376-TP3 16-            80D4892         BB SS-130 131     WC- 16-080-00.844-SA106-GR.B-               80C4891        AE CS-131 132     WC-28-01.500-SA106-GR.C-CS-132              80D4892        AB 140     WC-N-7.0-7.99-SA540-GR.B24-                 80D4903        BB CL.3-CS-140 WCRE-30                       3.0 - ISI Program Description                         Revision 0 Page 35 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE 3.10-1 (Continued)
WCGS CALIBRATION STANDARDS
[BLOCK NUMBER I _
DESCRIPTION/TITLE IDRAWING       1APPLICABLE NUMBER] SYSTEM(S) 144         WC-2.0-HPCI-02.000-SA240-TP304-             80D4915            EM SS-144 156         WC-02-1 60-00.344-SA3 12-TP304-             80D4897            BB SS-156 159         WC-04-080-00.337-SA106-GR.B-                80D4893        AB, AE, FC CS-i159 169         WC-NSE-04-1 60-SA508-CL.2                80E491 8          BB 160-SAl182-F3 16L-BI- 169 170         WC-NSE-06-160-SA508-CL.2                 80E4922           BB 160-SAl182-F3 16L-BI-170 171         WC-NSE-14-1 60-SA508-CL.2                80E4923           BB 160-SA1 82-F3 16L-BI- 171 172         WC-00.875-RHR-00.750-SA240-                  80D491 7           EJ TP304-SS-172 175         WC-1 1-RPV-1 1-SA533-GR.B-CL. 1-             80D8410           BB ASCL-175 176         WC-9-RPV-9-SA533-GR.B-CL. 1-                 80D841 1          BB ASCL-176 177         WC-7-RPV-7-SA533-GR.B-CL. 1-                 80D841 2          BB ASCL-177 178        WC-F-XX-33-SA533-GR.B-CL.1-                  80D8413           BB ASCL-178 179        WC-NSE-XXX-3-SA182-GR316-                    5D64166           BB (Note 1)     CL.XX-XXX-3-SA508-GR.XX-CL2-BI-179 183       WC-12-STD-00.375-SA3 12-TP304-               80C4891            EJ SS-183 192       WC-14-40S-00.438-SA358-TP304-                80C4891         BN, EN CL. 1-192 193       WC-S-2.5- 14-SAl193-GR.B7-CS-1 93             80C84 15           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-SA540-GR.B24-CL.3-               Jiiture use         BB CS-195                                         Note 3 WCRE-30                            3.0 - ISI Program Description                           Revision 0 Page 36 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE 3.10-1 (Continued)
WCGS CALIBRATION STANDARDS
[BLOCK
[NUMBER IJ      _
DESCRIPTION/TITLE TDRAWING IAPPLICABLE NUMBER         JSYSTEM(S) 203             WC-08-40S-00.322-SA3 12-TP304-                       M-1 89-               EJ SS-203                                                10203 204             WC-10O-40S-00.365-SA3 12-TP304-                      M- 189-               EJ SS-204                                                10204 8747             Alternate ASME Calibration Block                     Note 4              Note 5 A5 16-70 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 ASMVE Calibration Block                    Note 4              Note 5 A5 16-70 Steel 8751             Alternate ASME Calibration Type                      Note 4              Note 6 316 Stainless Steel 8752            Alternate ASMIE Calibration Type                     Note 4              Note 7 304 Stainless Steel Ax 6-01            6" Axial Reference Block                           100 155C87          BB, Note 8 Circ 6-01          6" Circumferential Reference Block                 100155C88          BB, Note 8 Ax 8-01           8" Axial Reference Block                           100 155C89         BB, Note 8 Circ 8-01          8" Circumferential Reference Block                 100 155C90          BB, Note 8 Axial/Flat         16" Axial/Flat Reference Block                     1001 55C91          BB, Note 8 16-01 Circ 16-01          16" Circumferential Reference Block                100 155C92          BB, Note 8 NOTES:
Note 1: Block 179 was modified by Westinghouse in 1996. The drawing number referenced is the 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, if the block is modified to comply with Appendix VIII, or an equivalent RCP stud cal block meeting Section XI requirements (such as Callaway Block 93).
Note 3: Previous examinations were conducted utilizing either block 155 or Callaway block 95. The Interval 3 examinations will utilize block 195, if the block is modified to comply with Appendix VIII, or an equivalent RV stud cal block meeting Section XI requirements (such as Callaway Block 95).
WCRE-30                                   3.0 - ISI Program Description                                     Revision 0 Page 37 of4l

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN NOTES (Continued):
Note 4: The Alternate ASME Calibration Block is depicted on Figure 4 of PDI-UT-I and PDI-UT-2.
Note 5: The Alternate Calibration Blocks numbered 8747 and 8750 may be utilized in lieu of carbon steel calibration blocks after approval by WCNOC Level III QC, 1S1 Engineering, and review by the ANII.
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 Ill QC, 1SI Engineering, and review by the ANII.
Note 7: The Alternate Calibration Blocks numbered 8749 and 8752 may be utilized in lieu of Type 304 stainless steel calibration blocks after approval by WCNOC Level III QC, 1S1 Engineering, and review by the ANII.
Note 8: These are reference blocks to be utilized for the examination of the overlays installed on the pressurizer nozzles piping welds. Reference P0 733795 and Receipt Inspection Report 06-052193.
3.11      Inservice Inspection Drawing Index M-189-50 Series List Reference Drawings             M-189-50ISI-REF        SHEET 1 of 4 M-189-50ISI-REF        SHEET 2 of 4 M-189-50ISI-REF        SHEET 3 of 4 M-189-50ISI-REF        SHEET 4 of 4 AB System                      M-189-50AB-01-01         SHEET    1 of 1 M-189-50AB-02-01         SHEET    1 of 1 M-189-50AB-03-01         SHEET    1 of 1 M-189-50AB-04-01         SHEET    1 of 1 AE System                      M-189-50AE-01-04         SHEET    1 of 1 M-189-50AE-02-04         SHEET    1 of 1 M-189-50AE-03-05         SHEET    1 of 1 M-189-50AE-04-05         SHEET    1 of 1 AL System                      M-189-50AL-01-01         SHEET 1 of 2 M-189-50AL-01-01         SHEET 2 of 2 M-189-50AL-01-02         SHEET 1 of 1 M-189-50AL-02-03         SHEET 1 of 1 M-189-50AL-03-04         SHEET 1 of 1 M- 189-50AL-04-02        SHEET 1 of 1 M-189-50AL-05-03         SHEET 1 of 1 M-189-50AL-06-04         SHEET 1 of 1 M-1 89-50AL-07-06 SHEET 1 of 1 WCRE-30                                       3.0 - 1S1 Program Description                                    Revision 0 Page 38 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN BB System    M-189-50BB-00-01      SHEET 1 of 1 M-189-50BB-01-01      SHEET 1 of 1 M-189-50BB-01-02      SHEET 1 of 1 M-189-50BB-01-04      SHEET 1 of 2 M-189-50BB-01-04      SHEET 2 of 2 M-189-50BB-01-08      SHEET 1 of 1 M-189-50BB-02-01      SHEET 1 of 1 M-189-50BB-02-02      SHEET 1 of 1 M-189-50BB-02-11      SHEET 1 of 1 M-189-50BB-03-01      SHEET 1 of 1 M-189-50BB-03-09      SHEET 1 of 1 M-189-50BB-04-01      SHEET 1 of 1 M-189-50BB-04-07      SHEET 1 of 1 M-189-5OBB-05-01      SHEET 1 of 1 M-189-50BB-06-01      SHEET 1 of 1 BG System    M-189-50BG-01-01      SHEET   1 of 1 M-189-50BG-01-21      SHEET   1 of 1 M-1 89-50BG-02-22     SHEET   1 of 2 M-1 89-50BG-02-22     SHEET   2 of 2 M-189-50BG-03-23      SHEET   1 of 1 M-189-50BG-04-09      SHEET   1 of 1 M-189-50BG-05-24      SHEET   1 of 1 M-189-50BG-06-02      SHEET   1 of 2 M-189-50BG-06-02      SHEET   2 of 2 M-189-50BG-06-10      SHEET   1 of 1 BM System    M-189-50BM-01-01 SHEET 1 of 1 M-189-50BM-01-02 SHEET 1 of 1 BN System    M-189-50BN-01-01 SHEET 1 of 3 M-189-50BN-01-01 SHEET 2 of 3 M-189-50BN-01-01 SHEET 3 of 3 EF System    M-189-50EF-01-01      SHEET 1 of 2 M-189-50EF-01-01      SHEET 2 of 2 M-189-50EF-01-02      SHEET 1 of 2 M-189-50EF-01-02      SHEET 2 of 2 M-189-50EF-01-03      SHEET 1 of 2 M-189-50EF-01-03      SHEET 2 of 2 M-189-50EF-01-07      SHEET 1 of 1 M-189-50EF-01-08      SHEET 1 of 1 M-189-50EF-01-09      SHEET 1 of 1 M-189-50EF-01-10      SHEET 1 of 1 M-189-50EF-02-01      SHEET 1 of 3 M-189-50EF-02-01      SHEET 2 of 3 M-189-50EF-02-01      SHEET 3 of 3 M-189-50EF-02-04      SHEET 1 of 1 M-189-50EF-02-05      SHEET 1 of 2 M-189-50EF-02-05      SHEET 2 of 2 M-189-50EF-02-06      SHEET 1 of 1 M-189-50EF-02-08      SHEET 1 of 2 WCRE-30                  3.0 - ISI Program Description  Revision 0 Page 39 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN M-189-50EF-02-08      SHEET 2 of 2 M-189-50EF-02-09      SHEET 1 of 1 M-189-50EF-02-10      SHEET 1 of 1 M-189-50EF-03-01      SHEET 1 of 1 EG System    M-189-50EG-01-01       SHEET 1 of 1 M-189-50EG-01-02       SHEET 1 of 2 M-189-50EG-01-02       SHEET 2 of 2 M-189-50EG-02-03       SHEET 1 of 2 M-189-50EG-02-03       SHEET 2 of 2 M-189-50EG-02-05       SHEET 1 of 2 M- 189-50EG-02-05      SHEET 2 of 2 M-189-50EG-03-06       SHEET 1 of 1 M-189-5OEG-03-07       SHEET 1 of 1 M-1 89-50EG-04-01      SHEET 1 of 2 M-189-50EG-04-01       SHEET 2 of 2 M-189-5OEG-05-06       SHEET 1 of 2 M-189-50EG-05-06       SHEET 2 of 2 EJ System    M-189-50EJ-01-01      SHEET 1 of 5 M-189-50EJ-01-01      SHEET 2 of 5 M-189-50EJ-01-01      SHEET 3 of 5 M-189-50EJ-01-O1      SHEET 4 of 5 M-189-50EJ-01-01      SHEET 5 of 5 M-189-5OEJ-01-04      SHEET 1 of 1 M-189-50EJ-02-02      SHEET 1 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-1 89-50EJ-02-02     SHEET 5 of 5 M-1 89-50EJ-02-04     SHEET 1 of 3 M-1 89-50EJ-02-04     SHEET 2 of 3 M-189-50EJ-02-04      SHEET 3 of 3 EM System    M-189-50EM-01-01        SHEET  1 of 1 M-189-50EM-02-01        SHEET  1 of 1 M-189-50EM-03-05        SHEET  1 of 1 M-1 89-50EM-04-03       SHEET  1 of 1 M-189-50EM-05-01        SHEET  1 of 2 M-189-50EM-05-01        SHEET  2 of 2 M-189-50EM-06-02        SHEET   1 of 2 M-189-50EM-06-02        SHEET  2 of 2 M-189-50EM-06-03        SHEET   1 of 1 WCRE-30                   3.0 - 1ST Program Description   Revision 0 Page 40 of 4l

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN M-189-50EN-01-01      SHEET 1 of 3 EN System M-189-50EN-01-01      SHEET 2 of 3 M-189-50EN-01-01      SHEET 3 of 3 M-189-5OEN-02-02      SHEET 1 of 3 M-189-50EN-02-02      SHEET 2 of 3 M-189-50EN-02-02      SHEET 3 of 3 EP System           M-189-50EP-01-01     SHEET   1 of 1 M-1 89-50EP-02-02    SHEET   1 of 1 M-189-50EP-03-02     SHEET   1 of 1 M-189-50EP-04-01     SHEET   1 of 1 FC System           M-189-50FC-01-01 SHEET 1 of 1 GN System           M-189-50GN-01-01      SHEET   1 of 4 M-189-50GN-01-01      SHEET   2 of 4 M-189-50GN-01-01      SHEET   3 of 4 M-189-50GN-01-01      SHEET   4 of 4 M-189-50GN-02-02      SHEET   1 of 4 M-189-50GN-02-02      SHEET   2 of 4 M- 189-5OGN-02-02     SHEET   3 of 4 M-189-50GN-02-02      SHEET   4 of 4 KJ System           M-189-50KJ-01-01     SHEET 1 of 4 M-189-50KJ-01-01     SHEET 4 of 4 M-189-50KJ-02-04     SHEET 1 of 4 M-189-50KJ-02-04     SHEET 4 of 4 Equipment Drawings  M-189-50ISI-RBB01 SHEET 1 of 3 M-189-50ISI-RBB01 SHEET 2 of 3 M-189-50ISI-RBB01 SHEET 3 of 3 M-189-50ISI-TBB03 SHEET 1 of 2 M-189-50ISI-TBB03 SHEET 2 of 2 M-189-50IS1-EBB01A SHEET 1 of 1 M-189-50ISI-EBB01B SHEET 1 of 1 M-189-50ISI-EBB01C SHEET 1 of 1 M-189-501S1-EBB01D SHEET 1 of 1 M-189-50IS1-EEJ01A SHEET 1 of 1 M-189-501SI-EEJ01B SHEET 1 of 1 M-189-50ISI-PUMPS SHEET 1 of 1 M-189-50ISI-CRDMPL SHEET 1 of 1 WCRE-30                         3.0 - ISI Program Description  Revision 0 Page 41 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.0     WCGS SYSTEM INSERVICE INSPECTION PROGRAM PLANS This Section includes system specific 1S1 Program Plans which detail the examinations and tests scheduled for each WCGS system included in the ISI Program. Section 4.0 has been subdivided into three subsections:
Subsection 4.1 includes systems which are subject to Section XI 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.
Subsection 4.2 includes systems which are subject to ASME Section XI System Pressure Testing only.
These systems or portions of these systems include exempt Class 1, Class 2, and Class 3 components (per IWB-1220, IWC-1220, or IWD-1220) only.
Subsection 4.3 includes Class 2 components which are exempt Section XI NDE and Augmented NDE and are also excluded from periodic system pressure testing per TWA-5 110(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 4", this line cannot be exempted per the criteria of IWC-1 222. 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 4, and the GS System is not included in Section 4.1.
WCRE-30                         4.0 System Inservice Inspection Program Plans                   Revision 0 Page 1 of 1

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1 WCGS SYSTEMS SUBJECT TO SECTION XI NDE OR AUGMENTED NDE 4.1 WCGS Systems Subject To Section XI NDE WCRE-30                          or Augmented NDE                   Revision 0 Page 1 of 1

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.1 Main Steam System (AB)
A. Applicable System Piping and Instrument Drawings
: 1. M-12AB01-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 4".
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 4".
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 1  Main Steam Loop 1
: 2.        M-189-50AB-02-01             Sheet 1  Main Steam Loop 2
: 3.        M-189-50AB-03-01             Sheet 1  Main Steam Loop 3
: 4.        M-189-50AB-04-01             Sheet 1  Main Steam Loop 4 4.1.1 Main Steam System (AB)                                           Revision 0 WCRE-30                                        Page 1 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.1 Main Steam System (AR)
E.      Summary of 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 ASMvIE Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the 1SI 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         P1. P__2      P_.3        INTERVAL PIPING WELDED                  C-C            C3.20               --                         2           0       1        0                 1 ATTACHMENTS PRESSURE RETAINING                 C-D            C4.40--                                        4                            0110 BOLTING                                                                                                                               Note 2 PIPING COMPONENT                  F-A            F1.20               --                         28          2       2        26 SUPPORTS PIPING WELDS NOT                  R-A           R1.20.6               --                       155          5       6        516 SUBJECT TO A DAMAGE               Note I           Note 1 MECHANISM PIPING WELDS                     --                            USAR           3.6.2         203          2       1        14 SUBJECT TO HELB REQUIREMENTS Note 1: See Section H for an explanation of Category R-A and Item R1.XX nomenclature.
Note 2: Examination of Pressure Retaining Bolting is performed in accordance with Category C-D. See Note 2 in Paragraph I for selection and scheduling criteria.
WCRE-30                                                           4.1.1 Main Steam System (AB)                                                          Revision 0 Page 2 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI 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 Pipine 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-33 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-1, 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-1 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 through 4-4 of TR-1 12657 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 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 1 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-578-1.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table AB-1 (Period 1 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 and RI-ISI Programs. The requirements for examn~ation of these welds are discussed in Paragraphs F and H above, respectively.
: 2. Examination of Pressure Retaining Bolting is performed in accordance with Category C-D.
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 Category C-D, Notes 1 and 2.
: 3. The valves with this bolting were replaced in Interval 3. The preservice exam was performed with the surface exam method. The configuration of the bolting in the new valves will require a new calibration stud and demonstration of a specific procedure. Alternatively, the studs may be removed and a surface examination meeting the acceptance standards of IWB-35 15 may be substituted for the volumetric examination per Note 5 of Category C-D.
WCRE-30                         4.1.1 Main Steam System (AB)                                           Revision 0 Page 3 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN
: 4. These welds have been selected per the RI-ISI Program only. The requirements for examination of these welds are discussed in Paragraph H above.
WCRE-30                4.1.1 Main Steam System (AB)                                         Revision 0 Page 4 of7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AB-1 IIPeriod1Examinations I
[System: ABJ Relief Request or Size Thickness NDE Method           Item    Cal Block          Notes Component Name  Drawing Number Component Description                                                            Category AB-0 I-HV- 14-b AB-01-01       VALVE HV- 14 BONNET BOLTING                            2.5        NA      UT     C-D      C4.40                         2,3 AB-01-C002      AB-01-01       PIPING SUPPORT                                        28                 VT-3    F-A      F1.20 AB-01-H010      AB-02-01       PIPING SUPPORT                                        28                 VT-3    F-A      F1.20 AB-01-F007      AB-01-0I       28' MAIN STEAM HEADER TO FLUED HEAD (P-2)             28        1.5       UT     R-A      Ri1.20.6     132              1 AB-0 I-FO07     AB-01-01                                                             28        1.5       UT     USAR     3.6.2        132 28" MAIN STEAM HEADER TO FLUED HEAD (P-2)
AB-0i-F074      AB-04-01       28" MAIN STEAM HEADER TO FLUED HEAD (P-i)             28        1.5       UT     R-A      Ri1.20.6     1321 AB-01 -F074     AB-04-01                                                             28        1.5       UT     USAR     3.6.2        132 28' MAIN STEAM HEADER TO FLUED HEAD (P-i)
AB-01-S008-B    AB-01-01       10" PIPE TO 10" ELBOW                                  10       .594      UIT    R-A      Ri1.20.6     123              4 AB-0 1-F052-A   AB-03-01       28" PIPE TO TORSIONAL RESTRAINT                       28        1.5       UT     R-A      RI .20.6     168              4 AB-01-S032-W    AB-03-01       12" PIPE TO 12" PIPE CAP                               12       .688      UT     R-A      RI .20.6     129              4 WCRE-30                                                 4.1.1 Main Steam System (AR)                                                              Revision 0 Page 5 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AB-2
[Period 2 Examinations
[System:   AB Relief Request Component Name Drawing Number Component Description                                    Size Thickness NDE Method Category Item     Cal Block      or Notes AB-01l-R0Oi0   AB-02-0I       PIPING INTEGRAL ATTACHMENTS                             28                  MT     C-C      C3.20 AB-0Ol-R001    AB-04-0 l      PIPING SUPPORT                                          28                 VT-3    F-A      F1.20 AB-0I-R003     AB-03-0i       PIPING SUPPORT                                          28                 VT-3    F-A      FI.20 AB-01-F026     AB-02-01       28" MAIN STEAM HEADER TO FLUED HEAD (IP-3)              28         1.5      UT     R-A      Ri1.20.6     132 28" MAIN STEAM HEADER TO FLUED HEAD (P-3)                                                                132 AB-01-F026     AB-02-01                                                               28         1.5      UT     USAR     3.6.2 AB-01-F02 8-A  AB-02-01       28" PIPE TO TORSIONAL RESTRAINT                         28          1.5     U      R-A      Ri1.20.6     168 AB-01-S020-B   AB-02-01       10' PIPE TO 10" ELBOW                                    10        .594     UIT    R-A      R1 .20.6    123              4 AB-01-S018-L   AB-02-01       6" OUTLET ON MAIN STEAM HEADER TO 6" FLANGE             6          .432     UT     R-A      RI1.20.6     180             4 AB-01-S049-D   AB-04-01       10" ELBOW TO 10" X 8" REDUCER10                          10       .594      UT     R-A      Ri1.20.6     165             4 AB-01-S046-L   AB-04-01       6' OUTLET ON MAIN STEAM HEADER TO 6" FLANGE             6          .432     UT     R-A      R1 .20.6     180             4 WCRE-3 0                                              4.1.1 Main Steam System (AB)                                                               Revision 0 Page 6 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AB-3 SPeriod 3 Examinations1 lsystem: AB Relief Request or Size Thickness  NDE Method           Item     Cal Block    Notes Component Name Drawing Number  Component Description                                                             Category AB-0 1-CO011   AB-03-01        PIPING SUPPORT                                        10                 VT-3     F-A      F1.20 AB-01-H-005    AB-03-01        PIPING SUPPORT                                        28                 VT-3     F-A      F1.20 AB-0I-F050     AB-03-0OI       28" MAIN STEAM HEADER TO FLUED HEAD (P-4)             28         1.5      UT     R-A       RI .20.6     132 AB-01-F050                     28" MAIN STEAM HEADER TO FLUED HEAD (P-4)                                        USAR      3.6.2        132 AB-03-01                                                              28         1.5      UT AB-01-F006     AB-01-01        28' PIPE TO 28" ELBOW                                 28       .934       UT     R-A       R1 .20.6     135            4 AB-01-F097     AB-01-O1       FLUED HEAD (P-2) TO 28" PIPE                           28         .934     UT     R-A       Ri1.20.6     135            4 AB-01-S034-D   AB-03-01       10" ELBOW TO 10" PIPE                                  10        .594      UT     R-A       R1 .20.6     123            4 AB-01 -F076-A  AB-04-01       28" PIPE TO TORSIONAL RESTRAINT                        28         1.5      UT     R-A       Ri1.20.6     168            4 WCRE-30                                                   4.1.1Main tRevision                                                                   Revision 0AB 0
Page 7 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.2 Feedwater System (AE)
A. Applicable System Piping and Instrument Drawings
: 1. M- 12AE02-Feedwater System B. Classification of Components Details of the classification of the Feedwater System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Feedwater System. These drawings are included in the M-189-50 series.
: 1.       M-189-50AE-01-04            Sheet  1         Main Feedwater Loop   1
: 2.       M-189-50AE-02-04            Sheet  1         Main Feedwater Loop   2
: 3.       M-189-50AE-03-05            Sheet  1         Main Feedwater Loop   3
: 4.       M-189-50AE-04-05            Sheet  1        Main  Feedwater Loop   4 4.1.2 Feedwater System (AE)                                             Revision 0 WCRE-30                                       Page 1 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.2 Feedwater System (AE)
E.       Summary of 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 1SI 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     P1_     P_.2  P_.3       INTERVAL PIPING INTEGRAL                C-C              C3.20                --                           12       1      1     0                 2 ATTACHMENTS PIPING WELDS SUBJECT               R-A              R1.11                --                           33      5       3     4                12 TO THERMAL FATIGUE                Note I            Note 1 PIPING WELDS NOT                R-A              R1.20                                            108      6       5     2                13 SUBJECT TO A DAMAGE               Note 1            Note 1 MECHANISM PIPING COMPONENT                F-A              F1.20                --                          44       3       3     3 *9 SUPPORTS PIPING WELDS SUBJECT                                                 USAR              3.6.2          17      3       3     2                  8 TO HELB REQUIREMENTS WITH THERMAL FATIGUE             __  _   _  _    __   _    _   _   __    _    _  _  _   _   _  _ _   _   _ _ _ _   __                  _  _    _    _  _  _   _
PIPING WELDS                                     -USAR                          3.6.2           62      3       0     0                 3 SUBJECT TO HELB REQUIREMENTS NOT                                                                                                                        Note 2 SUBJECT TO A DAMAGE MECHANISM Note 1: See Section H for an explanation of Category R-A and Item R1 .XX nomenclature.
Note 2: Two of these welds were optionally selected for examination.
WCRE-30                                                            4.1.2 Feedwater System (AE)                                                   Revision 0 Page 2 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.2 Feedwater System (AE)
F. Augmented ISI Requirements The following Augmented 1SI requirements apply to the Feedwater 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-33 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 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 1 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-1 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 through 4-4 of TR-1 12657 Rev. B-A.
Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table AE-1 (Period 1 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.
: 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-30                       4.1.2 Feedwater System (AE)                                    Revision 0 Page 3 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AE-1 IPeriod 1 Examinations tSystem: AE Relief Request or Size                                       Cal Block          Notes Component Name Drawing Number  Component Description                                        Thickness NDE Method Category  Item 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       F 1.20 AE-05-R011I    AE-03-05       PIPING SUPPORT                                           14                VT-3    F-A       F1.20 AE-04-F015     AE-01-04        16" PIPE TO S.G.A. INLET NOZZLE                         16      0.844      UT     R-A       RI.11      131          1,3 AE-04-S010-C   AE-01-04       16"X14" REDUCER TO 16" PIPE                              16      0.844      UT     R-A       RI~ll      131          1,3 AE-04-S025-A   AE-01-04       4" PIPE TO 4" ELBOW                                     4        0.337      UIT    R-A       RI 1l      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       RI 11      159          1,2,3 AE-04-S025-B   AE-01-04       4" ELBOW TO 4" PIPE                                     4        0.337      UIT    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       RI ll      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 AE-04-FW3 14   AE-02-04       14" PIPE TO 14" PIPE                                     14      0.750      UT     R-A       RI.20      173          1,2 AE-04-FW3 14   AE-02-04       14" P/PE TO 14" PIPE                                     14      0.750      UT     USAR      3.6.2      173 AE-04-FW3 15   AE-02-04       14" PIPE TO FLUED HEAD (P-7)                             14      0.750      UT     R-A      R1.20       173          1,2 AE-04-FW3 15   AE-02-04       14" PIPE TO FLUED HEAD (P-7)                             14      0.750      UT     USAR     3.6.2       173 WCRE-30                                                       4.1.2 Feedwater System (A.E)                                                      Revision 0 Page 4 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL IS1 PROGRAM PLAN TABLE AE-1 IPeriod 1 Examinations
[System: AE Relief Request or Size Thickness NDE Method          Item   Cal Block          Notes Component Name Drawing Number Component Description                                                         Category AE-05-F006     AE-04-05       14" PIPE TO 14" PIPE                                 14     0.750      UT     R-A      Ri1.20     124           1 AE-05-EW3 19   AE-04-05       14" PIPE TO 14" PIPE                                 14     0.750      UT     R-A      Rl.20      124           1 AE-05-F008     AE-04-05       14" PIPE TO 14" PIPE                                 14     0.750      UT     R-A      RI.20      173           1 WCRE-30                                                    4.1.2 Feedwater System (AE)                                                    Revision 0 Page 5 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AE-2
[Period 2 Examinations
[System: AE Relief Request or Cal Block          Notes Component Name Drawing Number Component Description                                   Size Thickness NDE Method Category  Item AE-05-R028     AE-04-05       PIPING INTEGRAL ATTACHMENTS                             14                 MT     C-C      C3.20 AE-05-C001     AE-03-05       PIPING SUPPORT                                          14                VT-3    F-A      FI.20 AE-05-R028     AE-04-05       PIPING SUPPORT                                          14                VT-3    F-A      F1.20 AE-04-C002     AE-01-04       PIPING SUPPORT                                          14                VT-3    F-A      F1.20 AE-04-S026-A   AE-02-04       4" PIPE TO 4" ELBOW                                     4       0.337      UT     R-A      RI ll     159          1,2,3 AE-04-S026-A   AE-02-04                                                               4                         USAR     3.6.2     159          1,2,3 4" PIPE TO 4" ELBOW                                            0.337       UT AE-04-F040     AE-02-04       4" WELDOLET TO 4" PIPE                                  4      0.337       UIT    R-A      RI ll     159          1,2,3 AE-04-F040     AE-02-04                                                               4                         USAR     3.6.2     159          1,2,3 4" WELDOLET TO 4" PIPE                                         0.337       UT AE-02-04                                                               4                         R-A      RI.I1     159          1,2,3 AE-04-S026-B                  4" ELBOW TO 4" PIPE                                             0.337      UT AE-04-S026-B   AE-02-04                                                               4                         USAR     3.6.2     159          1,2,3 4" ELBOW TO 4" PIPE                                             0.337      UT AE-04-F002     AE-01-04       14" TORSIONAL RESTRAINT TO FE-5 10                      14      1.094      UT     R-A      R1.20     127 AE-04-F006     AE-01-04       14" PIPE TO 14" PIPE                                    14      1.094      UT     R-A      R1.20     124 AE-05-F021     AE-03-05       14" PIPE TO 14" PIPE                                    14      1.094      UIT    R-A      RI.20     124 AE-05-MW7147   AE-03-05       14" PIPE TO 14" PIPE                                    14      1.094      UT     R-A      R1.20     124 AE-04-S0 19-B  AE-01-04       14" PIPE TO 14" PIPE                                    14      0.750      UIT    R-A      R1.20     116 WCRE-30                                                      4.1.2 Feedwater System (AE)                                                     Revision 0 Page 6 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AE-3 ISystem: AE Relief Request or Size                               Item     Cal Block          Notes Component Name Drawing Number  Component Description                                     Thickness NDE Method Category AE-04-R016     AE-02-04       PIPING SUPPORT                                        14                VT-3    F-A      FI.20 AE-04-H001     AE-02-04       PIPING SUPPORT                                        14                VT-3    F-A      F1.20 AE-05-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      RI ll 159           1,2,3 AE-05-F033     AE-03-05       4' PIPE TO VALVE V127                                 4                                  3.6.2        159           1,2,3 0.337      UT     USAR 4" ELBOW TO 4" PIPE                                   4       0.337      UT     R-A      RI~ll        159           1,2,3 AE-05-FW900    AE-03-05 AE-05-FW900    AE-03-05       4" ELBOW TO 4" PIPE                                   4                                  3.6.2        159           1,2, 3 0.337      UT     USAR AE-04-S02 1-C  AE-02-04       16'"X 14' REDUCER TO 16" PIPE                          16     0.844      UT     R-A      Rl.ll.5      131           1,3 AE-04-F035A    AE-02-04       16" PIPE TO S.G.B. INLET NOZZLE                        16     0.844      UT1    R-A      R.1.11.5     131           1,3 AE-04-F071     AE-01-04       14" PIPE TO 14" ELBOW                                  14     0.750      UT     R-A      R1.20        116 AE-04-S008-A   AE-01-04       14" ELBOW TO 14" PIPE                                  14     0.750      UT     R-A      RI.20        116 WCRE-30                                                      4.1.2 Feedwater System (AE)                                                      Revision 0 Page 7 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.3 Auxiliary Feedwater System (AL)
A. Applicable System Piping and Instrument Drawings
: 1. M-12AL01-Auxiliary Feedwater System B. Classification of Components Details of the classification of the Auxiliary Feedwater System Components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics detail the nonexempt 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-01-01           Sheet 1     Auxiliary Feedwater Turbine Driven Pump Suction Piping
: 2.       M-189-50AL-01-01           Sheet 2     Auxiliary Feedwater Pump Motor Driven Pump Suction Piping
: 3.       M- 189-50AL-01-02          Sheet 1     Motor Driven Auxiliary Feedwater Pump "A" Discharge Piping
: 4.       M-1 89-50AL-02-03          Sheet 1     Motor Driven Auxiliary Feedwater Pump "B" Discharge Piping Feedwater
: 5.       M- 1 89-50AL-03-04         Sheet 1     Turbine Driven Auxiliary Feedwater Pump Suction Piping
: 6.       M-189-50AL-04-02           Sheet 1     Motor Driven Auxiliary Feedwater Pump "A" Discharge Piping
: 7.       M-1 89-50AL-05-03          Sheet 1     Motor Driven Auxiliary Feedwater Pump "B" Discharge Piping
: 8.       M-1 89-50AL-06-04          Sheet 1     Turbine Driven Auxiliary Feedwater Pump Discharge Piping
: 9.       M-1 89-50AL-07-06          Sheet 1     Turbine Driven Aux. Feedwater Standby Tanks & Piping WCRE-30                                4.1.3 Auxiliary Feedwater (AL)                          Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.3 Auxiliary Feedwater (AL)
E.        Summary of Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table 1 is a sunmmary 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      P1_l  P..2    P_3        INTERVAL PIPING WELDED                   C-C             C3.20              --                           9          1       0    01 ATTACHMENTS Pressure Vessel Welded            D-A             D 1.10             --                           3          0       0    1                  1 Attachments PIPING WELDED                   D-A             D 1.20--7                                                 0        0    11 ATTACHMENTS PIPING COMPONENT                  F-A             F1.20              --                           32        2        1    2                 5 SUPPORTS PIPING COMPONENT                  F-A             F1.30              --                          45          3       2    3                 8 SUPPORTS EQUIPMENT SUPPORTS                 F-A             F1.40               --                          11         0       4    15 (Other Than Piping)
PIPING WELDS NOT                  R-A             R1.20                                          126         0       0    00 SUBJECT TO A DAMAGE                Note 1           Note 1 MECHANISM Note 1: See Section H for an explanation of Category R-A and Item R1.XX nomenclature.
WCRE-30                                                          4.1.3 Auxiliary Feedwater (AL)                                                  Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.3 Auxiliary Feedwater (AL)
F. Augmented 1S1 Requirements No Augmented ISI requirements apply to the Auxiliary Feedwater System.
G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining components within the Auxiliary Feedwater System will receive a system leakage test per IWC-5220 each inspection period.
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 IWD-5220 every period.
Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed 1SI Progrnm A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class 1 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, guidance was taken from Code Case N-578-1 for the assignment of these designators. No welds in the Auxiliary Feedwater System were selected for examination in the RI-ISI program.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table AL-i (Period 1 Examinations), Table AL-2 (Period 2 Examinations),
and Table AL-3 (Period 3 Examinations).
WCRE-30                        4.1.3 Auxiliary Feedwater (AL)                               Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE AL-I IPeriod 1 Examinations
[System:  AL Component Name Drawing Number  Component                                            Size Thickness NDE Method Category Item   Relief Request    Notes AL-04-C013     AL-06-04        PIPING INTEGRAL ATTACHMENT                                              PT     C-C      C3.20 4
AL-03-R0L11    AL-05-03        PIPING SUPPORT                                                         VT-3    F-A      F 1.20 4
AL-04-C013     AL-06-04        PIPING SUPPORT                                                         VT-3    F-A      F 1.20 4
AL-03-R010     AL-02-03        PIPING SUPPORT                                                         VT-3    F-A      F1.30 6
AL-06-R001     AL-07-06        PIPING SUPPORT                                                         VT-3    F-A      F1.30 AL-01-H008     AL-01-01 SHT. 2 PIPING SUPPORT                                       8                 VT-3    F-A      FI.30 WCRE-30                                               4.1.3 Auxiliary Feedwater (AL)                                                        Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AL-2 I eid2Examinations LSystem: AL 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      F 1.30 AL-04-C002     AL-03-04        PIPING SUPPORT                                                    VT-3    F-A      F 1.30 PAL02-SUP- 1   AL-01-01 SHT. I 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 PAL0 1A-SUP-2  AL-01-01 SHT. 2 PUMP SUPPORT                                   8                  VT-3    F-A      F1.40 WCRE-30                                          4.1.3 Auxiliary Feedwater (AL)                                                        Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AL-3 SSystem:  AL Component Name Drawing Number Component                                          Size Thickness NDE Method Category Item   Relief Request    Notes AL-03-A001     AL-02-03       PIPING INTEGRAL ATTACHMENTS                                          VT-i    D-A      D1.20 AL-04-R014     AL-06-04       PIPING SUPPORT                                                       VT-3    F-A      F 1.20 4
AL-02-R011I    AL-04-02       PIPING SUPPORT                                                       VT-3    F-A      F1.20 AL-02-C003     AL-0 1-02      PIPING SUPPORT                                                       VT-3    F-A      F 1.30 6
AL-03-A001     AL-02-03       PIPING SUPPORT                                                       VT-3    F-A      F1.30 6
AL-06-C001     AL-07-06       PIPING SUPPORT                                                       VT-3    F-A      F 1.30 TAL01A-SUP-1   AL-07-06       TANK SUPPORT                                                         VT-3    F-A      F1.40 TAL0 IA-SUP-I  AL-07-06       TANK INTEGRAL AYIACHMENT                                             VT-I    D-A      DI.10 WCRE-30                                             4.1.3 Auxiliary Feedwater (AL)                                                       Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.4 Reactor Coolant System (BB)
A. Applicable System Piping and Instrument Drawings
: 1. M-12BB0 1-Reactor Coolant System
: 2. M-12BB02-Reactor Coolant System*
: 3. M-12BB03-Reactor Coolant System
* Except for ASME Class 2 components listed in Section 4.3 B. Classification of Components Details of the classification of the Reactor Coolant System components for I SI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
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-189-50 series.
: 1.        M-189-50BB-00-01           Sheet 1   Reactor Coolant System Primary Loop General Layout
: 2.        M-189-50BB-01-01           Sheet 1   Reactor Coolant Loop 1
: 3.        M-189-50BB-01-02           Sheet 1   Reactor Coolant Pressurizer Relief Header
: 4.        M- 189-50B B-01-04         Sheet 1   Reactor Coolant Pressurizer Spray Line
: 5.        M- 189-5OBB-01-04          Sheet 2   Reactor Coolant Pressurizer Spray Line
: 6.        M-189-5OBB-01-08           Sheet 1   Reactor Coolant Pump "A" Seal Water Injection Line
: 7.        M-189-50BB-02-01           Sheet 1   Reactor Coolant Loop 2
: 8.        M-1 89-50BB-02-02          Sheet 1   Reactor Coolant Pressurizer Safety Valve Lines
: 9.        M-189-50BB-02-1 1          Sheet 1   Reactor Coolant Pump "B" Seal Water Injection Line
: 10.      M-1 89-5OBB-03-0 1        Sheet  1   Reactor Coolant Loop 3
: 11.      M-189-50BB-03-09          Sheet  1   Reactor Coolant Pump "C" Seal Water Injection Line
: 12.      M-189-50BB-04-01          Sheet  1   Reactor Coolant Loop 4
: 13.      M-1 89-50BB-04-07         Sheet  1   Reactor Coolant Pump "D" Seal Water Injection Line
: 14.      M-189-50BB-05-01          Sheet  1   Reactor Coolant Pressurizer Surge Line
: 15.      M-189-5OBB-06-0l           Sheet 1   Reactor Coolant Loop Drain To Reactor Coolant Drain Tank
: 16.      M- 189-50ISI-RBB0 1        Sheet 1   Reactor Vessel
: 17.      M- 189-501SI-RBB0 1        Sheet 2   Reactor Vessel
: 18.      M- 189-50ISI-RBB01         Sheet 3   Reactor Vessel
: 19.      M- 189-50ISI-TBB01         Sheet 1   Pressurizer Vessel
: 20.       M-1 89-50ISI-TBB0 1        Sheet 2   Pressurizer Vessel
: 21.       M-1 89-50ISI-EBB01lA       Sheet 1   Steam Generator EBB01lA
: 22.       M-1 89-50ISI-EBB01 B       Sheet 1   Steam Generator EBB01B
: 23.       M-1 89-50ISI-EBB01lC       Sheet 1   Steam Generator EBB01iC
: 24.       M-1 89-50ISI-EBB01iD       Sheet 1   Steam Generator EBB0 1D
: 25.       M-1 89-50ISI-PUMPS         Sheet 1   IS1 Pumps
: 26.       M-189-50ISI-CRDMPL         Sheet 1   CRDM Platform WCRE-30                                4.1.4 Reactor Coolant System (BB)                                      Revision 0 Page 1 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.4 Reactor Coolant (BR)
E.       Summary of 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 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        P1_. P.22     P.33       INTERVAL Circumferential Shell         B-A             Bi 1.11                                          2           0      0      22 Welds, Reactor Vessel Longitudinal Shell Welds,        B-A             B 1.12-                                          90                 0      99 Reactor Vessel Circumferential Head           B-A             B 1.21--30                                                          0      33 Welds, Reactor Vessel Meridional Head Welds,          B-A             B 1.22--81                                                          2      58 Reactor Vessel Shell-to-Flange Weld,          B-A             B 1.30                                                                                         1 Reactor Vessel                                                                                                                        Note 4 Head-to-Flange Weld,           B-A             B 1.40               --                          10                 0      11 Reactor Vessel                                                                                                                        Note 4 Circumferential Shell-To-        B-B             B2. 11--21                                                          1      02 Head Welds, Pressurizer Longitudinal Shell-To-         B-B             B2.12--20                                                           1      12 Head Welds, Pressurizer Tube Sheet-To-Head            B-B             B2.40--4                                                     0      0      1 Weld, Steam Generator Nozzle-to-Vessel Welds,         B-D             B3.90--80                                                           0      88 Reactor Vessel Nozzle Inside Radius          B-D             B3.100--80                                                          0      88 Section, Reactor Vessel WCRE-30                                                      4.1.4 Reactor Coolant System (BB)                                                  Revision 0 Page 2 of 46

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

==SUMMARY==
AND SCHEDULE Nozzle-to-Vessel Welds,   B-D        B3.ll160           --                            2  26 Pressurizer Nozzle Inside Radius    B-D        B3.120             --                       62   2  2     6 Section, Pressurizer                                                                      Note 1 Nozzle Inside Radius    B-D        B3.140             --                       83   3  2     8 Section, Steam Generator                                                                    Note 1 Reactor Vessel Closure  B-G-1        B6.10                                     54  0 0 54     5 Head Nuts                                                                           Note 2 Reactor Vessel Closure  B-G-1        B6.20             --                      54  0 0 54     5 Studs                                                                             Note 2 Threads in Reactor Vessel B-G-1        B6.40             --                      54  0 0 54    5 Flange                                                                            Note 2 Reactor Vessel Closure  B-G-1        B6.50             --                      54  0 0 54    5 Washers                                                                            Note 2 Bolts &Studs in Pumps    B-G-1       B6.180            --                        4  0 0  1     1 Note 2 Flange Surface, When    B-G-1       B6.190            --                        4  0 0  11 Connection Disassembled,                                                                     Note 2 in Pumps Nuts, Bushings, &     B-G-1       B6.200            --                        40   0  11 Washers in Pumps                                                                         Note 2 Bolts, Studs, & Nuts in B-G-2        B7.20            --                        1*   *
* Note 2 Pressurizer Bolts, Studs & Nuts in  B-G-2        B7.30            --                        8*   *
* Note 2 Steam Generator Bolts, Studs & Nuts in  B-G-2        B7.50            --                        7*   *
* Note 2 Piping WCRE-30                                         4.1.4 Reactor Coolant System (BB)                Revision 0 Page 3 of 46

PLMAANDSHUL CSOMPROGRAM FOURTHN IUMNTERDA SECTI TABLE 1 SECTION XI AND AUGMENTED COMPONENT 

==SUMMARY==
AND SCHEDULE Bolts, Studs & Nuts in   B-G-2          B7.60           --                          4    *     *
* Note 2 Pumps Bolts, Studs & Nuts in   B-G-2          B7.70            --                         3    *     *
* Note 2 Valves Welded Attachments For      B-K          Bl10.10           --                         21         0    01 Vessels, Piping, Pumps and ValvesSee                                                                    Paragraph I, Note 11 Pump Casings        B-L-2         B 12.20           --                         4*         *
* 0
                                                                                                           **See Paragraph I, Note 7 Valve Bodies       B-M-2         B12.50            --                         3*         *
* 1 Exceeding NPS 4                                                                                     *See Paragraph I, Note 8 Vessel Interior     B-N-i         B13.10            --                         1    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           --                         10         0    1 Reactor Vessel Welds in Peripheral     B-O          B 14.20           --                        26    0     0    3                3 CRD Housings                                                                                                 Note 5 Welds in Peripheral ICI    B-O          B14.21            --                         50         0    11 Housings                                                                                                  Note 5 Steam Generator Tubing      B-Q          B 16.20          ----                                 -       - See Paragraph I, Note 10 Piping Component       F-A           FI. 10           --                        77    5   10     7               22 Supports Equipment Supports       F-A           F1.40            --                        79    8   12  11                 31 (Other Than Piping)
WCRE-30                                            4.1.4 Reactor Coolant System (BB)                                     Revision 0 Page 4 of 46

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

==SUMMARY==
AND SCHEDULE Piping Welds Subject to    R-A           R1.1 1              --                      36  3  5  3                11 Thermal Fatigue       Note 6         Note 6 Piping Welds Not Subject    R-A            R1,20               --                      287 8 10 10               28 to a Damage Mechanism      Note 6         Note 6 Piping Welds Subject       --                            USAR               3.6.2   89  0  0  00                            /
To HELB Requirements Reactor Coolant Pump       --             -AUG.l1                        AUG.FW      9*
* 44 Flywheel
* See Paragraph. I, Note 9 Shell Circumferential   C-A           Ci1.10                                       122    1 03 Welds Head Circumferential    C-A           C1 .20--40                                          1 01 Welds Tubesheet-to-Shell Weld   C-A           CI1.30               --                      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-C22 Section in Vessels Without  C-C22                                                -41          0 0 Reinforcing Plate, Greater than 1/2" Nominal Thickness RC Hot Leg SE         R-A           R1.20               --                      41    0   01 UT Exam Note 3 RC Cold Leg SE         R-A           R1.20               --                      42    0   03 UT Exam Note 3 WCRE-30                                               4.1.4 Reactor Coolant System (BB)                            Revision 0 Page 5 of 46

X              COMPROGENSUMARPLANDSHUL FO URTHENTERVA SECIO 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  P_1  P__2  P__3        INTERVAL Pressurizer Nozzle Piping         --                        Code Case       F (DM-R)          3     0     0    1                     1 Overlaid DM Welds Repaired                                     N-770-1                                                            Notes 7, 8 Pressurizer Nozzle Piping         -I3R-05                                     (SS-R)          4     0     1    0                     1 Overlaid SS Welds RepairedNoe7, Pressurizer Nozzle Piping         --                        Code Case        C (DM-P)         3     0     1    0                     1 Overlaid DM WeldsN-71 Preemptive                                             -701Notes                                                               7, 8 Pressurizer Nozzle Piping         -I3R-05                                      (SS-P)         2     0     0    1                     1 Overlaid SS Welds Preemptive                                                                                                              Notes 7, 8 Reactor Vessel Upper Head                        -Code             Case         B4.10         79     0    79   79                   158 Nozzles and Partial                                      N-291 Penetration Welds, Visual                                      Note                                                                  9 Exam_____________
Reactor Vessel Upper Head                       -Code              Case         B4.20         79     0    79    0                    79 Nozzles and Partial                                      N-729-1Noe1 Penetration Welds,                                                                                                           Nt Volumetric/Surface Exam                                                                                            ____________
Reactor Vessel, Alloy                                     Cd ae             B58              85          8  5                      7 600/82/182 bottom-mounted                                      N-od7as2B2-15                         5     5     8                     7 instrument penetrations,                                                                                                        Note 11 Visual Exam Reactor Vessel, Alloy                        -Code              Case        B 15.90         48          8   12                    12 600/82/182 Hot leg nozzle-to-                                  N-722-1Noe1 pipe connections, VisualNoe1 Exam                                           ______                                                    ____________
Reactor Vessel, Alloy            --                       Code Case         B 15.95         40          2    2                     4 600/82/182 Cold leg nozzle-                                   N-722-1                                                              oe1 to-pipe connections, VisualNoe1 Exam Piping, Alloy 600/82/1 82          --                       Code Case         B 15.200        12    24   24   36                    72 Hot leg instrument                                       N-722-1Noe1 connectionsNoe1 WCRE-30                                                   4.1.4 Reactor Coolant System (BB)                                            Revision 0 Page 6 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN COMPONENT OR ITEM                 CODE           CODE                AUG.                   AUG                TOTAL IN    EXAMS BY PERIOD & INTERVAL DESCRIPTION           CATEGORY          ITEM NO.        CATEGORY                ITEM NO.                 SYSTEM P1   P_22 P..3      INTERVAL Piping, Alloy 600/82/1 82                           -Code                Case             B 15.205                   4  0    2    2                4 Cold leg instrument                                             N-722-1Noe1 connectionsNoe1 Locations in Normally                                           MVRP-146                 UH/H                      12      2    3                 6 Stagnant Non-Isolable RCS Branch Lines Subject toNoe1 Thermal Fatigue_______
Locations in Normally                             -MRP-146                                 DH                      33      3    6                9 Stagnant Non-Isolable RCS Branch Lines Subject toNoe1 ThermalFatigue______________
Locations in Normally                                           MRP-146                    UH                      1 Stagnant Non-Isolable RCS Branch Lines Subject toNoe1 Thermal Fatigue______________                                                   ________                  ______
Unmitigated Butt Weld at Hot                                         Code Case                  A-2                     44      4    4                12 Leg Operating Temperature <                                           N-770-1 625&deg;F________
Unmitigated Butt Weld at                                         Code Case                    B44                            4    4                12 Cold Leg Operating                                              N-770-I Temperature > 525&deg;F and <
580&deg;F                                                _______________________________________________
Note 1: This Code Item Number is not included in Section XI12007 Edition with the 2008 Addenda, examination is required per 10CFR50.55a(b)(2)(xxi).
Note 2: Examination of Pressure Retaining Bolting is performed in accordance with Categories B-G-1 and B-G-2. See Notes 1-6 and 30 in Paragraph I for selection and scheduling criteria.
Note 3: Three dissimilar metal welds were selected under RI-ISI requirements. All of the welds subject to PWSCC have additional augmented examinations performed per Code Case N-770-1. The RI-ISI exam may be conducted at the same time as the N-770-1 exam.
Note 4: Examination of Reactor Vessel Shell-to-Flange and Head-to Flange welds are performed in accordance with Category B-A, Note 5.
Note 5: Welds in Peripheral CRD Housings (Category B-O, Item No. B14.20) are shown on drawing M-189-501SI-RBB01 in Section A-A and include 26 locations as discussed in Note 6 of this drawing. Welds in Peripheral ICI Housings (Category B-O, Item No. B 14.21) are also shown on drawing M-189-501S1-RBB01 in Section A-A and include 5 locations, Penetrations 74-78.
Note 6: See Section H for an explanation of Category R-A and Item R1.XX nomenclature.
Note 7: The Pressurizer nozzle-to-safe end welds and safe end-to-piping welds were overlaid in Interval 3 during P.115. Per 13R-05, and Code Case N-770-1, 25% of these overlaid welds are now included in the ISI Program and examined once each inspection interval.
Note 8: See Section F for an explanation of the Category and Item designations.
WCRE-30                                                         4.1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 7 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Note 9: The VE exams are extended to once every     3 rd refueling outage per Note 4 of Code Case N-729-1. The acceptability of this frequency (EDY calculation) is documented in procedure STS PE-040E.
Note 10: The volumetric/surface exams are performed once every 8 calendar years. The acceptability of this frequency (MIY calculation) is documented in procedure STS PE-040E.
Note 11: The BMI~s are examined every other refueling outage beginning in RF17.
Note 12: The RPV Hot leg nozzle-to-pipe connections are required to be examined each refueling outage; however, per Note 5 of Table 1 of Code Case N-722-1, an ultrasonic examination is acceptable in lieu of the VE exam. Ultrasonic examinations (that meet the requirements of Note 5 of the subject Code Case) are tentatively scheduled for RF23 and RF26. These UT exams will be credited in lieu of the VE exams.
Note 13: The examination frequency requirement of these components is once per Interval.
Note 14: The examination frequency requirement of these components is each refueling outage.
Note 15: The initial examination of the MRP-146 locations was required in RF17. The MRP-146 locations have been seperated into 2 items: UK/H and DH. The UH-H item requires examination each refueling outage beginning with RFl9; and the DH items require examination every other refueling outage beginning in RF 19.
Note 16: This is a "One time" exam to be performed the first refueling outage after June 1, 2016 (RLF21).
WCRE-30                                                           4.1.4 Reactor Coolant System (BB)                                                      Revision 0 Page 8 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.4 Reactor Coolant (BB)
F. Augmented ISI Requirements The following Augmented IST 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, 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-33 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 Regulatory Guide 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 "AUG. 1" and Item No. "AUG.FW" but may be performed at anytime during the inspection interval. Approved Amendment 106 of the Technical Specifications allows examinations to be completed on each flywheel at an interval not to exceed 20 years
: 3. USNRC Regulatory Guide 1.65. Revision 0. Materials and Inspections 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 Examination Category B-G-1 of the 2007 Edition with the 2008 Addenda are understood to satisfy the WCNOC commitment to Regulatory Guide 1.65. These examinations are 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 1. 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.
: 7. Pressurizer Nozzle Weld Overlays-In Interval 3, a mitigation strategy was performed on the Pressurizer nozzle-to-safe end dissimilar metal (DM) piping welds by installation of a full structural weld overlay (WOL). Due to the configuration, this modification also encompassed the adjacent SS piping welds. These WOL configurations are tracked under Code Case N-770-l Inspection Items of Table 1, and under I3R-05. Examinations are on a 25% sampling basis each inspection interval. The components tracked under Code Case N-770-l are Item F (DM-R) for DM repaired welds, and Item C (DM-P) for DM preemptive welds,. The components tracked under I3R-05 are Item (SS-R) for SS repaired welds and Item (SS-P) for SS preemptive welds.
: 8. Code Case N-729-1-The NRC has mandated that ISI programs shall be augmented by the implementation of Code Case N-729- 1, with the conditions stated in 10 CFR 50.55a(g)(6)(ii)(D) by December 31, 2008.
: 9. Code Case N-722-l- The NRC has mandated that ISI programs shall be augmented by the implementation of Code Case N-722-l, with the conditions stated in 10 CFR 50.55a(g)(6)(ii)(E). The inspections required by this Code Case are required to begin the refueling outage after January 1, 2009.
: 10. MRP-146, Material Reliability Program: Management of Thermal Fatigne in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines-The evaluation for this program is documented in WCRE-25, Program Plan for Thermal Fatigue: The initial inspection of locations that did not pass the screening criteria in the applicable 2.1 sections of MRP-146 to be performed prior to the end of the next refueling outage that is initiated after January 31, 2009 (RFl17). Revision 1 of MRP-146 provides the option of performing periodic inspections in lieu of monitoring. Locations with UH/H configuration are WCRE-30                              4.1.4 Reactor Coolant System (BB)                                       Revision 0 Page 9 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN to be inspected every refueling outage (RFO) beginning with the first RFO after January 31, 2012 (RF 19).
Locations with the DR configuration are to be inspected every other RFO beginning with the first RFO after January 31, 2012 (RF 19). Such inspections shall be conducted in accordance with the requirements of section 2.4 of MRP-146, volumetric examination (UT or RT). Per letter MRP 2015-019, applicable section 2.3.2, a "One time examination of UH configured piping greater than 2-inches NPS and not larger than 4-inches NPS and having the potential of previous cold in-leakage" shall be performed no later that the first refueling outage commencing after June 1, 2016.
: 11. Code Case N-770 The NRC has mandated that ISI programs shall be augmented by the implementation of Code Case N-770-1, with the conditions stated in 10 CFR 50.55a(g)(6)(ii)(F). The inspections required by this Code Case are required to begin the refueling outage after August 22, 2011.
An additional notation is that the visual examination requirements of this Code Case are encompassed by the requirements of Code Case N-722- 1.
G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWB-5000, the Class 1 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 XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining components within the Reactor Coolant 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 lSI A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class 1 and 2 piping welds at WCGS. This program is described in detail in Section 2.3. Reactor Coolant System welds selected for examination per the RI-ISI program are listed in Tables BB-1, BB-2 and BB-3. Since the EPRI methodology used for the RI-ISI Program does not prescribe Code Examination Category and Item Numbers, guidance was taken fr-om 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-112657 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 through 4-4 of TR-1 12657 Rev. B-A.
Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table BB-1 (Period 1 Examinations), Table BB-2 (Period 2 Examinations), and Table BB-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 Category B-G-2, Notes 1 and 3.
: 2. Bolting is required to be examined only when a connection is disassembled or bolting is removed. For components other than piping, examination of bolting is required only when the component is examined under Examination Category B-B, B-L-2 and B-M-2. Examination of bolted connection is required only once during the interval. See Category B-G-2, Notes 1 and 2.
: 3. Examination may be alternatively performed on the bolts or studs in pump PBB01 B, PBB01 C, or PBB01D. See Category B-G-I, Note 3.
: 4. Examination of the pump flange will be pefformed when connection is disassembled for maintenance.
Examination may be alternatively performed on the pump flange of PBB01B, PBB01C, or PBB01D. See Category B-G-l, Notes 3 and 4.
WCRE-30                                4.1.4 Reactor Coolant System (BB)                                        Revision 0 Page 10 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN
: 5. Examination of the pump nuts, bushings and washers may be alternatively performed on the pump nuts, bushings and washers of PBB01B, PBB01C, or PBB01D. See Category B-G-l, Notes 3 and 4.
: 6. Examination of the steam generator hotleg and coldieg manway bolting may be alternatively performed on the bolting ofEBB01A, EBB01B, or EBB01D. See Category B-G-l, Notes 3 and 4.
: 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 or repair. The 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 that perform 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 to 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 fr'equency of examination of a 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 Generator Management," provides details of SG tubing inspection activities.
: 11. The 4 Pressurizer Seismic Supports (Code Item F1 .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
: 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. An enhanced VT-i examination may be performed in lieu of the UT examination per I1OCFR50.55a(b)(2)(xxi)(A).
: 15. Examination of the Reactor Nozzle-to-Vessel welds is performed in accordance with Code Case N-6 13-1, which allows an alternative examination volume to be utilized.
: 16. Examination of the Reactor Nozzle-to-Vessel inner radius area is performed in accordance with Code Case N-648-1, and the conditions specified in Revision 17 of Regulatory Guide 1.147.
: 17. These locations are subject to PWSCC. This examination may be performed at the same time as the Code Case N-770-1 exam.
: 18. Calibration of the instruments for this location will utilize reference blocks Axial/Flat 16-0 1 and Circ 16-01.
: 19. Calibration of the instruments for this location will utilize reference blocks Ax 6-01 and Circ 6-01.
: 20. Calibration of the instruments for this location will utilize reference blocks Ax 8-01 and Circ 8-01.
: 21. See CCP 11977 and WO 05-277921-000 for the modified thickness of these components.
WCRE-30                          4.1.4 Reactor Coolant System (BB)                                         Revision 0 Page 11 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN
: 22. These components have been selected in accordance with the Augmented ISI requirements of Code Case N-729-1 and conditions of 10 CFR 50.55a(g)(6)(ii)(D). The non-visual examination of these components shall utilize approved calibration blocks as required by the demonstrated procedure. The Item 4.10 components are to be examined every third refueling outage (an IWA-2212 VT-2 exam is performed under the insulation through multiple access ports in outages that the VE is not performed). The Item 4.20 components are to be examined every fifth refueling outage. The exams performed in RF15 under NRC Order EA-03-009 are credited for the baseline examinations.
: 23. These components have been selected in accordance with the Augmented 1S1 requirements of Code Case N-722-1 and conditions of 10 CFR 50.55a(g)(6)(ii)(E). These components to be examined every other refueling outage beginning in RF17.
: 24. These components have been selected in accordance with the Augmented 151 requirements of Code Case N-722-1 and conditions of 10 CFR 50.55a(g)(6)(ii)(E). These components to be examined every refueling outage beginning in RF17. Per Note 5 of Table 1 of the Code Case, an ultrasonic examination is acceptable in lieu of the VE examination. Ultrasonic examinations of these components are scheduled in RF17 and in RF20.
: 25. These components have been selected in accordance with the Augmented 1S1 requirements of Code Case N-722-1 and conditions of 10 CFR 50.55a(g)(6)(ii)(E). These components to be examined once per Interval.
: 26. These components have been selected in accordance with the Augmented ISI requirements of Code Case N-722-1 and conditions of 10 CFR 50.55a(g)(6)(ii)(E). These components to be examined every refueling outage beginning in RF17.
: 27. These locations have been selected per MRP- 146 guidance. See Paragraph F.10 above. The examination of these locations are to be in accordance with Section 2.4 of MRP-146. The initial exams were performed in RF17. The periodic examinations began in RF19. Locations designated as Item UH/H shall be examined each refueling outage. Locations designated as Item DH shall be examined every other refueling outage.
: 28. These components have been selected in accordance with the Augmented 1S1 requirements of Code Case N-770-l and conditions of 10 CFR 50.55a(g)(6)(ii)(F).
: 29. This location selected per MRP letter 2015-0 19. This is a "one time" examination to be performed in accordance with Section 2.3.2 of MRP 2015-019. This examination shall be performed in the first refueling outage commencing after June 1, 2016 (RF2 1). This examination is a supplement to the MRP-146 exams..
: 30. WCNOC procedures require that the 1S1 Coordinator be informed whenever a Class 1 component is disassembled for repair or maintenance and that the ISI Coordinator specify if a VT-i and/or VT-3 exam is required. Whenever a component is required to have a B-G-2 or B-M-2 exam performed, the ISI Coordinator shall revise the applicable Table BB-l, BB-2, or BB-3 and Table i to reflect the component being examined. Reference procedures AP 16A-003, ASME Section XI Repair and Replacement Program; and Al i6C-007, Work Order Planning.
WCRE-30                         4.1.4 Reactor Coolant System (BB)                                      Revision 0 Page 12 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB.1
[Period 1 Examinations
[System: BB Relief Request or Component Name    Drawing Number     Component Description                                     Size Thickness NDE Method Category Item    Cal Block         Notes CH-I 01-1 04-A    ISJ-RBB01 SHIT I   RV CLOSURE HEAD MERIDIONAL WELD                           NA        8.25     UT     B-A      B 1.22      177 TBB03-CIRCUJM-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 SHlT. 1  SAFETY NOZZLE A TO TOP HEAD WELD                         NA         1.90     UIT    B-D      B3.110      101 TBB03-10B-B-W     ISI-TBB03 SHT. 1   SAFETY NOZZLE B TO TOP HEAD WELD                         NA         1.90     UT     B-D      B3.110      101 TBB03-10B-A-IR    IS1-TBB03 SHIT. 1  SAFETY NOZZLE A INNER RADIUS                             NA         1.90     UT     B-D      B3. 120     101                14 TBB03-I 0B-B-IR   ISI-TBB03 SI-IT. 1 SAFETY NOZZLE B INNER RADIUS                              NA        1.90     UT     B-D      B3.120      101                14 EBB01C-IB-IR      ISI-EBB01C SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                        NA         5.00     UIT    B-D      B3.140      104                14 EBB01D-1A-IR      ISI-EBB01D SI-T. 1 PRIMARY INLET NOZZLE INNER RADIUS                        NA         5.00     UT     B-D      B3. 140     104                14 EBB01D-1B-IR      ISI-EBB01D SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                        NA         5.00     UT     B-D      B3. 140     104                14 TBB03-SKIRT-W     ISI-TBB03 SHT. 1   SUPPORT SKIRT INTEGRAL ATTACHMENT                                            PT     B-K      B10.1 RV-INTER1OR       ISI-RBB01 SHT. 1   REACTOR VESSEL INTERIOR                                                     VT-3    B-N-1    B13. 10 EBB01A-SEAM-3-W   ISI-EBB01A SilT. I STUB BARREL TO SHELL SECTION A                           NA         3.0      UT     C-A      CI.10       102 EBB01A-SEAM-6-W   ISI-EBB01A SHT. 1 TRANSITION CONE TO SHELL SECTION C                        NA         3.76     UT     C-A      CI.10       102 EBB01A-SEAM-2-W   ISI-EBB01A SI-T. 1 TUBESHEET TO STUB BARREL                                 NA         3.0      UT     C-A      C 1.30      102 EBB01A-1 1-W      ISI-EBB01A SHT. 1 FEED WATER NOZZLE WELD                                    NA         3.76   UT/MT    C-B      C2.21       102 EBB01 A- I 1-IR   ISI-EBB01A SHT. I FEED WATER NOZZLE INNER RADIUS                            NA         3.76     UT     C-B      C2.22       102 BB-02-R01 1       BB-01-02           PIPING SUPPORT                                                              VT-3    F-A      FI.1 BB-02-R015        BB-01-02           PIPING SUPPORT                                                              VT-3    F-A      FI.1 BB-04-R009        BB-01-04 SHT. 1    PIPING SUPPORT                                           4                  VT-3    F-A      Fl 10 BB-04-H009        BB-01-04 SILT. 2   PIPING SUPPORT                                           4                  VT-3    F-A      FI.10 WCRE-30                                                    4.1.4 Reactor Coolant System (BB)                                                           Revision 0 Page 13 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-1 IPeriod 1 ExaminationsI
[System: BB Relief Request or Cal Block         Notes Component Name Drawing Number   Component Description                                      Size Thickness NDE Method Category Item BB-04-R033     BB-01-04 SHT. 2  PIPING SUPPORT                                             4                 VT-3    F-A      Fl.10 CRDMPL-SUP- 1  ISI-CRDMPL       CRDM Upper Seismic Support                                                   VT-3    F-A      F1.40 CRDMPL-SUP-2   ISI-CRDMPL       CRDM Upper Seismic Support                                                   VT-3    F-A      F1.40 EBB01A-01 231  M-717-00002      SG A LOWER COLUMN SUPPORT                                                    VT-3    F-A      F1.40 EBB01A-05 231  M-717-00009      SG A LOWER LATERAL SUPPORT                                                   VT-3    F-A      F1.40 PBB01lA-SUP-1  ISI-PUMPS        RCP A TIE ROD SUPPORT                                                        VT-3    F-A      F 1.40 PBB01lA-SUP-lA ISI-PUMPS        RCP A COLUMN SUPPORT                                                         VT-3    F-A      F 1.40 RBB-01-01      ISI-RBB01 SHT. 1 RV SUPPORT PAD 1                                                             VT-3    F-A      F1.40                     14R-02 TBB03-SKIRT-W  ISI-TBB03 SHT. 1 SUPPORT SKIRT SUPPORT                                                        VT-3    F-A      F1.40 BB-0 l-F001    BB-05-01         14" NOZZLE ON 60-BCA-29" TO 14" PIPE                       14                 UT     R-A      RI ll      130                 12 1.25 BB-02-F019     BB-01-02         3" PIPE TO VALVE PCV-456A                                  3       0.438      UT     R-A      RI.ll      112             12, 13 BB-04-FW3 14   BB-01-04 SHT. 1  4" PIPE TO 4" ELBOW                                        4       0.531      UT     R-A      RI.1l      114             12, 13 BB-04-F010     BB-01-04 SHT. 2  4" PIPE TO 4" ELBOW                                        4       0.53 1     UT     R-A      RI.20      114                 12 BB-04-S007-D   BB-01-04 SPIT. 2 4" PIPE TO 4" ELBOW                                        4       0.531      UT     R-A      R1.20      114                 12 BB-04-S007-E   BB-01-04 SHT. 2  4" ELBOW TO 4" PIPE                                        4       0.53 1     UIT    R-A      R1.20      114                 12 BB-08-FW308    BB-01-08         2"'PUP PIECE TO 2" PIPE                                    2       0.344      UT     R-A      R1.20      156                 12 BB-08-FW309    BB-01-08         2" PIPE TO 2"X2"X3/4" TEE                                  2       0.344      UT     R-A      R1.20      156                 12 BB-08-FW3 11   BB-01-08         2"X2"X3/4" TEE TO 2" PIPE                                  2       0.344      UT     R-A      R1.20      156                 12 BB-08-FW3 12   BB-01-08         2" PIPE TO 2" ELBOW                                        2       0.344      UIT    R-A      R1.20      156                 12 BB-02-FW900    BB-01-02         6" ELBOW TO 6" PIPE                                        6       0.7 19     UT     R-A      R1.20      117                 12 RV-30 1-121-A  ISI-RBB01 SHT. 1 LOOP # 1 RPV OUTLET NOZZLE TO SAFE-END                     29       2.92      UT     R-A      R1.20      179                  12 WCRE-30                                                  4.1.4 Reactor Coolant System (BB)                                                         Revision 0 Page 14 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE    BB-1 I~rodT    Eaminations  I
[System: BB Relief Request or Component Name  Drawing Number    Component Description                                     Size Thickness NDE Method Category Item     Cal Block          Notes RV-302-12 1-A   ISI-RBBO1 SHT. 1  SAFE-END TO LOOP #1 RPV INLET NOZZLE                      27.5     2.79      UT     R-A      R1.20        179                12 RV-302-12 1-Dl  ISI-RBB01 SHT. 1  SAFE-END TO LOOP #4 RPV INLET NOZZLE                      27.5     2.79      UT     K-A      RI.20        179                12 RV-201-151-1   ISI-RBB01 SHT. 1 RV BMI PENETRATION     I                                                     VE     N-722-1  B15.80 RV-201-151-2   ISI-RBB01 SHT. 1 RV BMI PENETRATION    2                                                      VE     N-722-1  B 15.80 RV-201-151-3   ISI-RBBO1 SHT. 1 RV BM1 PENETRATION    3                                                      VE     N-722-1  B 15. 80 RV-201-151-4   ISI-RBB01 SHT. I RV BM1 PENETRATION    4                                                      VE     N-722-1  B 15.80 RV-201-151-5   ISI-RBB01 SHT. 1 RV BM1 PENETRATION    5                                                      VE     N-722-1  B 15.80 RV-201-151-6   ISI-RBBO1 SHT. I RV BMI PENETRATION    6                                                      VE     N-722-1  B 15.80 RV-201-151-7   ISI-RBB01 SHT. I RV BMI PENETRATION    7                                                      VE     N-722-1  B 15.80 RV-201-151-8   ISI-RBBO1 SHT. 1 RV BM1 PENETRATION    8                                                      VE     N-722-1  B15.80 RV-201-151-9   ISI-RBBOI SHT. I RV BMI PENETRATION    9                                                      VE     N-722-1  B15.80 RV-201-151-10  ISI-RBB01 SHT. I RV BM1 PENETRATION    10                                                     VE     N-722-1  B 15.80 RV-201-151-11I ISI-RBB01 SHT. 1 RV BM1 PENETRATION    11                                                     VE     N-722-I  B 15.80 RV-201-151-12  ISI-RBB01 SHT. 1 RV BMI PENETRATION     12                                                    VE     N-722-1  B15.80 RV-201-15l-13  ISI-RBB0 1 SHlT. 1 RV DM1 PENETRATION    13                                                     VE     N-722-1  B 15.80 RV-201-151-14  ISI-RBB01 SLIT. 1 RV BMI PENETRATION    14                                                     VE     N-722-1  B 15.80 RV-201-151-15  ISI-RBBO1 SHT. I RV BM1 PENETRATION    15                                                     VE     N-722-1  B 15.80 RV-201-151-16  ISI-RBB01I SHlT. 1 RV BMI PENETRATION    16                                                     VE     N-722-1  B 15.80 RV-201-151-17  ISI-RBB01 SHT. 1 RV BMI PENETRATION    17                                                     VE     N-722- I B15.80 RV-201-151-18  ISI-RBB01 SHT. 1 RV BMI PENETRATION    18                                                     VE     N-722-I  B15.80 RV-201-151-19  ISI-RBBO1 SHT. I RV BM1 PENETRATION    19                                                     VE     N-722-1  B 15.80 RV-201 -151-20 ISI-R.BB01 SHT. 1 RV BM1 PENETRATION    20                                                     VE     N-722-1  B 15.80 RV-201-151-21  ISI-RBB01 SilT. 1 RV BMI PENETRATION    21                                                     YE     N-722-1  B 15.80 RV-201 -151-22 ISI-RBBO01 SHT. 1 RV BMI PENETRATION    22                                                     VE     N-722-1  B 15.80 RV-201-151-23  ISI-RBB01 SHT. 1 RV BMI PENETRATION    23                                                     VE     N-722-1  B15.80 RV-201-151-24  ISI-RBB01 SHT. I RV BMI PENETRATION    24                                                     YE     N-722-1  B 15.80 RV-201-151-25  ISI-RBB0 1 SHT. 1 RV BMI PENETRATION    25                                                     VE     N-722-1  B 15.80 23 RV-201-151-26  ISI-RBBO01 SHT. 1 RV BMI PENETRATION    26                                                     VE     N-722-1  B15.80 RV-201-151-27  ISI-RDBB1 SHlT. I RV BMI PENETRATION    27                                                     YE     N-722-1  BI5.80 RV-201-151-28  ISI-RBB01 SHT. 1 RV DM1 PENETRATION    28                                                     YE     N-722-1  B15.80 RV-20l- 151-29 ISI-RBB01 SHT. I RV BM1 PENETRATION    29                                                     VE     N-722-1  B 15.80 RV-201-151-30  ISI-RBB01 SHIT. I RV BM1 PENETRATION    30                                                     VE     N-722-1  B 15.80 RV-201-151-31  ISI-RBB01 SHlT. 1 RV BMI PENETRATION    31                                                     VE     N-722-1  B15.80 RV-201-151-32  ISI-RBB01 SHlT. 1 RV BMI PENETRATION    32                                                     VE     N-722-1  B 15.80 RV-201-151-33  ISI-RBB01 SHT. I RV BM1 PENETRATION    33                                                     VE     N-722-1  B 15.80 RV-201-I51-34  ISI-RBB01 SHT. 1 RV BM1 PENETRATION    34                                                     VE     N-722-1  B 15.80 RV-201-151-35  ISI-RBB01 SHT. I RV BMI PENETRATION    35                                                     YE     N-722-1  B 15.80 RV-201-151-36  ISI-RBB01 SHT. 1 RV DMI PENETRATION    36                                                     YE     N-722-1  B15.80 RV-20 1-151-37 ISI-RBB01 SIHT. I RV BM1 PENETRATION    37                                                     VE     N-722-1  B 15.80 WCRE-30                                                    4.1.4 Reactor Coolant System (BB)                                                          Revision 0 Page 15 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE    BB-1 Ieo  Examinations Isystem: BB Relief Request or Component Name     Drawing Number       Component Description                                     Size Thickness NDE Method Category Item     Cal Block         Notes RV-201-151-38     ISI-RBB01   SHT. 1  RY  BMI   PENETRATION 38                                                     VE     N-722-1  B 15.80                         23 RV-201-151-39     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 39                                                     VE     N-722-1  B 15.80                         23 RV-201-151--40    ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 40                                                     VE     N-722-1  B15.80                          23 RV-201-151-41     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 41                                                     VE     N-722-1  B 15.80                         23 RV-201-151-42     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 42                                                     VE     N-722-1  B15.80                          23 RV-201-151-43     ISI-RBB01   SHT. I  RV  BMI   PENETRATION 43                                                     VE     N-722-1  815.80                          23 RV-201-1 51--44   ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 44                                                     VE     N-722-1  B 15.80                         23 RV-201-151-45     ISI-R.BB01  SHT. 1  RV  BMiI  PENETRATION 45                                                     VE     N-722-1  B 15.80                         23 RV-201-1 51--46   ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 46                                                     VE     N-722-1  B 15.80                         23 RV-201-151-47     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 47                                                     YE     N-722-1  B 15.80                         23 RV-201-151-48     ISI-RBB01   SI-T. 1  RV  BMI   PENETRATION 48                                                     YE     N-722-1  B 15.80                         23 RV-201-151-49     ISI-RBB01   SI-IT. I  RV  BMI   PENETRATION 49                                                     YE     N-722-1  B 15.80                         23 RV-201 -151-50    ISI-RBB01   SHT. I  RV  BMI   PENETRATION 50                                                     VE     N-722-1  B15.80                          23 RV-201-151-51     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 51                                                     YE     N-722-1  B 15.80                         23 RV-201-151-52     ISI-RBB01   SHT. I  RV  BMI   PENETRATION 52                                                     YE     N-722-1  B 15.80                         23 RV-201-151-53     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 53                                                     VE     N-722-1  B 15.80                         23 RV-201-151-54     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 54                                                     YE     N-722-1  B 15.80                         23 RV-201-151-55     ISI-RBB01   SHT. I  RV  BMI   PENETRATION 55                                                     YE     N-722-1  B15.80                          23 RV-201-151-56     ISI-RBB01   SHIT. I  RV  BMI   PENETRATION 56                                                     YE     N-722-I  815.80                          23 RV-201- 151-57    ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 57                                                     YE     N-722-1  B15.80                          23 RV-201-151-58     ISI-RBB01   SHT. 1  RV  BMIT  PENETRATION 58                                                     YE     N-722-1  815.80                          23 RV-301 -121 -A     ISI-RBB01   SHT. 1 LOOP   #1 RPV OUTLET NOZZLE   TO SAFE-END                29       2.92       VE     N-722-1  815.90                       24 RV-30 1-12 1-B     ISI-RBB01   SHT. 1 LOOP   #2 RPV OUTLET NOZZLE   TO SAFE-END                29       2.92       YE     N-722-1  B15.90                       24 RV-301-121-C       ISI-RBB01I  SHT. I LOOP   #3 RPV OUTLET NOZZLE   TO SAFE-END                29       2.92       YE     N-722-1  B 15.90                      24 RV-301-121-D       ISI-RBB01   SHT. I LOOP   #4 RPV OUTLET NOZZLE   TO SAFE-END                29       2.92       YE     N-722-1  815.90                       24 BB-01-S 102-TW-T   BB-01-01             LOOP   #1 NARROW   RANGE THERMOWELL,    TOP                                  YE     N-722-1  B 15.200                     26 BB-0 1-S 102-TW-I  BB-01-01             LOOP   #1 NARROW   RANGE THERMOWELL,    INSIDE                               YE     N-722-1  B15.200                      26 BB-01-S102-TW-O    BB-01-01             LOOP   # 1 NARROW  RANGE THERMOWELL,    OUTSIDE                              YE     N-722-1  815.200                      26 BB-01 -S202-TW-T   BB-02-01             LOOP   #2 NARROW   RANGE TH-ERMOWELL,   TOP                                  YE     N-722- I B 15.200                     26 BB-01-S202-TW-I    BB-02-01             LOOP   #2 NARROW   RANGE THERMOWELL,    INSIDE                               YE     N-722-1  B 15.200                     26 BB-01-S202-TW-O    BB-02--01            LOOP   #2 NARROW   RANGE THERMO WELL,   OUTSIDE                              VE     N-722-1  B 15.200                     26 BB-01-S302-TW-T    BB-03-01             LOOP   #3 NARROW   RANGE THERMOWELL,    TOP                                  YE     N-722-1  B815,200                     26 BB-01-S302-TW-I    BB-03-01             LOOP   #3 NARROW   RANGE TH-ERMO WELL,  INSIDE                               YE     N-722-1  B 15.200                     26 BB-01 -S302-TW-O   BB-03-01             LOOP   #3 NARROW   RANGE THERMO WELL,   OUTSIDE                              VE     N-722-1  B 15.200                     26 BB-01 -S402-TW-T   BB-04-01             LOOP   #4 NARROW   RANGE THERMOWELL,    TOP                                  YE     N-722-1  B 15.200                     26 BB-01-S402-TW-I    BB-04-01             LOOP   #4 NARROW   RANGE THERMO WELL,   INSIDE                               YE     N-722-1  815.200                      26 BB-01-S402-TW-O    BB-04-01             LOOP   #4 NARROW   RANGE THERMOWELL,    OUTSIDE                              YE     N-722-1  B15.200                      26 HB-24-W502         BB-06-01             2' ELBOW TO2" PIPE                                        2       0.344      UT     MRP-146  DH           156             27 WCRE-30                                                         4.1.4 Reactor Coolant System (BB)                                                           Revision 0 Page 16 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-1
[Period 1 Examinations SSystem: BB Relief Request or Component Name  Drawing Number    Component Description                                     Size Thickness NDE Method  Category Item Cal Block          Notes HB-24-W5 12     BB-06-0 1         2' ELBOW TO2" PIPE                                                0.344      UT     MRF-146   DHI      156              27 BG-23-W596A     BG-03-23          2" ELBOW TO2" PIPE                                                0.344      UT     MRP-1 46  DH       156              27 BG-21 -F027A BG-01-21                                                                                       UT     MRP-146   UH/H     112              27 3" PIPE TO 3" NOZZLE ON BB-56-BCA-27 1/2"                 3       0.438 BG-21 -F014A    BG-01-21          3" PIPE TO 3" NOZZLE ON BB-01-BCA-27 1/2"                 3       0.438      UIT    MRP-146   UH       112              29 RV-301-121-A    ISI-RBB0 1 SHT. 1 LOOP #1 RPV OUTLET NOZZLE TO SAFE-END                     29       2.92    UT/VE    N-770-1   A-2      179              28 RV-301-121-B    ISI-RBB01I SHT. l LOOP #2 RPV OUTLET NOZZLE TO SAFE-END                     29       2.92    UT/VE    N-770-1   A-2      179              28 RV-30 1-12 1-C  ISI-RBB01 SLIT. 1 LOOP #3 RPV OUTLET NOZZLE TO SAFE-END                     29       2.92    UT/VE    N-770-1   A-2      179              28 RV-301 -121 -D  ISI-RBB01 SHT. 1  LOOP #4 RPV OUTLET NOZZLE TO SAFE-END                     29       2.92    UT/VE    N-770-1   A-2      179              28 RV-302-12 1-A  ISI-RBB01 SHT. 1   SAFE-END TO LOOP #1 RPV INLET NOZZLE                      27.5    2.79      UT      N-770-1   B        179             28, RV-302-12 1-B  ISI-RBB01 SHT. 1   SAFE-END TO LOOP #2 RPV INLET NOZZLE                      27.5    2.79      UT      N-770-1   B        179             28, RV-302-121-C   ISI-RBB01 SHT. 1   SAFE-END TO LOOP #3 RPV INLET NOZZLE                      27.5    2.79      UT      N-770-1   B        179             28, RV-302-121-D   ISI-RBB0 1 SHT. I  SAFE-END TO LOOP #4 RPV INLET NOZZLE                      27.5    2.79      UT      N-770-1   B        179             28, WCRE-30                                                 WCRE-304.1.4 Reactor Coolant System (BB)                                                         Revision 0 Page 17 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2 IPeriod 2 Examinations
[System: BB Relief Request or Component Name     Drawing Number     Component Description                                     Size Thickness  NDE Method Category Item     Cal Block         Notes CH-101-104-B       ISI-RBB01 SHlT. 1  RV CLOSURE HEAD MERIDIONAL WELD                           NA        *8.25     UT     B-A      B 1.22       177 CH-10 1-104-C      ISI-RBB0 1 SHT. 1  RV CLOSURE HEAD MERIDIONAL WELD                           NA         8.25     UT     B-A      B 1.22       177 TBB03-CIRCUM- 1 -W ISI-TBB03 SHlT. 1  SHELL TO UPPER HEAD WELD                                  NA         1.90     UT     B-B      B2.11 101 TBB03-SEAM-4-W     ISI-TBB03 SHT. 1   SHELL TO UPPER HEAD LONGITUDINAL WELD                     NA         1.90     UT                           101 B-B      B2.12 TBB03-10B-C-W      ISI-TBB03 SHlT. 1  SAFETY NOZZLE C TO TOP HEAD WELD                          NA         1.90     UT     B-D      B3.1 10      101 TBB03-10B-D-W      ISI-TBB03 SHlT. 1  RELIEF NOZZLE D TO TOP HEAD WELD                          NA         1.90     UT     B-D      B3.110       101 TBB03-10B-C-IR     ISI-TBB03 SHlT. 1  SAFETY NOZZLE C INNER RADIUS                              NA         1.90     UT     B-D      B3. 120      101 14 TBB03-10B-D-IR     ISI-TBB03 SHlT. 1  RELIEF NOZZLE D INNER RADIUS                              NA         1.90     UT     B-D      B3. 120      101             14 EBB01 C-1A-IR      ISI-EBB01C SHlT. 1 PRIMARY INLET NOZZLE INNER RADIUS                         NA         5.00     UT     B-D      B3. 140      104             14 EBB01B-1A-IR.      ISI-EBB01B SHlT. 1 PRIMARY INLET NOZZLE INNER RADIUS                         NA         5.00     UT     B-D      B3. 140      104             14 EBB01B-1B-IR       ISI-EBB01B SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                         NA         5.00     UT     B-D      B3. 140      104             14 RV-INTERIOR        ISI-RBB01 SHlT. 1                                                                               VT-3    B-N-i    B 13. 10 REACTOR VESSEL INTERIOR EBBO1A-SEAM-5-W    ISI-EBB01A SHT. 1 SHELL SECTION B TO TRANSITION CONE                         NA         3.00     UT     C-A      CI.10        102 EBB01A-SEAM-8-W    ISI-EBB01A SHT. 1 SHELL SECTION D TO TOP HEAD                                NA         3.95     UT     C-A      C 1.20       102 BB-04-R012         BB-0 1-04 SHT. 1   PIPING SUPPORT                                            4                  VT-3    F-A      FI.1 BB-04-R017         BB-01-O4 SHT. 1    PIPING SUPPORT                                            6                  VT-3    F-A      FI.1 BB-04-R021l        BB-01-04 SHT. I    PIPING SUPPORT                                            4                  VT-3    F-A      FI.1 BB-04-C006         BB-01-04 SHT. 2    PIPING SUPPORT                                            4                  VT-3    F-A      FI.10 BB-04-C0100        BB-01-04 SHT. 2    PIPING SUPPORT                                            4                  VT-3    F-A      Ft.1 BB-04-H001         BB-01-04 SHT. 2    PIPING SUPPORT                                            4                  VT-3    F-A      FI.1 BB-04-H005         BB-01-04 SHT. 2                                                              4                  VT-3    F-A      FI.1 PIPING SUPPORT WCRE-30                                                      4.1.4 Reactor Coolant System (BB)                                                             Revision 0 Page 18 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BB-2 IPeriod 2 Examinations
[ Systm:BB Relief Request or Component Name Drawing Number   Component Description                                      Size Thickness NDE Method Category Item   Cal Block         Notes BB-02-H001     BB-02-02         PIPING SUPPORT                                             6                 VT-3    F-A BB-01-H001     BB-05-01         PIPING SUPPORT                                              14               VT-3    F-A HB-24-R015     BB-06-0 1        PIPING SUPPORT                                             2                 VT-3    F-A      FlI.10 CRDMPL-SUP-3   ISI-CRDMPL       CRDM Upper Seismfic Support                                                  VT-3    F-A      FI.40 CRDMPL-SUP-4   ISI-CRDMPL       CRDM Upper Seismic Support                                                   VT-3    F-A      Fl1.40 EBB01A-02 231  M-717-00002      SG A LOWER COLUMN SUPPORT                                                    VT-3    F-A      F 1.40 EBBO1A-06 231  M-71 7-00009     SG A LOWER LATERAL SUPPORT                                                   VT-3    F-A      FI.40 EBBO1A-07 231  M-71 7-00009     SG A LOWER LATERAL SUPPORT                                                   VT-3    F-A      F 1.40 EBB01A-08 231  M-717-00010      SG A UPPER LATERAL SUPPORT                                                   VT-3    F-A      Fl1.40 EBB01A-UP-2    M-717-00015      SG A UPPER LATERAL SUPPORT                                                   VT-3    F-A      Fl1.40 EBB01A=UP-3    M-717-00015      SG A UPPER LATERAL SUPPORT                                                   VT-3    F-A      F 1.40 PBB01 A-SUP-2  ISI-PUMPS        RCP A TIE ROD SUPPORT                                                        VT-3    F-A      F1.40 PBB01A-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      F 1.40                    I4R-02 RBB-01-03      ISI-RBB01 SHT. 1 RV SUPPORT PAD 3                                                             VT-3    F-A      F 1.40                    I4R-02 BB-04-FW302    BB-01-04 SHT. I  4" ELBOW TO 4" PIPE                                                           UT     R-A      RI.II      114             12, 13 4       0.53 1 BB-02-FW301    BB-02-02         6' 180 DEGREE RET. TO 6" FLANGE (VALVE 8010A)              6       0.7 19     UT     R-A      RI.11      117             12, 13 BB-01-F002     BB-05-01         14" PIPE TO 14" PIPE                                        14      1.25      UT     R-A      RI ll      130             12, 13 BB-01-S101-13  BB-01-01         3" NOZZLE TO 3" X 1.5" REDUCER                             3       0.438      UIT    R-A      RI.I11     112              12, 13 BB-01-$201-15  BB-02-01         3" NOZZLE TO 3" X 1.5" REDUCER                             3       0.438      UT     R-A      RI lI      112             12, 13 BB-01-F 108    BB-01-01         31" ELBOW TO 31" PIPE                                      31       2.88      UT     R-A      R1.20  SAP-01, 105             12 WCRE-30                                                  4.1.4 Reactor Coolant System (BB)                                                         Revision 0 Page 19 of 4.6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2 IPeriod 2 Examinations
[System: B88 Relief Request or Component Name       Drawing Number    Component Description                                       Size  Thickness     NDE Method Category item   Cal Block           Notes BB-0 1-S 105-04      BB-01-01          31" PIPE TO 31" ELBOW                                       31        2.88          UT     R-A      R1.20  SAP-01, 105              12 BB-04-S01 5-B        BB-01-04 SIT. 2   4" ELBOW TO 4" PIPE                                         4         0.531         UT     R-A      R1.20      114                  12 BB-04-S01 5-D        BB-01-04 SIT. 2   4" PIPE TO 4" ELBOW                                         4         0.531         UT     R-A      R1.20      114                  12 BB-04-S0 15-E        BB-01-04 SHT. 2   4" ELBOW TO 4" PIPE4                                                  0.531         UT     R-A      R1.20      114                  12 BB-02-S001-D         BB-02-02          6" ELBOW TO 6" PIPE6                                                  0.719         UT     R-A      R1.20       117                 12 BB-02-FW304          BB-02-02          6" ELBOW TO 6" PIPE6                                                  0.719         UT     R-A      R1.20      117                  12 BB-01-F103           BB-01-01          SAFE END TO 29" I.D. PIPE                                   29          2.5         UT     R-A      R1.20  SAP-01, 105              12 BB-01-F203           BB-02-01          SAFE END TO 29" ID PIPE                                     29          2.5         UT     R-A      R1.20  SAP-07, 106              12 BB-01-F303           BB-03-01          SAFE END TO 29" ID PIPE                                     29          2.5         UT     R-A      R1.20  SAP-07, 106              12 TBB03-MW7086-WOL-DM  ISI-TBB03 SHT. 1  SAFETY NOZZLE A TO SAFE-END WELD OVERLAY                    6    See I, Note 21     UT     N-770-1  DM-P  See I, Note 20 BB-02-MW7086-WOL-SS  BB-02-02          SAFETY NOZZLE A SAFE-END TO PIPE WELD OVERLAY               6    See I, Note 21     UT     I3R-05   SS-R  See I, Note 20 CH-107-101          ISI-RBB0 1 SHT. I RV  VENT PENETRATION                                                                 VE    N-729-I  B4.10                           22 CH-1 12-201         ISI-RBB0 1 SIHT. I RV  CRDM PENETRATION 1                                                              VE     N-729-1  B4.10                           22 CH-1 12-202-2       ISI-RBB01 SHT. I RV  CRDM PENETRATION 2                                                              VE     N-729-1  B4.10                           22 CH-1 12-202-3       ISI-RBBO1 SHT. 1 RV  CRDM PENETRATION 3                                                              VE     N-729-1  B4.10                           22 CH- 112-202-4       ISI-RBB0 1 SHT. I RV  CRDM PENETRATION 4                                                              VE     N-729-1I B4.10                        22 CH-1 12-202-5       ISI-RBB01 SHT. 1 RV  CRDM PENETRATIONS5                                                              VE     N-729-1  B4.10                        22 CH-1 12-203-6       ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 6                                                              VE     N-729- I B4.10                        22 CH-1 12-203-7       ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 7                                                              VE     N-729-1  B4.10                        22 CH-1 12-203-8       ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 8                                                              VE     N-729-1  B4.10                        22 Cl-1-i12-203-9      ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 9                                                              VE     N-729-1  84.10                        22 CH-I112-204-10      ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 10                                                             VE     N-729-1  B4.10                        22 CH-1 12-204-11      ISI-RBB01 SI-T. I RV  CRDM PENETRATION 11                                                             VE     N-729-1  B4.10                        22 CH-1 12-204-12      ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 12                                                             VE     N-729-1  84.10                        22 CH-1 12-204-13      ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 13                                                             VE     N-729-1  B4.10                        22 CH-1 12-205-14      ISI-RBB0I SI-T. I RV  CRDM PENETRATION 14                                                             VE     N-729-1  84.10                        22 CH-1 12-205-15      ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 15                                                             VE     N-729-1  B4.10                        22 CH-1 12-205-16      ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 16                                                             VE     N-729-1  B4.10                        22 CH-1 12-205-17      ISI-RBB01 SIT. 1 RV  CRDM PENETRATION 17                                                             VE     N-729-1  84.10                        22 Cl-I-i12-206-18     ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 18                                                             VE     N-729-1  84.10                        22 CH-1 12-206-19      ISI-RBB01 SI-T. 1 RV  CRI7M PENETRATION 19                                                            VE     N-729-1  B4.10                        22 WCRE-30                                                        4.1.4 Reactor Coolant System (BB)                                                                 Revision 0 Page 20 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2
[Period 2 Examinations SSystem: BB Relief Request or Component Name    Drawing Number    Component Description                                    Size Thickness NDE Method Category Item   Cal Block          Notes CE-I! 12-206-20  ISI-RIBB01 SET. I  RV CRDM PENETRATION 20                                                      VE     N-729-1  B4.10                      22 CE-i112-206-21   ISI-RBB01 SHT. 1   RV CRDM PENETRATION 21                                                      VE     N-729-1  B4.10                      22 CH-1 12-207-22   ISI-RIBB01 SET. 1  RV CRDM PENETRATION 22                                                      VE     N-729-1  B4.10                      22 CE-i112-207-23   ISI-RIBB01 SHT. 1  RV CRDM PENETRATION 23                                                      VE     N-729-1  B4.10                      22 CE-I 12-207-24   ISI-RBB01I SHT. I  RV CRDM PENETRATION 24                                                      VE     N-729-1  B4.l0                      22 CH-1 12-207-25   ISI-RIBB01 SHT. 1  RV CRDM PENETRATION 25                                                      VE     N-729-1  B4.10                      22 CE-I112-207-26   ISI-RIBB01 SHIT. 1 RV CRDM PENETRATION 26                                                      VE     N-729-1I B4.10                      22 CH-1 12-207-27   ISI-RBB01 SET. I   RV CRDM PENETRATION 27                                                      VE     N-729-1  B4.10                      22 CH- 112-207-28   ISI-RBB01 SET. 1   RV CRDM PENETRATION 28                                                      VE     N-729-1  B4.10                      22 CH-1 12-207-29   ISI-RBBO1 SHT. 1   RV CRDM PENETRATION 29                                                      VE     N-729-1  B4.10                      22 CH-1 12-208-30   ISI-RIBB01 SHIT. 1 RV CRDM PENETRATION 30                                                      VE     N-729-1  B4.10                      22 CH- 112-208-31   ISI-RBB01 SHT. 1   RV CRDM PENETRATION 31l                                                     VE     N-729-1  B4.10                      22 CH-1 12-208-32   ISI-RBB01 SET. 1   RV CRDM PENETRATION 32                                                      VE     N-729-I  B4.10                      22 CH-1 12-208-33   ISI-RBB01 SET. I   RV CRDM PENETRATION 33                                                      VE     N-729-1  B4.10                      22 CH-1 12-208-34   ISI-RBB01 SHT. 1   RV CRDM PENETRATION 34                                                      VE     N-729-1  B4. 10                     22 CH-I 12-208-35   ISI-RIBB01 SET. I  RV CRDM PENETRATION 35                                                      VE     N-729-1  B4.10                      22 CE-i112-208-36   ISI-RIBB01 SELT. 1 RV CRDM PENETRATION 36                                                      VE     N-729-1  B4.10                      22 CU-I112-208-37   ISI-RBB01 SET. 1   RV CRDM PENETRATION 37                                                      VE     N-729-1  B4.10                      22 Cl-I-i12-209-3 8 ISI-RBB01 SET. 1   RV CRDM PENETRATION 38                                                      VE     N-729-1  B4.10                      22 CH-1 12-209-39   ISI-RBB01 SET. I   RV CRDM PENETRATION 39                                                      VE     N-729-I  B4.10                      22 Cl--i12-209-40   ISI-RBB01 SET. 1   RV CRDM PENETRATION 40                                                      VE     N-729- I B4.10                      22 CH-1 12-209-41   ISI-RBB01 SET. 1   RV CRDM PENETRATION 41                                                      VE     N-729-1  B4.10                      22 CE-I112-210-42   ISI-RIBB01 SET. 1  RV CRDM PENETRATION 42                                                      VE     N-729-1  B4.10                      22 CU-I112-210-43   ISI-RIBB01 SEIT. 1 RV CRDM PENETRATION 43                                                      VE     N-729-1  B4. 10                     22 CH-1 12-210-44   ISI-RBB0 1 SET. 1  RV CRDM PENETRATION 44                                                      VE     N-729-1  B4.10                      22 CE-i112-210-45   ISI-RBB01 SET. 1   RV CRDM PENETRATION 45                                                      VE     N-729-i  B4.10                      22 CH-112-21I0.46   ISI-RBB01 SEIT. 1  RV CRDM PENETRATION 46                                                      VE     N-729-1  B4.10                      22 CH-1 12-210-47   ISI-RBB01 SELT. 1  RV CRDM PENETRATION 47                                                      VE     N-729-1  B4. 10                     22 CE-112-210.48    ISI-RBB01 SET. 1   RV CRDM PENETRATION 48                                                      VE     N-729-1  B4.10                      22 CH-1 12-210-49   ISI-RIBB01 SET. I  RV CRDM PENETRATION 49                                                      VE     N-729-1  B4.10                      22 CH-1 12-211-50   ISI-RBB01 SET. I   RV CRDM PENETRATION 50                                                      VE     N-729-1  B4.10                      22 CH-112-211-51    ISI-RBB01 SEIT. I  RV CRDM PENETRATION 51                                                      VE     N-729-1  B4. 10                     22 CH-1 12-211-52   ISI-RBB01 SET. 1   RV CRDM PENETRATION 52                                                      VE     N-729-l  B4.10                      22 CH-1 12-211-53   ISI-R.BB01 SET. I  RV CRDM PENETRATION 53                                                      VE     N-729-1  B4.10                      22 CH-1 12-212-54   IS1-RiBB01 SET. 1  RV CRDM PENETRATION 54                                                      VE     N-729-1  B4.10                      22 CE-I112-212-55   ISI-RIBB01 SELT. 1 RV CRDM PENETRATION 55                                                      VE     N-729-1  B4.10                      22 CH-1 12-212-56   ISI-RBB01 SET. 1   RV CRDM PENETRATION 56                                                      VE     N-729-1  B4.10                      22 CH-1 12-212-57   ISI-RBB01 SET. 1   RV CRDM PENETRATION 57                                                      VE     N-729-1  B4.10                      22 CH-1 12-212-58   1SI-RBB01 SET. 1   RV CRDM PENETRATION 58                                                      VE     N-729-1  B4.10                      22 CH-1 12-212-59   ISI-RBB01 SET. 1   RV CRDM PENETRATION 59                                                      VE     N-729-1  B4.10                      22 CE-I112-212-60   ISI-RBB0 1 SELT. 1 RV CRDM PENETRATION 60                                                      VE     N-729-1  B4.10                      22 CH-112-212-61    ISI-RBB01 SET. 1   RV CRDM PENETRATION 61                                                      VE     N-729-1  B4.10                      22 WCRE-30                                                   4.1.4 Reactor Coolant System (BB)                                                          Revision 0 Page 21 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2 Isystem: BBl Relief Request or Component Name   Drawing Number     Component Description                                 Size Thickness NDE Method Category Item   Cal Block         Notes CR-i112-213-62  ISI-RBB01  SRT. I  RV CRDM PENETRATION    62                                                VE     N-729-1  B4. 10                     22 CH-1 12-213-63  ISI-RBB01  SHT. 1  RV CRDM PENETRATION    63                                                VE     N-729-I  84.10                      22 CR-i112-213-64  ISI-RBB01  SIHT. 1  RV CRDM PENETRATION    64                                                VE     N-729-1  84.10                      22 CH-I112-213-65  ISI-RBB01  SRT. 1  RV CRDM PENETRATION    65                                                VE     N-729-1I 84.10                      22 CH-1 12-214-66  ISI-RBB01  SRT. 1  RV CRDM PENETRATION    66                                                VE     N-729-1  B4.10                      22 CR-1 12-214-67  ISI-RBB01  SHT. I  RV CRDM PENETRATION    67                                                VE     N-729-I  B4.10                      22 CH-1 12-214-68  ISI-RBBO01 SHT. 1  RV CRDM PENETRATION    68                                                VE     N-729-1  B4.10                      22 CR-i112-214-69  ISI-RBB01  SHT. I  RV CRDM PENETRATION    69                                                VE     N-729-1  84.10                      22 CH-1 12-214-70  ISI-RBB01  SILT  I  RV CRDM PENETRATION    70                                                VE     N-729-1  B4. 10                     22 CH-1 12-214-71  ISI-RBB01  SUT. I  RV CRDM PENETRATION    71                                                VE     N-729-1  B4.10                      22 CR-i112-214-72  ISI-RBB01  SHT. 1  RV CRDM PENETRATION    72                                                VE     N-729-1  84.10                      22 CH-1 12-214-73  ISI-RBB01  SRT. 1  RV CRDM PENETRATION    73                                                VE     N-729-I  B4.10                      22 CH-1 12-215-74  ISI-RBB01  SHT. 1  RV CRDM PENETRATION    74                                                VE     N-729-1  84.10                      22 CH-1 12-215-75  ISI-R8B01  SRLT. 1  RV CRDM PENETRATION    75                                                VE     N-729-1  B4.10                      22 CH-1 12-215-76  ISI-RBB01  SRT. 1  RV CRDM PENETRATION    76                                                VE     N-729-1  B4.10                      22 Cl-I1I12-215-77 ISI-RBB01  SRT. 1  RV CRDM PENETRATION    77                                                VE     N-729-1  84.10                      22 CR-I112-215-78  ISI-RBB01  SHT. 1  RV CRDM PENETRATION    78                                                VE     N-729-1  B4.10                      22 CH-107-I01      ISI-RBB01  SHT. 1  RV VENT PENETRATION                                   NA        NA      UT/ET N-729-I  B4.20                      22 CR-112-201      ISI-RBB01  SRT. 1  RV CRDM PENETRATION    1                              NA        NA      UT/ET   N-729-1  84.20                      22 CR-i 112-202-2  ISI-RBB01  SRT. 1  RV CRDM PENETRATION    2                              NA        NA      UT/ET   N-729-1  B4.20                      22 CH- 112-202-3   ISI-RBB01  SHT. I  RV CRDM PENETRATION    3                              NA        NA      UT/ET   N-729-1  84.20                      22 CR-I112-202-4   ISI-RBB01  SHiT. 1  RV CRDM PENETRATION    4                              NA        NA      UT/ET   N-729-1  84.20                      22 CH-1 12-202-5   ISI-RBB01  SRT. 1  RV CRDM PENETRATION    5                              NA        NA      UT/ET   N-729-1  B4.20                      22 Cl-i- 112-203-6 ISI-RBB01  SHT. 1  RV CRDM PENETRATION    6                              NA        NA      UT/ET   N-729-1  B4.20                      22 CR-i112-203-7   ISI-RBB01  SILT. I RV CRDM PENETRATION    7                              NA        NA      UT/ET   N-729-1  84.20                      22 CR-i 112-203-8  ISI-RBB01  SilT. 1  RV CRDM PENETRATION    8                              NA        NA      UT/ET   N-729-I  B4.20                      22 CH-1 12-203-9   ISI-RBB01  SRT. 1  RV CRDM PENETRATION    9                              NA        NA      UT/ET   N-729-1  B4.20                      22 CH-i112-204-10  ISI-RBB801 SRIT. I  RV CRDM PENETRATION     10                            NA        NA      UT/ET   N-729-1  B4.20                      22 CR-i112-204-11  ISI-RIBB01 SHiT. 1  RV CRDM PENETRATION     11                            NA        NA      UT/ET   N-729-1  84.20                      22 CH-1 12-204-12  ISI-RBB01  SRT. 1  RV CRDM PENETRATION     12                            NA        NA      UT/ET   N-729-1  B4.20                      22 CH-I112-204-13  ISI-RBB01  SET. 1  RV CRDM PENETRATION     13                            NA         NA     UT/ET   N-729-I  84.20                      22 CR-1 12-205-14  ISI-RBB01  SHT. 1  RV CRDM PENETRATION     14                            NA         NA     UT/ET   N-729-I  84.20                      22 CR-i112-205-15  ISI-RBB01  SRT. I  RV CRDM PENETRATION     15                            NA         NA     UT/ET   N-729-1  84.20                      22 CR-i112-205-16  ISI-R.BB01 SRT. 1  RV CRDM PENETRATION     16                            NA         NA     UT/ET   N-729-1  84.20                      22 CR-I112-205-17  ISI-RBB01  SHT. 1  RV CRDM PENETRATION     17                            NA         NA     UT/ET   N-729-1  84.20                      22 CH-1 12-206-18  ISI-RBB01  SET. 1  RV CRDM PENETRATION     18                            NA         NA     UT/ET   N-729-1  84.20                      22 CR-I112-206-19  ISI-RBB01  SRT. 1  RN CRDM PENETRATION     19                            NA         NA     UT/ET   N-729-1  84.20                      22 CH- 112-206-20  ISI-RBB01  SRT. 1  RV CRDM PENETRATION    20                             NA         NA     UT/ET   N-729-1  84.20                      22 CR-i112-206-2 1 ISI-RBB01  SRT. 1  RV CRDM PENETRATION    21                             NA         NA     UT/ET   N-729-1  84.20                      22 CR-i112-207-22  ISI-RBB01  SHT. 1 RV CRDM PENETRATION    22                              NA        NA     UT/ET   N-729-1  84.20                      22 CR-i112-207-23  ISI-RBB0!  SRT. 1 RV CRDM PENETRATION    23                              NA        NA     UT/ET   N-729-1  84.20                      22 WCRE-30                                                      1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 22 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BB-2
[Period 2 Examinations ISystem: 8B8 Relief Request or Component Name    Drawing Number    Component Description                                    Size Thickness NDE Method Category Item  Cal Block         Notes CR-i112-207-24   1S1-REDO01 SRT. 1  RV CRDM PENETRATION 24                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-I112-207-25   1SI-RBBO01 SHT. 1  RV CRDM PENETRATION 25                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-I112-207-26   ISI-RB801I SKIT. I RV CROM PENETRATION 26                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR- 112-207-2?   ISI-RBB01 SHT. 1   RV CRDM PENETRATION 27                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i112-207-28   1SI-RBB0 1 SHT. 1  RV CRDM PENETRATION 28                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-I112-207-29   ISI-RBB01 SHT. 1   RV CRDM PENETRATION 29                                   NA        NA     UT/FT    N-729-1  84.20                    22 CR-i112-208-30   ISI-RBB0 1 SRT. 1  RV CRDM PENETRATION 30                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i112-208-3 1  151-REDO01 SRT. I  RV CRDM PENETRATION 31                                   NA        NA     UT/ET    N-729-I  84.20                    22 CR-i112-208-32   1SI-RBB01 SLRT. 1  RV CRDM PENETRATION 32                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i 112-208-33  1S1-RBB0 I SHT. 1  RV CRDM PENETRATION 33                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i1!2-208-34   ISI-RBB01 SHT. I   RY CRDM PENETRATION 34                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i 112-208-35  1SI-RBB0 1 SRT. 1  RV CRDM PENETRATION 35                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR-i112-208-36   1SI-RBB01I SHT!. I RV CRDM PENETRATION 36                                   NA        NA     UT/FT    N-729-I  84.20                    22 CR-i112-208-37   1SI-R8B01 SHT. 1   RV CRDM PENETRATION 37                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i 112-209-38  lSi-RBB01 SILT. 1  RV CRDM PENETRATION 38                                   NA        NA     UT/FT    N-729-I  84.20                    22 CR-i112-209-39   ISI-RBB0 1 SHT. 1  RV CRDM PENETRATION 39                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR- 112-209-40   1SI-RBB0 1 SHT. 1  RV CRDM PENETRATION 40                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i112-209-41   ISI-RBB01 SHT. 1   RV CRDM PENETRATION 41                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i112-210-42  1SI-RBB01 SRT. 1    RV CRDM PENETRATION 42                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i112-210-43   151-REDO01 SRT. 1  RV CRDM PENETRATION 43                                   NA        NA     UT/FT    N-729-1  84.20                    22 CH-i112-210-44  ISI-RBB01 SRT. 1    RV CRDM PENETRATION 44                                  NA         NA     UT/ET    N-729-1  84.20                    22 CH-112-210-45   IST-REDO0I SRT. 1   RV CRDM PENETRATION 45                                  NA         NA     UT/ET    N-729-I  84.20                    22 CR-i112-210-46  ISI-RiBB01 SRT. 1   RV CRDM PENETRATION 46                                  NA         NA     UT/FT    N-729-i  84.20                    22 CR-i112-210-47  1SI-REBO01 SRT. 1   RV CRDM PENETRATION 47                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR-i112-210-48   ISI-RBBO01 SRT. 1  RV CREM PENETRATION 48                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i112-210-49   IS1-RBBO01 SLIT. 1 RV CRDM PENETRATION 49                                  NA         NA     UTT/ET   N-729-1  84.20                    22 CR-i112-211-50   1SI-REDO0I SLRT. 1 RY CRDM PENETRATION 50                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR-112-21il-5i   1SI-REDO0I SRT. I  RV CRDM PENETRATION 51                                   NA        NA     UT/FT    N-729-1  84.20                    22 CR-i112-211-52   ISI-RBBO01 SRT. 1  RV CRDM PENETRATION 52                                   NA        NA     UT/FT    N-729-1  84.20                    22 CR-I112-211-53   1S1-REDO01 SRT. 1  RV CRDM PENETRATION 53                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR-i112-212-54  ISI-RBB01 SHT. 1    RV CRDM PENETRATION 54                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i112-212-55  ISI-REDOI SIIT. 1   RV CRDM PENETRATION 55                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR-i112-212-56   ISI-REDB0I SHT. 1  RV CRDM PENETRATION 56                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i112-212-57   1S1-REDO01 SRT. 1  RV CRDM PENETRATIONS?7                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR- 112-212-58   ISI-RBB01 SHIT. I  RV CRDM PENETRATION 58                                   NA        NA     UT/ET    N-729-i  84.20                    22 CR-I112-212-59   ISI-RBB01 SI-T. 1  RV CRDM PENETRATION 59                                  NA         NA     UT/FT    N-729-i  84.20                    22 CR-i1i2-212-60   ISI-RBDOI SIRT. 1  RV CRDM PENETRATION 60                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i112-212-61   ISI-RBBO0I SHT. 1  RV CRDM PENETRATION 61                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i112-21.3-62  ISI-RBBO01 SHT. 1  RV CRDM PENETRATION 62                                   NA        NA     UT/FT    N-729- I 84.20                    22 CR-i112-213-63   ISI-REBB0 SHIT. I  RV CRDM PENETRATION 63                                  NA         NA     UT/FT    N-729- I 84.20                    22 CR-i112-213-64   ISI-REDO01 SRT. 1  RV CRDM PENETRATION 64                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR-I112-213-65   ISI-RBD01 SHIT. 1  RV CRDM PENETRATION 65                                  NA         NA     UT/ET    N-729-1  84.20                    22 WCRE-30                                                    1.4 Reactor Coolant System (BB)                                                        Revision 0 Page 23 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2
[Peiod 2Examinations I ISystem: BBI Relief Request or Component Name   Drawing Number     Component Description                                     Size Thickness NDE Method Category Item     Cal Block         Notes CH-1 12-214-66  ISI-RBB01   SI-T. 1 RV CRDM  PENETRATION     66                               NA        NA      UJT/ET  N-729-I  B4.20                        22 CH-1 12-214-67  ISI-RBB01   SHT. I RV CRDM  PENETRATION     67                               NA         NA     UT/ET   N-729-1  B4.20                        22 CH-1 12-214-68  ISI-RBB01   SHT. I RV CRDM  PENETRATION     68                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-214-69  ISI-RBB01   SI-T. I RV CRDM  PENETRATION     69                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-214-70  ISI-RBB01   SHT. 1 RV CRDM  PENETRATION     70                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-214-71  ISI-RBB01   SHlT. 1 RV CRDM  PENETRATION     71                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-214-72  ISI-RBB01   SHT. 1 RV CRDM  PENETRATION     72                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-214-73  ISI-RBB01   SHT. 1 RV CRDM  PENETRATION     73                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-215-74  ISI-RBB01   SHT. 1 RV CRDM  PENETRATION     74                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-112-215-75   1SI-RBB01  SHIT. I RV CRDM  PENETRATION     75                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-112-215-76   ISI-RBB01  SHT. 1 RV CRDM  PENETRATION     76                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-215-77  ISI-RBB01  SI-T. 1 RV CRDM  PENETRATION     77                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-215-78  ISI-RBB01   SHT. 1 RV CRDM  PENETRATION      78                              NA        NA      UT/ET   N-729-1  B4.20                        22 RV-201-151-1    ISI-RBB01 SI-IT. 1                                                                               VE    N-722-1  B 15.80                      23 RV BMI PENETRATION    I RV-201-151-2    ISI-RBB01 SHT. 1 RV BMI PENETRATION    2                                                       VE    N-722-1  B 15.80                      23 RV-201-151-3    ISI-RBB01 SHT. 1 RV BMI PENETRATION    3                                                      VE     N-722-1  B 15.80                      23 RV-201-I151-4   ISI-RBB01 SHT. 1 RV BMI PENETRATION    4                                                       VE    N-722-1  B15.80                       23 RV-201-151-5    ISI-RBB01 SHT. 1 RV BMI PENETRATION    5                                                      VE     N-722-1  B1 5.80                      23 RV-201-151-6    ISI-RBB01 SI-T. 1 RV BMI PENETRATION    6                                                      VE     N-722-1  B 15.80                      23 RV-201 - 151-7  ISI-RBB01 SHT. I RV BMI PENETRATION    7                                                       VE    N-722-I  B 15.80                      23 RV-201-151-8    ISI-RBB01 SI-T. 1 RV BMI PENETRATION    8                                                       VE    N-722-I  B 15.80                      23 RV-201-151-9    ISI-RBB01 SI-IT. I RV BMI PENETRATION    9                                                      VE     N-722-1  B 15.80                      23 RV-201-151-10   ISI-RBB01 SHT. I RV BMI PENETRATION    10                                                     VE     N-722-1  B 15.80                      23 R.V-20 1-151-11 ISI-RBB01 SHIT. 1 RV BMI PENETRATION    11                                                     VE     N-722-1  B 15.80                      23 RV-201-151-12   ISI-R.BB01 SHlT. 1 RV BMI PENETRATION    12                                                     VE     N-722-1  B 15.80                      23 RV-201-151-13   ISI-RBB01 SHT. 1 RV BMI PENETRATION    13                                                     VE     N-722-1  B 15.80                      23 RV-201-151-14   ISI-RBB01 SHT. 1 RV BMI PENETRATION    14                                                      VE    N-722-1  B 15.80                      23 RV-201-1 51-15  ISI-R.BB0 1 SI-T. 1 RV BMI PENETRATION    15                                                      VE    N-722-1  B 15.80                      23 RV-201-1 51-16  ISI-RBB01 SHT. I RV BMI PENETRATION     16                                                     VE    N-722-1  B15.80                       23 RV-201-1 51-17  ISI-RBB01 SHT. 1 RV BMI PENETRATION    17                                                      VE    N-722-1  B 15.80                      23 RV-20 1-151-18  ISI-RBB01 SHT. I RV BMI PENETRATION    18                                                      VE    N-722-1  B 15.80                      23 RV-201-1 51-19  1SI-RBB01 SHT. 1 RV BMI PENETRATION    19                                                      VE    N-722-1  B 15 .80                     23 RV-201I-151-20  ISI-RBB01 SI-T. I RV BMI PENETRATION    20                                                      VE    N-722-1  B 15.80                      23 RV-201 - 151-21 ISI-RBB01 SI-T. 1 RV BMI PENETRATION    21                                                      VE    N-722-1  B 15.80                      23 RV-201-151-22   ISI-RBB01 SHT. I RV BMI PENETRATION    22                                                      VE    N-722-1  B 15.80                      23 RV-201-151-23   ISI-RBB01 SHT. I RV BMI PENETRATION    23                                                      VE    N-722-1  B 15.80                      23 RV-201-151-24   ISI-RBB01 SHT. I RV BMI PENETRATION    24                                                      VE    N-722-1  B15.80                       23 RV-201-151-25   ISI-RBB01 SHT. I RV BMI PENETRATION    25                                                      VE    N-722-1  B 15.80                      23 RV-201-151-26   ISI-RBB01 SHT. 1 RV BMI PENETRATION    26                                                      VE    N-722-1  B15.80                       23 RV-201-151-27   ISI-RBB01 SHT. I RV BMI PENETRATION    27                                                      VE    N-722-1  B 15.80                      23 RV-201-151-28   ISI-RBB01 SHT. 1 RV BMI PENETRATION    28                                                      VE    N-722-1  B 15.80                      23 WCRE-30                                                      4.1.4 Reactor Coolant System (BB)                                                         Revision 0 Page 24 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2 IPeriod 2 Examinations
[System: BB Relief Request or Component Name    Drawing Number    Component Description                                      Size Thickness NDE Method Category Item     Cal Block          Notes RV-201-151-29    ISI-RBBOI SHlT. I RV BMI PENETRATION 29                                                         VE     N-722-1  BI15.80                      23 RV-201-151-30    ISI-RBB01 SHT. 1 RV BMI PENETRATION 30                                                         VE     N-722-1  B1 5.80                      23 RV-201-151-31   ISI-RBB01 SHT. 1 RV BMI PENETRATION 31                                                         YE     N-722-1  B 15.80                      23 RV-201-I151-32  ISI-RBB01 SHlT. 1 RV BMI PENETRATION 32                                                         VE     N-722-1  B 15.80                      23 RV-201-151-33   ISI-RBBO1 SHlT. 1 RV BMI PENETRATION 33                                                         VE     N-722-1  B 15.80                      23 RV-201-151-34   ISI-RBB01 SI-T. 1 RV BMI PENETRATION 34                                                         VE     N-722-I  B 15.80                      23 RV-201-1 51-35  ISI-RBB01 SHlT. 1 RV BMI PENETRATION 35                                                         VE     N-722-I  B 15.80                      23 RV-201-151-36   ISI-RBB01 SI-T. I RV BMI PENETRATION 36                                                         VE     N-722-lI B 15.80                      23 RV-201-151-37   ISI-RBB01 SHlT. 1 RY BMI PENETRATION 37                                                         VE     N-722-1  B15.80                       23 RV-201-151-38   ISI-RBB01 SilT. 1 RY BMI PENETRATION 38                                                         VE     N-722-1  B 15.80                      23 RV-201 -151-39  ISI-REBB1 SHlT. 1 RV BMI PENETRATION 39                                                         VE     N-722-1  B 15.80                      23 RV-201-151-40   ISI-RBB01 SilT. 1 RV BMI PENETRATION 40                                                         VE     N-722-1  B 15.80                      23 RV-201-151-41   ISI-RBB01 SHT. 1 RV BMI PENETRATION 41                                                         VE     N-722-1  B 15.80                      23 RV-201 -151-42  ISI-RBB01 SHlT. 1 RV BMI PENETRATION 42                                                         VE     N-722-1  B 15.80                      23 RV-201-151-43   ISI-RBB01 SilT. I RY BMI PENETRATION 43                                                         VE     N-722-1  B 15.80,                     23 RV-201-151-44   ISI-RBB0I SHT. I RV BMI PENETRATION 44                                                         VE     N-722-1  B 15.80                      23 RV-201 -15 1-45 ISI-RBB01 SHlT. 1 RV BMI PENETRATION 45                                                         VE     N-722-1  B 15.80                      23 RV-201-151--46  ISI-RBB01 SHT. 1 RV BMI PENETRATION 46                                                         VE     N-722-1  B 15.80                      23 RV-201-1 51--47 ISI-RBB01 SHlT. 1 RY BMI PENETRATION 47                                                         VE     N-722-1  B 15.80                      23 RV-201-151-48   ISI-RBB01 SHlT. 1 RV BMI PENETRATION 48                                                         VE     N-722-1  B 15.80                      23 RV-201-151-49   ISI-RBB01 SHlT. 1 RV BMI PENETRATION 49                                                         VE     N-722-I  B 15.80                      23 RV-201-151-50   ISI-RBB01 SHT. 1 RV BMI PENETRATION 50                                                         VE     N-722-I  B 15.80                      23 RV-201-151-51   ISI-RBBO1 SHT. 1 RV BMI PENETRATION 51                                                         VE     N-722-1  B 15.80                      23 RV-201-151-52   ISI-RBB01 SHT. 1 RV BMI PENETRATION 52                                                        YE      N-722-1  B 15.80                      23 RY-201-151-53   ISI-RBB01 SHT. 1 RV BMI PENETRATION 53                                                        YE      N-722-1  B15.80                       23 RV-20 I-151-54  ISI-RBB01 SHT. I RV BMI PENETRATION 54                                                        YE      N-722-1  B 15.80                      23 RV-201-151-55   ISI-RBB01 SilT. 1 RV BMI PENETRATION 55                                                         VE     N-722-1  B 15.80                      23 RV-201-151-56   ISI-RBB0 1 SilT. 1 RV BMI PENETRATION 56                                                         VE     N-722-1  B 15.80                      23 RV-201-151-57   ISI-RBBO1 SHT. 1 RY BMI PENETRATION 57                                                         VE     N-722-1I B 15.80                      23 RV-201 -I51-58  ISI-RBB01 SHT. 1 RY BMI PENETRATION 58                                                         VE     N-722-1  BI15.80                      23 RV-30 1-121-A    ISI-RBB01 SHT. 1 LOOP #1 RPY OUTLET    NOZZLE  TO SAFE-END                 29       2.92       VE     N-722-1  B 15.90                      24 RY-301 -121-B    ISI-RBB01 SHT. I LOOP #2 RPY OUTLET    NOZZLE  TO SAFE-END                 29       2.92       VE     N-722-1  B15.90                       24 RV-30 1-12 1-C   ISI-RBB0 1 SHlT. 1 LOOP #3 RPV OUTLET    NOZZLE  TO SAFE-END                 29       2.92       VE     N-722-1  B 15.90                      24 RV-301-121-D     ISI-RBB01 SHLT. I LOOP #4 RPY OUTLET    NOZZLE  TO SAFE-END                 29       2.92       VE     N-722-1  B 15.90                      24 RV-302-12 1-A                                                                                 27.5     2.79      YE      N-722-1  B15.95                       25 ISI-RBB01 SilT. 1  SAFE-END TO LOOP #1 RPV INLET NOZZLE RV-302-121 -D    IS1-RBB01 SHlT. 1  SAFE-END TO LOOP #4 RPV INLET NOZZLE                      27.5     2.79       VE     N-722-1  B15.95                       25 WCRE-30                                                     4.1.4 Reactor Coolant System (BB)                                                            Revision 0 Page 25 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2
[Period 2 Examinations
[System: BB]
Relief Request or Component Name    Drawing Number     Component Description                                     Size     Thickness NDE Method Category Item     Cal Block         Notes BB-0 I-S 102-TW-T BB-01-01           LOOP  #1 NARROW   RANGE  THERMO WELL,   TOP                                      VE     N-722-I  B 15.200                     26 BB-01 -S 102-TW-I BB-01-01           LOOP  #1 NARROW   RANGE  TIHERMO WELL,  INSIDE                                   VE     N-722-1  B 15.200                     26 BB-0 1-S 102-TW-O BB-01-01           LOOP  #1INARROW   RANGE  THERMO WELL,   OUTSIDE                                  VE     N-722-1  B15.200                      26 BB-01 -S202-TW-T  BB-02-01           LOOP  #2 NARROW   RANGE  TIHERMO WELL,  TOP                                      VE     N-722-1  B15.200                      26 BB-01 -S202-TW-I  BB-02-01           LOOP  #2 NARROW   RANGE  THERMO WELL,   INSIDE                                   VE     N-722-1  B 15.200                     26 BB-0 1-S202-TW-O  BB-02-01           LOOP  #2 NARROW   RANGE  THERMO WELL,   OUTSIDE                                  VE     N-722-1  B 15.200                     26 BB-01l-S302-TW-T  BB-03-01           LOOP  #3 NARROW   RANGE  THERMO WELL,   TOP                                      VE     N-722-1  B 15.200                     26 BB-0 1-S302-TW-I  BB-03-01           LOOP  #3 NARROW   RANGE  THERMOWELL,    INSIDE                                   YE     N-722-1  B 15.200                     26 BB-01-$302-TW-O   BB-03-01           LOOP  #3 NARROW   RANGE  THERMOWELL,    OUTSIDE                                  YE     N-722-1  B 15.200                     26 BB-01-S402-TW-T   BB-04-01           LOOP  #4 NARROW   RANGE  TI{ERMOWELL,   TOP                                      VE     N-722-1  B 15.200                     26 BB-01 -S402-TW-I  BB-04-01           LOOP  #4 NARROW   RANGE  THERMO WELL,   INSIDE                                   YE     N-722-1  B 15.200                     26 BB-0 I-S402-TW-O  BB-04-01           LOOP  #4 NARROW   RANGE  THERMO WELL,   OUTSIDE                                  YE     N-722-1  B 15.200                     26 BB-0l-S 101-TW-T  BB-01-01           LOOP #1 NARROW RANGE THERMO WELL, TOP                                            VE     N-722-1  B 15.205                     25 BB-01-S401-TW-T   BB-04-01           LOOP #4 NARROW RANGE THERMOWELL, TOP                                             VE     N-722-1  B 15.205                     25 HB-24-W502        BB-06-0 1          2' ELBOW TO2" PIPE                                              2     0.344      UT     MRP-146  DH           156             27 HB-24-W512        BB-06-0 1          2" ELBOW TO2" PIPE                                              2     0.344      UT     MRP-146  DH           156             27 BG-23-W596A       BG-03-23           2" ELBOW TO2" PIPE                                              2     0.344      UT     MRP-146  DH           156             27 BG-21-F027A       BG-01-21           3' PIPE TO 3" NOZZLE ON BB-56-BCA-27 1/2"                       3     0.438      UT     MRP-146  UH/H         112             27 RV-301-121-A      ISI-RBB01 SHT. 1   LOOP # 1 RPV OUTLET NOZZLE TO SAFE-END                    29   2.92            UT/YE    N-770-1  A-2          179             28 RV-301-121-B      ISI-RBB01 SHT. 1   LOOP #2 RPV OUTLET NOZZLE TO SAFE-END                     29   2.92            UT/VE    N-770-1  A-2          179             28 RV-301-121-C      ISI-RBB01 S1LIT. I LOOP #3 RPV OUTLET NOZZLE TO SAFE-END                     29   2.92            UT/YE    N-770-1  A-2          179             28 RV-301-121-D      ISI-RBB01 SHT. 1   LOOP #4 RPV OUTLET NOZZLE TO SAFE-END                     29   2.92            UT/YE    N-770-1  A-2          179             28 RV-302-12 1-A     ISI-RBB01 SHT. I   SAFE-END TO LOOP #1 RPV INLET NOZZLE                      27.5         2.79      UT     N-770-1  B            179                28, RV-302-12 1-B     ISI-RBB01 SHT. 1   SAFE-END TO LOOP #2 RPV INLET NOZZLE                      27.5         2.79      UT     N-770-1  B            179                28, RV-302-12 1-C     ISI-RBB01 SHT. 1   SAFE-END TO LOOP #3 RPV INLET NOZZLE                      27.5         2.79      UT     N-770-1  B            179                28, RV-302-121-D      ISI-RBB01 SHT. 1   SAFE-END TO LOOP #4 RPV INLET NOZZLE                      27.5         2.79      UT     N-770-1  B            179                28, WCRE-30                                                     4.1.4 Reactor Coolant System (BB)                                                                Revision 0 Page 26 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BB-3 lsystem: BB Relief Request or Component Name Drawing Number    Component Description                                Size Thickness  NDE Method Category Item   Cal Block          Notes RV-101-171     ISI-RBB01 SHT. I  RV CIRCUMFERENTIAL SHELL WELD                        NA        9.63      UT     B-A      BI~ll      176 RV-103-121     ISI-RBB0O1 SHT. 1 RV CIRCUMFERENTIAL SHELL WELD                        NA        9.63      UT     B-A      BI.I 1   175,176 RV-101-122A    1SI-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      Bl.12      175 RV-101-122C    ISI-RBB01 SET. I  RV LONGITUDINAL SHELL WELD                           NA        11.75     UT     B-A      B1.12      175 RV-101-124A    ISI-RBB0 1 SET. 1 RV LONGITUDINAL SHELL WELD                          "NA        9.63      UT     B-A      Bl.12      176 RV-101-124B    ISI-RBB0 1 SET. I RV LONGITUDINAL SHELL WELD                           NA        9.63      UT     B-A      BI1.12     176 RV-101-124C    ISI-RBB01 SET. 1  RV LONGITUDINAL SHELL WELD                           NA        9.63      UT     B-A      Bl1.12     176 RV-101-142A    ISI-RBB01 SHT. 1  RV LONGITUDINAL SHELL WELD                           NA        9.63      UT     B-A      Bl1.12     176 RV-101-142B    ISI-RBB01 SEIT. 1 RV LONGITUDINAL SHELL WELD                           NA        9.63      UT     B-A      B1.12      176 RV-101-142C    ISI-RBB01 SHT. 1  RV LONGITUDINAL SHELL WELD                           NA        9.63      UT     B-A      B1.12      176 CH-103-101     ISI-RBB01 SHT. 1  RV CLOSURE HEAD CIRCUMFERENTIAL WELD                 NA        8.25      UT     B-A      B1.21      177 RV-10 1-14 1   ISI-RBB01 SET. 1  RV LOWER HEAD TO SHELL WELD                          NA        6.38      UT     B-A      B1.21   176, 177 RV-102-151     ISI-RBB01 SET. 1  RV LOWER HEAD TO DOLLAR PLATE WELD                   NA        6.38      UT     B-A      B 1.21     177 CH-101-104-D   ISI-RBB01 SHT. 1  RV CLOSURE HEAD MERIDIONAL WELD                      NA        8.25      UT     B-A      B 1.22     177 RV-101-1 54A   ISI-RBB01 SHT. 1  RV LOWER HEAD MERIDIONAL WELD                        NA        6.38      UT     B-A      B 1.22     177 RV-101-154B    ISI-RBB01 SHT. 1  RV LOWER HEAD MERIDIONAL WELD                        NA        6.38      UT     B-A      B1.22      177 RV-101-154C    IS1-RBB01 SET. 1  RV LOWER HEAD MERIDIONAL WELD                        NA        6.38      UT     B-A      B 1.22     177 RV-101-154D    ISI-REBB1 SHT. 1  RV LOWER HEAD MERIDIONAL WELD                        NA        6.38      UT     B-A      B1.22      177 RV-I01-121     ISI-RBB01 SET. 1  RV FLANGE TO VESSEL WELD                             NA        11.75     UT     B-A      B 1.30     178 CH-101-101     ISI-RBB01 SHT. 1  RV CLOSURE HEAD TO FLANGE WELD                       NA        8.25    UT/MT    B-A      B1.40      176 WCRE-30                                                4.1.4 Reactor Coolant System (BB)                                                        Revision 0 Page 27 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3 Ieod3Examinations Relief Requesteor Cal Block           Notes Component Name    Drawing Number     Component Description                                    Size Thickness    NDE Method Category Item TBB03-SEAM-I-W    ISI-TBB03 SHT. 1   SHELL TO BOTTOM HEAD LONGITUDINAL WELD                   NA        3.75        UT     B-B      B2.12       101 EBB01ID-SEAM- 1-W ISI-EBB01D SHT. 1 BOTTOM HEAD TO TUBESHEET                                  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-105-12 1-B     ISI-RBB01 SI-IT. 1 INLET NOZZLE C TO VESSEL WELD                            NA         1 1.75     UT     B-D      B3.90     175, 178 RV-105-121-C      ISI-RBB01 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. 1   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-I    B-D      B3. 100 RV-105-121-B-IR   ISI-RBB01 SHT. 1   INLET NOZZLE C INNER RADIUS AND BORE                                          VT-I    B-D      B3.100 RV-105-121-C-IR   ISI-RBB01 SHT. 1   INLET NOZZLE F INNER RADIUS AND BORE                                          VT-I    B-D      B3. 100 RV- 105-121-D-IR  ISI-RBB01 SHT. I   INLET NOZZLE G INNER RADIUS AND BORE                                          VT-I    B-D      B3. 100 RV- 107-121-A     ISI-RBB01 SHT. I   OUTLET NOZZLE A TO VESSEL WELD                           NA         1 1.75     UT     B-D      B3.90     175, 178 RV-107-12 1-B     IS1-RBB01 SHT. 1   OUTLET NOZZLE D TO VESSEL WELD                           NA         11.75      UT     B-D      B3.90     175, 178 RV-107-12 1-C     ISI-RBB01 SI-T. 1  OUTLET NOZZLE E TO VESSEL WELD                           NA         1 1.75     UT     B-D      B3.90     175, 178 RV-107-121-D      ISI-RBB01 SHT. 1   OUTLET NOZZLE H TO VESSEL WELD                           NA         11.75      UT     B-D      B3.90     175, 178 RV-107-121-A-IR   ISI-RBB01 SHT. I   OUTLET NOZZLE A INNER RADIUS AND BORE                                         VT-1    B-D      B3. 100 RV-107-121-B-IR   ISI-RBB01 SI-T. I  OUTLET NOZZLE D INNER RADIUS AND BORE                                         VT-I    B-D      B3. 100 RV-107-121-C-IR. ISI-RBB01 SHT. 1   OUTLET NOZZLE C INNER RADIUS AND BORE                                         VT-i    B-D      B3.100 RV-107-121-D-IR   ISI-RBB01 SHT. 1   OUTLET NOZZLE D INNER RADIUS AND BORE                                         VT-i    B-D      B3. 100 TBB03-10A-W       ISI-TBB03 SHT. 1   SURGE NOZZLE TO BOTTOM HEAD WELD                         NA         2.55       UIT    B-D      B3.1 10     101 TBB03-10C-W       ]SI-TBB03 SHT. 1   SPRAY NOZZLE C TO TOP HEAD WELD                          NA         1.90       UT     B-D      B3.110      101 TBB03-10A-IR      ISI-TBB03 SHT. I   SURGE NOZZLE INNER RADIUS                                NA         2.55       UT     B-D      B3.120      101                  14 4.1.4 Reactor Coolant System (BB)                                                              Revision 0 WCRE-30 Page 28 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3 I~rod3Examin~ations Relief Request or Component Name Drawing Number     Component Description                                  Size Thickness  NDE Method Category Item    Cal Block         Notes TBB303-10C-IR  ISI-TBB03 SHT. 1   SPRAY NOZZLE C INNER. RADIUS                          NA          1.90     UT     B-D      B3. 120     101                14 EBII01A-1A-IR  ISI-EBB01A SHT. 1 PRIMARY INLET NOZZLE INNER RADIUS                      NA         5.00      UT     B-D      B3.140      104                14 EBII01A-1B-IR  ISI-EBB01A SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                     NA         5.00      UIT    B-D      B3.140      104                14 EB}301A-1A-IR  ISI-EBB01A SHT. 1 PRIMARY INLET NOZZLE INNER RADIUS                      NA         5.00     VT-i    B-D      B3. 140 EBII01A-1B-IR  ISI-EBB01A SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                     NA         5.00     VT-1    B-D      B3. 140 EBII01B-IA-IR  ISI-EBB0iB SHT. 1 PRIMARY INLET NOZZLE INNER RADIUS                      NA         5.00     VT-1    B-D      B3. 140 EBII01B-1B-IR  ISI-EBB01B SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                     NA         5.00     VT-I    B-D      B3. 140 EBII01C-1A-IR  ISI-EBB01C SHT. 1 PRIMARY INLET NOZZLE INNER RADIUS                      NA         5.00     VT-I    B-D      B3. 140 EBIB01C-1B-IR  ISI-EBB01C SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                     NA         5.00     VT-I    B-D      B3. 140 EBI301D-IA-IR  ISI-EBB01D SHT. 1 PRIMARY INLET NOZZLE INNER RADIUS                      NA         5.00     VT-I    B-D      B3. 140 EBt301D-iB-IR  ISI-EBB01D SHlT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                    NA         5.00     VT-i    B-D      B3. 140 CH-NUT-01      ISI-RBB01 SHlT. 1  REACTOR VESSEL NUT I                                                      VT-1    B-G-1    B6.10 CH-NUT-02      ISI-RBB0 1 SHT. 1  REACTOR VESSEL NUT 2                                                      VT-1    B-G-1    B6.10 CH-NUT-03      ISI-RBBO1 SHlT. 1  REACTOR VESSEL NUT 3                                                      VT-I    B-G-I    B6.10 CH-NUT-04      ISI-RBB01 SHlT. I  REACTOR VESSEL NUT 4                                                      VT-i    B-G-I    B6.10 CH-NUT-05      ISI-RBB01 SHlT. I  REACTOR VESSEL NUT 5                                                      VT-I    B-G-1    B6.10 CH-NUT-06      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 6                                                      VT-1    B-G-1    B6.10 CH-NUT-07      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 7                                                      VT-I    B-C-I    B6.10 CU-NUT-08      ISI-RBB0OI SilT. I REACTOR VESSEL NUT 8                                                      VT-I    B-C-I    B6.10 CH-NUJT-09     ISI-RBB01 SilT. 1  REACTOR VESSEL NUT 9                                                      VT-i    B-G-i    B6.10 CH-NUT- 10     ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 10                                                     VT-1    B-G-1    B6.10 WCRE-30                                                  4.1.4 Reactor Coolant System (BB)                                                        Revision 0 Page 29 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3
[~eio 3Examinations Relief Request or Component Name Drawing Number                                                            Size Thickness NDE Method Category Item   Cal Block         Notes Component Description CH-NUT-1 11    ISI-RBB0 1 SHT. I  REACTOR VESSEL NUT 11                                                    VT-i    B-G-1    B6.10 CH-NUJT-12     ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 12                                                    VT-i    B-G-1    B6.10 CH-NUT-13      ISI-RBBOL SHT. 1   REACTOR VESSEL NUT 13                                                    VT-i    B-U-i    B6.10 CH-NUT-14      ISI-RBB0I SHT. 1   REACTOR VESSEL NUT 14                                                    VT-I    B-G-1    B6.10 CH-NUT-I 5     ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 15                                                    VT-I    B-G-1    B6.10 CH-NUT-i6      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 16                                                    VT-i    B-U-i    56.10 C H-NULT- 17   ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 17                                                    VT-i    B-G-I    56.10 CH-NUT-1 8     ISI-RBB0 1 SH-T. 1 REACTOR VESSEL NUT 18                                                    VT-i    B-G-1    56.10 CH-NUT- 19     ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 19                                                    VT-i    B-G-I    B6. 10 CH-NUT-20      ISI-RBB0 1 SHT. I  REACTOR VESSEL NUT 20                                                    VT-I    B-G-I    56.10 CH-NUT-21      ISI-RBB01 SI-T. I  REACTOR VESSEL NUT 21                                                    VT-1    B-U-I    56.10 CH-NUT-22      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 22                                                    VT-I    B-G-i    B6.10 CH-NUT-23      ISI-RBB0 1 SHT. 1  REACTOR VESSEL NUT 23                                                    VT-I    B-G-I    B6.10 CH-NUT-24      ISI-RBB0 1 SHT. 1  REACTOR VESSEL NUT 24                                                    VT-i    B-G-l    56.10 CH-NUT-25      ISI-RBB01 SilT. I  REACTOR VESSEL NUT 25                                                    VT-i    B-U-I    B6.10 CH-NUTr-26     ISI-RBB01 SH-T. 1  REACTOR VESSEL NUT 26                                                    VT-i    B-U-i    B6.10 CH-NUT-27      ISI-RBB0 1 SHT. I  REACTOR VESSEL NUT 27                                                    VT-i    B-U-i    56.10 CH-NUT-28      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 28                                                    VT-i    B-U-i    56.10 CH-NUT-29      ISI-RBB0 1 SilT. 1 REACTOR VESSEL NUT 29                                                    VT-i    B-U-I    B6.10 CH-NUT-30      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 30                                                    VT-i    B-U-I    56.10 CH-NUT-3 I     ISI-RBB01 SilT. I  REACTOR VESSEL NUT 31                                                    VT-i    B-U-i    B6. 10 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                       Revision 0 Page 30 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BB-3 F~rod3Examinations ]
[System: BBj Relief Request or Component Name                                                                         Size Thickness NDE Method Category  Item  Cai Block         Notes Drawing Number     Component Description CH-NUT-32      IS1-RBB01 SHT. 1   REACTOR VESSEL NUT 32                                                  VT-I    B-U-i    B6.10 CH-NUT-33      ISI-RBB01 SHT. I   REACTOR VESSEL NUT 33                                                  VT-i    B-G-1    B6.10 CH-NUT-34      ISI-RBB01 SHT. I   REACTOR VESSEL NUT 34                                                  VT-i    B-G-i    B6.10 CH-NUT-35      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 35                                                  VT-i    B-G-1    B6.10 CH-NUT-36      ISI-RBB01 SHT. I   REACTOR VESSEL NUT 36                                                  VT-I    B-U-I    B6.10 CE-NUT-37      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 37                                                  VT-i    B-U-i    B6.10 CH-NUT-38      ISI-RBB01 SET. 1   REACTOR VESSEL NUT 38                                                  VT-I    B-G-i    B6.10 CH-NUT-39      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 39                                                  VT-i    B-U-i    B6.10 CH-NUT-40      ISI-RBB0I SET. 1   REACTOR VESSEL NUT 40                                                  VT-I    B-G-i    B6.1i0 CH-NUT--41     ISI-RBB01 SET. 1   REACTOR VESSEL NUT 41                                                  VT-i    B-G-i    B6. 10 CH-NUT-42      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 42                                                  VT-i    B-G-i    B6.10 CH-NUT--43     ISI-RBB0 1 SHlT. I REACTOR VESSEL NUT 43                                                  VT-i    B-G-i    B6.10 CH-NUT-44      ISI-RBB01 SHT. I   REACTOR VESSEL NUT 44                                                  VT-i    B-U-i    B6.10 CH-NUT-45      ISI-RBB01 SHT. I   REACTOR VESSEL NUT 45                                                  VT-i    B-U-i    B6.10 CH-NUT-46      ISI-RBB01 SilT. I  REACTOR VESSEL NUT 46                                                  VT-i    B-U-i    B6.10 CH-NUT--47     ISI-RBB01 SET. 1   REACTOR VESSEL NUT 47                                                  VT-i    B-U-i    B6.10 CH-NUT-48      ISI-RBB01 SET. 1   REACTOR VESSEL NUT 48                                                  VT-i    B-U-i    B6.10 CH-NUT--49     ISI-RBB01 SET. 1   REACTOR VESSEL NUT 49                                                  VT-i    B-U-i    B6.10 CH-NUT-50      ISI-RBB01 SET. 1   REACTOR VESSEL NUT 50                                                  VT-i    B-U-i    B6.10 CH-NUT-5 1     ISI-RBB01 SET. 1   REACTOR VESSEL NUT 51                                                  VT-i    B-U-i    B6.10 CH-NUT-52      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 52                                                  VT-i    B-U-i    B6.10 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 31 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE BB-3 Ieid3ExaminationsI
[System: BB    ]Relief                                               Request or Size  Thickness NDE Method Category Item  Cal Block    Notes Component Name Drawing Number    Component Description CH-NUT-53      ISI-RBB01 SHT. 1  REACTOR. VESSEL NUT 53                                                     VT-i    B-U-I    B6.10 CH-NUT-54      ISI-RBB01 SHT. 1  REACTOR VESSEL NUT 54                                                      VT-i    B-G-1    B6.10 CH-STUD-01     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 1                                   NA         NA       UT     B-G-1    B6.20     195 CH-STUD-02     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 2                                   NA          NA      UIT    B-U-i    B6.20     195 CH-STUD-03     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 3                                   NA          NA      UT     B-U-i    B6.20     195 CH-STUD-04     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 4                                   NA          NA      UT     B-U-i    B6.20     195 CH-STUD-05     ISI-RBBOI SHT. 1  REACTOR. VESSEL STUD 5                                  NA          NA      UT     B-G-i    B6.20     195 CH-STUD-06     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 6                                   NA          NA      UT     B-U-I    B6.20     195 CH-STUD-07     ISI-RBB01 SHT. I  REACTOR VESSEL STUD 7                                   NA          NA      UT     B-G-I    B6.20     195 CH-STUD-08     ISI-RBB01 SHT. I  REACTOR. VESSEL STUD 8                                  NA          NA      UT     B-U-I    B6.20     195 CH-STUD-09     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 9                                   NA         NA       UT     B-U-i    B6.20     195 CH-STUD-10     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 10                                  NA          NA      UIT    B-U-I    B6.20     195 CH-STUD-1 1    ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 11                                  NA          NA      UT     B-U-i    B6.20     195 CH-STUD-12     ISI-RBBO1 SHT. I  REACTOR VESSEL STUD 12                                  NA          NA      UT     B-U-i    B6.20     195 CH-STUD-13     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 13                                  NA          NA      UT1    B-U-i    B6.20     195 CH-STUD-14     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 14                                  NA          NA      UT     B-U-i    B6.20     195 CH-STUDJ-15    ISI-RBB01 SHT. I  REACTOR VESSEL STUD 15                                  NA          NA      UT     B-U-i    B6.20     195 CH-STUD- 16    ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 16                                  NA          NA      UT     B-U-i    B6.20     195 CI--STUD- 17   ISI-RBB0 1 SHT. 1 REACTOR VESSEL STUD 17                                  NA          NA      UT     B-U-I    B6.20     195 CH-STUD- 18    ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 18                                  NA          NA      UT     B-U-i    B6.20     195 CH-STUD- 19    ISI-RBB01 SHT. I  REACTOR VESSEL STUD 19                                  NA          NA      UT1    B-U-i    B6.20     195 WCRE-30                                                 . 1.4 Reactor Coolant System (BB)                                                   Revision 0 Page 32 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3 Ieod3ExaminationsI Relief Request or Size Thickness NDE Method Category Item  Cal Block         Notes Component Name Drawing Number    Component Description CH-STtJD-20    ISI-RBB01 SHT.1   REACTOR VESSEL STUD 20                                 NA        NA       UT     B-G-I    B6.20     195 CH-STUD-21     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 21                                 NA        NA       UT     B-U-t    B6.20     195 CH-STUD-22     ISI-RBB01 SEIT. 1 REACTOR VESSEL STUD 22                                 NA        NA       UT     B-G-t1   B6.20     195 CH-STUD-23     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 23                                 NA        NA       UT     B-G-1    B6.20     195 CH-STUD-24     ISI-RBBO01 SET. 1 REACTOR VESSEL STUD 24                                                                              195 NA        NA       UT     B-U-I    B6.20 CH-STUD-25     ISI-RBBO01 SET. 1 REACTOR VESSEL STUD 25                                 NA        NA       UT     B-U-I1   B6.20     195 CH-STUD-26     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 26                                 NA        NA       UT     B-G-t1   B6.20     195 CH-STUD-27     ISI-RBB01 SET. 1  REACTOR VESSEL STUD 27                                 NA        NA       UT     B-U-i    B6.20     195 CH-STUD-28     ISI-RBB01 SET. 1  REACTOR VESSEL STUD 28                                 NA        NA       UT     B-U-i    B6.20     195 CH-STUD-29     ISI-RBB01 SEIT. 1 REACTOR VESSEL STUD 29                                 NA        NA       UT     B-U-i    B6.20     195 CH-STUD-30     ISI-RBB01 SET. 1  REACTOR VESSEL STUD 30                                 NA        NA       liT    B-U-I    B6.20     195 CH-STUD-31I    ISI-RBB01 SET. 1  REACTOR VESSEL STUD 31                                 NA        NA       UT     B-G-t1 B6.20     195 CH-STUD-32     1SI-RBB01 SET. 1  REACTOR VESSEL STUD 32                                 NA        NA       UT     B-U-i1   B6.20     195 CH-STUD-33     ISI-RBB01 SET. 1  REACTOR VESSEL STUD 33                                 NA        NA       UT     B-U-i1   B6.20     195 CH-STUD-34     ISI-RBBOt SHTr. 1 REACTOR VESSEL STUD 34                                 NA        NA       UT     B-U-I    B6.20     195 CH-STUIJ-35    ISI-RBB01 SET. 1  REACTOR VESSEL STUD 35                                 NA        NA       UT     B-U-I1   B6.20     195 CH-STUD-36     ISI-RBB01 SET. 1  REACTOR VESSEL STUD 36                                 NA        NA       UT     B-U-i    B6.20     195 CH-STUD-37     ISI-RBBO1 SEIT. 1 REACTOR VESSEL STUD 37                                 NA        NA       UT     B-U-i1   B6.20     195 CH-STUD-38     ISI-RBB01 SELT. 1 REACTOR VESSEL STUD 38                                 NA        NA       UT     B-U- I   B6.20     195 CHI-STUD-39                                                                             NA        NA       UT     B-U-i    B6.20     195 ISI-RBB0I SET. 1  REACTOR VESSEL STUD 39 CH-STUD-40     ISI-RBB01 SELT. 1 REACTOR VESSEL STUD 40                                 NA        NA       UT     "B-U-i   B6.20     195 WCRE-30                                                4.1.4 Reactor Coolant System (BB)                                                       Revision 0 Page 33 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE    BB-3 I~dd3Examinations
[System: BB Relief Request or Size Thickness NDE Method Category Item  Cal Block          Notes Component Name Drawing Number    Component Description CH-STUD-41     ISI-RHB01 SHlT. 1 REACTOR VESSEL STUD 41                                   NA         NA      UIT    B-G-I    B6.20     195 CH-STUD-42     ISI-RBB01 SHlT. 1 REACTOR VESSEL STUD 42                                   NA         NA      UT     B-G-I    B6.20     i195 CH-STUD-43     ISI-RBB01 SHT. I  REACTOR VESSEL STUD 43                                   NA         NA      UT     B-G-i    B6.20     195 CH-STUD-44     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 44                                                                                195 NA         NA      UIT    B-U-I    B6.20 CH-STUD-45     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 45                                   NA         NA      UIT    B-G-I    B6.20     195 CH-STUD-46     ISI-RBB0i SHlT. 1 REACTOR VESSEL STUD 46                                   NA         NA      UT     B-G-I    B6.20     195 CH-STUD-.47    ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 47                                                                                195 NA         NA      UT     B-G-i    B6.20 CH-STUD-48     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 48                                   NA         NA      UT              B6.20     195 B-U-I CH-STUD-49     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 49                                   NA         NA      UIT    B-U-i    B6.20     195 CH-STUD-50     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 50                                   NA         NA      UT     B-U-i    B6.20     195 CH-STUD-51I    ISI-RBB0i SHT. I  REACTOR VESSEL STUD 51                                   NA         NA      UIT    B-U-1    B6.20     195 CH-STUD-52     ISI-RBB01 SHT. I  REACTOR VESSEL STUD 52                                   NA         NA      UIT    B-U-i    B6.20     195 CH-STUD-53     ISI-RBB01 SHlT. 1 REACTOR VESSEL STUD 53                                   NA         NA      UT     B-U-i    B6.20     195 CH-STUD-54     ISI-REBB1 SHT. 1  REACTOR VESSEL STUD 54                                   NA         NA      UT     B-U-I    B6.20     195 RV-LIG-01      ISI-RBB01 SHlT. 1 REACTOR VESSEL THREAD IN FLANGE 1                        NA         NA      UT     B-U-I    B6.40     140 RV-LIG-02      ISI-RBB01 SHT. 1  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                        140 B-U-I    B6.40 RV-LIG-04      ISI-RBB01 SHT. I  REACTOR VESSEL THREAD IN FLANGE 4                                                           B6.40     140 NA         NA      UT     B-U-I RV-LIG-05      ISI-RBB01 SHlT. I REACTOR VESSEL THREAD IN FLANGES5                        NA         NA      UT     B-U-I    B6.40     140 RV-LIG-06      ISI-RBB01 SHT. 1  REACTOR VESSEL THREAD IN FLANGE 6                        NA         NA      UT              B6.40     140 RV-LIG-07      IS1-RBB01 SilT. 1 REACTOR VESSEL THREAD IN FLANGE 7                        NA         NA      UT     B-G-I    B6.40      140 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                         Revision 0 Page 34 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3 IFrod3Examintions Relief Request or Component Name Drawing Number     Component Description                                Size Thickness NDE Method Category Item  Cal Block         Notes RV-LIG-08      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD 1N FLANGE 8                    NA        NA       UT     B-G-I    B6.40     140 RV-LIG-09      ISI-RBB0 1SHT. 1   REACTOR VESSEL THREAD IN FLANGE 9                    NA        NA       UT     B-G-1    B6.40     140 RV-LIG- 10     ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 10                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-I I     ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD TN FLANGE 11I                  NA        NA       UT     B-G-1    B6.40     140 RV-LIG- 12     ISI-RBB01 SHT. 1   REACTOR VESSEL TH-READ IN FLANGE 12                  NA        NA       UT     B-G-I    B6.40     140 RV-LIG-1 3     ISL-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 13                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG- 14     ISI-RBB0l SI-T. 1  REACTOR VESSEL THREAD IN FLANGE 14                   NA        NA       UT     B-G-I    B6.40     140 RV-LIG- 15     ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 15                   NA        NA       UT     B-G-I    B6.40     140 RV-LIG-1 6     ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 16                   NA        NA       UT     B-G-I    B6.40     140 RV-LIG- 17     ISI-RBB0I SHT. 1   REACTOR VESSEL THREAD IN FLANGE 17                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-1 8     ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 18                   NA        NA       UiT    B-G-1    B6.40     140 RV-LIG-1 9     ISI-RBB01 SHT. I   REACTOR VESSEL THREAD IN FLANGE 19                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-20      ISI-RBB01 SHIT. I  REACTOR VESSEL THREAD IN FLANGE 20                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-21      ISI-REBB1 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 21                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-22      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 22                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-23      ISI-RBB0 1 SHT. 1  REACTOR VESSEL THREAD IN FLANGE 23                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-24      ISI-RBB0 1 SHT. 1  REACTOR VESSEL THREAD IN FLANGE 24                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-25      ISI-RBB0 1 SHT. 1  REACTOR VESSEL THREAD IN FLANGE 25                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-26      ISI-RBB0 1 SHIT. 1 REACTOR VESSEL THREAD IN FLANGE 26                   NA        NA       UT     B-G-1    B640      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 SIHT. 1  REACTOR VESSEL THREAD TN FLANGE 28                   NA        NA       UT     B-G-1    B6.40     140 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                    Revision 0 Page 35 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE BB-3 Peid 3Examinations Relief Request or Component Name                                                                          Size Thickness NDE Method Category Item  Cal Block         Notes Drawing Number     Component Description RV-LIG-29      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 29                    NA        NA       UIT    B-G- 1   B6.40     140 RV-LIG-30      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 30                    NA        NA       UT     B-G- 1   B6.40     140 RV-LIG-31      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 31                    NA        NA       UT     B-G-I    B6.40     140 RV-LIG-32      ISI-RBB01 SHLT. 1  REACTOR VESSEL THREAD IN FLANGE 32                                                                 140 NA        NA       UT     B-U-i    B6.4u RV-LIG-33      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 33                    NA        NA       UT     B-U-i    86.40     140 RV-LIG-34      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 34                    NA        NA       UT     B-G-1    86.40     140 RV-LIG-35      ISI-RBB01 SHT. I   REACTOR VESSEL THREAD IN FLANGE 35                    NA        NA       UT     B-G-1    B6.40     140 RV-LIG-36      ISI-RBBO1 SHT. I   REACTOR VESSEL THREAD IN FLANGE 36                    NA        NA       UT     B-G-i    B6.40 140 RV-LIG-37      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 37                    NA        NA       UT     B-G-I    B6.40     140 RV-LIG-38      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 38                    NA        NA       UT     B-G-1    B6.40 140 RV-LIG-39      ISI-RBB01 SILT. 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-U-i    86.40     140 RV-LIG-41      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 41                    NA        NA       UT     B-G-I    B6.40     140 RV-LIG-42      ISI-RBB01 SHT. I   REACTOR VESSEL THREAD IN FLANGE 42                    NA        NA       UIT    B-U-i    86.40     140 RV-LIG-43      ISI-R.BBO1 SHlT. I REACTOR VESSEL THREAD IN FLANGE 43                    NA        NA       UT     B-U-i    86.40     140 RV-LIG-44      ISI-RBB01 SHLT. 1  REACTOR VESSEL THREAD IN FLANGE 44                    NA        NA       UT     B-U-I    B6.40     140 RV-LiG.-45     ISI-RBB01 SilT. 1  REACTOR VESSEL THREAD IN FLANGE 45                                                       B6.40     140 NA         NA      UT     B-U-I RV-LIG.-46     ISI-RBB01 SLITr.1  REACTOR VESSEL THREAD IN FLANGE 46                    NA         NA      UT     B-U-i1   86.40     140 RV-LIG-47      ISI-RBB01 SILT. 1  REACTOR VESSEL THREAD IN FLANGE 47                    NA         NA      UT     B-U-I    B6.40     140 RV-LIG-48      ISI-RBB01 SHlT. 1  REACTOR VESSEL THREAD IN FLANGE 48                    NA         NA      UiT    B-U-i    86.40     140 RV-LIG-49      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 49                    NA        NA       UT     B-U-i    86.40     140 WCRE-30                                                  4.1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 36 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3
[Peiod 3 xaminations ]
[System: BB Relief Request or Component Name                                                                          Size Thickness NDE Method Category Item  Cal Block         Notes Drawing Number     Component Description RV-LIG-50      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 50                    NA        NA       UT     B-G-1    B6.40     140 RV-LIG-51      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD I-N FLANGE 51                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-52      ISI-RBB0 1 SHT. 1  REACTOR VESSEL THREAD IN FLANGE 52                    NA        NA       UT     B-G-1    B6.40     140 RV-LIG-53      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 53                    NA        NA       UT     B-G-1    B6.40     140 RV-LIG-54      ISI-RBBO01 SHT. 1  REACTOR VESSEL THREAD IN FLANGE 54                    NA        NA       UT     B-G-I    B6.40     140 CH-WASI-i-01   ISI-RBB01I SHT. 1  REACTOR VESSEL WASHER AND BUSHING I                                     VT-I    B-G-1    B6.50 CH-WASH-02     ISI-RBB01 SI-T. I  REACTOR VESSEL WASHER AND BUSHING 2                                     VT-I    B-G-1    B6.50 CH-WASH-03     ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 3                                     VT-i    B-G-!    B6.50 CH-WASHI-04    ISI-RiBB01 SI-T. 1 REACTOR VESSEL WASHER AND BUSHING 4                                     VT-I    B-G-i    B6.50 CH-WASH-05     ISI-RBB0I SI-IT. 1 REACTOR VESSEL WASHER AND BUSHING 5                                     VT-1    B-G-1    B6.50 CH-WASI-i-06   ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 6                                     VT-i    B-G-1    B6.50 CH-WASH-07     ISI-RBB01 SI-T. 1  REACTOR VESSEL WASHER AND BUSHING 7                                     VT-i    B-G-1    B6.50 CH-WASH-08     ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 8                                     VT-i    B-G-1    B6.50 CH-WASH-09     ISI-RBB0i SHT. 1   REACTOR VESSEL WASHER AND BUSHING 9                                     VT-i    B-G-1    B6.50 CH-WASH-1I 0   ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 10                                    VT-i    B-G-1    B6.50 CH-WASH-1 1    ISI-RBBO01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 11                                    VT-i    B-G-1    B6.50 CH-WASH-i2     ISI-RBBOI SHT. 1   REACTOR VESSEL WASHER AND BUSHING 12                                    VT-I    B-G-I    B6.50 CH-WASI--13    ISI-RBBO1 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 13                                    VT-I    B-G-I    B6.50 CH-WASI--14    ISI-RBB01 SI-T. 1  REACTOR VESSEL WASHER AND BUSHING 14                                    VT-i    B-G-1    B6.50 CH-WASI-I 5    ISI-RBB01 SI-T. I  REACTOR VESSEL WASHER AND BUSHING 15                                    VT-I    B-G-1    B6.50 CH-WASI-I- 6   ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 16                                    VT-1    B-G-1    B6.50 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 37 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BB-3 Isystem: BB Relief Request or Thickness NDE Method          Item  Cal Block         Notes Component Name Drawing Number    Component Description                                Size                      Category CH-WASH- 17    ISI-RBB01 SI-T. 1 REACTOR VESSEL WASHER AND BUSHING 17                                   VT-I    B-G-I    B6.50 CH-WASH-1 8    ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 18                                   VT-I    B-G-I    B6.50 CH-WASH-19     ISI-RBB01 SHIT. 1 REACTOR VESSEL WASHER. AND BUSHING 19                                  VT-1    B-G-I    B6.50 CH-WASH-20     ISI-RBB01 SHT. I  REACTOR VESSEL WASHER. AND BUSHING 20                                  VT-i    B-G-1    B6.50 CH-WASH-21I    ISI-RBBO1 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 21                                   VT-1    B-G-1    B6.50 CH-WASH-22     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 22                                   VT-1    B-G-I    B6.50 CH-WASH-23     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 23                                   VT-l    B-G-1    B6.50 CH-WASH-24     ISI-RBB01 SHT. I  REACTOR VESSEL WASHER AND BUSHING 24                                   VT-i    B-G-I    B6.50 CH-WASH-25     ISI-RBBOI SHT. 1  REACTOR VESSEL WASHER AND BUSHING 25                                   VT-i    B-G-I    B6.50 CH-WASH-26     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 26                                   VT-I    B-G-I    B6.50 CH-WASH-27     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 27                                   VT-I    B-G-1    B6.50 CH-WASH-28     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 28                                   VT-I    B-G-1    B6.50 CH-WASH-29     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 29                                   VT-I    B-G-i    B6.50 CH-WASH-30     ISI-RBB01 SHT. 1  REACTOR. VESSEL WASHER. AND BUSHING 30                                 VT-1    B-G-I    B6.50 CH-WASH--31I   ISI-RBB0 1 SHT. 1 REACTOR. VESSEL WASHER AND BUSHING 31                                  VT-I    B-G-1    B6.50 CH-WASH-32     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSH{ING 32                                  VT-1    B-G-I    B6.50 CH-WASH-33     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 33                                   VT-I    B-G-1    B6.50 CH-WASH-34     ISI-RBB01 SHT. I  REACTOR VESSEL WASHER AND BUSHING 34                                   VT-I    B-G-1    B6.50 CH-WASH-35     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 35                                   VT-i    B-G-1    B6.50 CH-WASH-36     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 36                                   VT-I    B-G-1    B6.50 CH-WASH-37     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER. AND BUSHING 37                                  VT-1    B-G-I    B6.50 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                    Revision 0 Page 38 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE    BB-3 lSystem: BB]
Relief Request or Component Name        Drawing Number    Component Description                               Size Thickness NDE Method Category Item   Cal Block         Notes CH-WASH-38           ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 38                                  VT-i    B-G-I    B6.50 CH-WASH-39           ISI-RBB01 SET. 1   REACTOR VESSEL WASHER AND BUSHING 39                                  VT-I    B-G-i    B6.50 CH-WASH-40           ISI-RBB01 SET. 1   REACTOR VESSEL WASHER AND BUSHING 40                                  VT-i    B-G-i    B6.50 CH-WASH-41           ISI-RBB0i SHT. 1   REACTOR VESSEL WASHER AND BUSHING 41                                  VT-i    B-U-i    B6.50 CH-WASH--42          ISI-R.BB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 42                                  VT-i    B-U-i    B6.50 CH-WASH-43           ISI-RBB0i SEIT. 1  REACTOR VESSEL WASHER AND BUSHING 43                                  VT-i    B-U-i    B6.50 CH-WASH-44           ISI-RBB0 1 SET. 1  REACTOR VESSEL WASHER AND BUSHING 44                                  VT-i    B-U-i    B6.50 CH-WASH-45           ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 45                                  VT-i    B-U-i    B6.50 CH-WASH-46           ISI-R.BB0 1 SET. I REACTOR VESSEL WASHER AND BUSHING 46                                  VT-I    B-U-i    B6.50 CH-WASH-47           ISI-RiBB0I SHT. 1  REACTOR VESSEL WASHER AND BUSHING 47                                  VT-i    B-U-i    B6.50 CH-WASH-48           ISI-REBB0   SHT. 1 REACTOR VESSEL WASHER AND BUSHING 48                                  VT-i    B-U-i    B6.50 CH-WASH-49           ISI-RiBBO1 SHT. I  REACTOR VESSEL WASHER AND BUSHING 49                                  VT-I    B-U-i    B6.50 CH-WASH-50           ISI-RBB01 SHT. I   REACTOR VESSEL WASHER AND BUSHING 50                                  VT-i    B-U-i    B6.50 CH-WASH-51           ISI-RBBOL SET. 1   REACTOR VESSEL WASHER AND BUSHING 51                                  VT-i    B-U-i    B6.50 CH-WASH-52           ISI-RBBOI SHT. 1   REACTOR VESSEL WASHER AND BUSHING 52                                  VT-i    B-U-i    B6.50 CH-WASH-53           ISI-RBB01 SET. 1   REACTOR VESSEL WASHER AND BUSHING 53                                  VT-I    B-U-i    B6.50 CH-WASH-54           ISI-RBB01 SET. 1   REACTOR VESSEL WASHER AND BUSHING 54                                  VT-i    B-U-i    B6.50 PBB01 A-STUDS        M-712-00057        PBB01A PUMP MAIN BOLTS / STUDS (24)                 NA        NA       UT     B-U-i    B6.180 PBB01 A-FLANGE       ISI-PUMPS          PBB01A FLANGE SURFACE                                                 VT-i    B-U-i    B6.190                         4 PBB01 A-WASHERS/NUTS M-712-00057        PBB01A PUMP MAIN NUTS, BUSHINGS, WASHERS     (24)                     VT-i    B-U-I    B6.200                         5 WCRE-30                                                       WCRE-304.1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 39 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3
[Prid 3 xamiInationsI
[System: BB Relief Request or Size Thickness NDE Method          Item     Cal Block         Notes Component Name     Drawing Number    Component Description                                                            Category RV-INTERIOR        ISI-RBB01 SHT. 1  REACTOR VESSEL INTERIOR                                                  VT-3    B-N-1    B13.10 RV-CSL- 104-142-A  ISI-RBB01I SHT. 1 CORE SUPPORT LUG                                                         VT-3    B-N-2    B 13 .60 RV-CSL- 104-142-B  ISI-RBB01 SHT. 1  CORE SUPPORT LUG                                                         VT-3    B-N-2    B 13.60 RV-C SL- 104-142-C ISI-RBB01 SI-T. I CORE SUPPORT LUG                                                         VT-3    B-N-2    B 13.60 RV-CSL- 104-142-D  ISI-RBB01 SHT. 1  CORE SUPPORT LUG                                                         VT-3    B-N-2    B 13.60 RV-CSL-104-142-E   ISI-RBB01 SHT. 1  CORE SUPPORT LUG                                                         VT-3    B-N-2    B 13.60 RV-CSL- 104-142-F  ISI-RBB01 SHT. I  CORE SUPPORT LUG                                                         VT-3    B-N-2    B 13.60 RV-CORE STRUCT     ISI-RBB01 SHT. 1  REMOVABLE CORE SUPPORT STRUCTURES                                        VT-3    B-N-3    B 13.70 CH-214-1 12-B      ISI-RBB0 1 SHT. I PENETRATION 67 CRDM HOUSING WELD                                          PT     B-O      B 14.20 CH-214-1 12-E      ISI-RBB01 SHT. 1  PENETRATION 70 CRDM HOUSING WELD                                          PT     B-O      B 14.20 CH-2t4-1 12-G      ISI-RBB0 1 SHT. 1 PENETRATION 72 CRDM HOUSING WELD                                          PT     B-O      B 14.20 CH-215-1 12-B      ISI-RBB01 SHT. 1  PENETRATION 75 CRDM HOUSING WELD                                          PT     B-O      B 14.2 1 EBB01A-16-W        ISI-EBB01A SHT. 1 STEAM NOZZLE WELD                                      NA        3.95   UT/MT    C-B      C2.21        102 BB-02-H007         BB-0l-02          PIPING SUPPORT                                         3                 VT-3    F-A      FI.1 BB-02-H008         BB-01-02          PIPING SUPPORT                                         3                 VT-3    F-A      FI.1 BB-04-R014         BB-0 1-04 SILT. 1 PIPING SUPPORT                                         4                 VT-3    F-A      Fi.1 BB-04-C003         BB-01-04 SHT. 2   PIPING SUPPORT                                         4                 VT-3    F-A      FI.1 BB-04-R008         BB-01.-04 SI-T. 2 PIPING SUPPORT                                         4                 VT-3    F-A      FI.10 BB-l1l-HO01        BB-02-11I         PIPING SUPPORT                                         2                 VT-3    F-A      FI.I0 BB-0 l-R004        BB.-05-01         PIPING SUPPORT                                         14                VT-3    F-A      FI.10 WCRE-30                                                     4.1.4 Reactor Coolant System (BB)                                                         Revision 0 Page 40 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3
[System: BB Relief Request or Component Name Drawing Number    Component Description                                 Size Thickness NDE Method Category Item   Cal Block         Notes CRDMPL-SUP-5   ISI-CRDMPL        CRDM Upper Seismic Support                                              VT-3    F-A      F1.40 CRDMPL-SUP-6   ISI-CRDMPL        CRDM Upper Seismic Support                                              VT-3    F-A      FI.40 EBB01A-03 231  M-717-00002       SO A LOWER COLUMN SUPPORT                                               VT-3    F-A      F 1.40 EBB01A-04 231  M-717-00002       SG A LOWER COLUMN SUPPORT                                               VT-3    F-A      F1.40 PBB01 A-SUP-3  ISI-PUMPS         RCP A TIE ROD SUPPORT                                                   VT-3    F-A      F1.40 PBB0 1A-SUP-3A ISI-PUMPS         RCP A COLUMN SUPPORT                                                    VT-3    F-A      F 1.40 RBB-01-04      ISI-RBB01 SilT. 1 RV SUPPORT PAD 4                                                        VT-3    F-A      F 1.40                   I4R-02 TBB03-LUG-A-W  ISI-TBB03 SHT. 1  SEISMIC SUPPORT                                                         VT-3    F-A      FI.40                         11 TBB03-LUG-B-W  ISI-TBB03 SHT. I  SEISMIC SUPPORT                                                         VT-3    F-A      F1.40                         II TBB03-LUG-C-W  ISI-TBB03 SHLT. 1 SEISMIC SUPPORT                                                         VT-3    F-A      F1.40                         11 TBB03-LUG-D-W  ISI-TBB03 SI-T. I SEISMIC SUPPORT                                                         VT-3    F-A      F 1.40                        11 BB-0 1-$301-09 BB-03-01          3" NOZZLE TO 3" X 1.5' REDUCER                                           UIT    R-A      RI.1lI                    12, 13 3       0.438                                 112 BB-C01-S401-10 BB-04-01          3" NOZZLE TO 3" X 1 1/2" REDUCER                      3       0.438      UIT    R-A      RI 11      112            12, 13 BB-C01-S00 1-6 BB-05-01          14" PIPE TO 14' ELBOW                                 14       1.25      UT     R-A      RI.I11     130            12, 13 BB-C01-F 102   BB-01-C1          27 1/2' ELBOW-LOOP #1 RPV INLET SAFE-END              27.5     2.5       UIT    R-A      R1.20  SAP-07, 106            12 BB-C01-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-04-S01 1-D  BB-01-04 SI-T. I  6"X4" REDUCER TO 6" PIPE                              6       0.7 19    *UT     R-A      R1.20      117                12 BB-04-S002-E   BR-0 1-04 SHlT. 2 6"X4" EXPANDER TO 6" PIPE                             6       0.7 19     UT     R-A      R1.20      117                12 BB-C6-F001     BB-02-01          3" PIPE TO 3" NOZZLE ON C36-BCA-3 1"                  3       0.438      UT     R-A      R1.2C      112            12, 13 BB-06-PW6000   BB-02-0l          3" PIPE TO CAP (B.W.)                                 3       0.438      UT     R-A      R1.20      112                12 HB-24-W50 1    BB-06-01          2" PIPE TO 2" ELBOW                                   2       0.344      UIT    R-A      R1 .20     156                12 WCRE-30                                                   WR-04.1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 41 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3
[System: BB Relief Request or Size Thickness      NDE Method Category Item     Cal Block          Notes Component Name       Drawing Number     Component Description PBB01 A-FLYWH-EEL    ISI-PUMPS          PUMP FLYWHEEL                                        NA           NA      UT/PT/MT  AUG. 1   AUG.FW                             9 PBB01 B-FLYWHEEL     ISI-PUMPS          PUMP FLYWHEEL                                        NA           NA      UT/PT/MT  AUG. 1   AUG. FW                            9 PBB01 C-FLYWHEEL     ISI-PUMPS          PUMP FLYWHEEL                                        NA           NA      UT/PT/MT  AUG. 1   AUG.FW                             9 PBB01 D-FLYWHEEL     1SI-PUMPS          PUMP FLYWHEEL                                        NA           NA      UT/PT/MT  AUG. 1   AUG.FEW                            9 RV-30 1-121-A        ISI-RBB01 SHT. 1   LOOP #1 RPV OUTLET NOZZLE TO SAFE-END                                                                                          28 29        2.92        UT/VE    N-770-1  A-2           179 RV-30t -12 1-B       1SI-RBB01 SIHT. I  LOOP #2 RPV OUTLET NOZZLE TO SAFE-END                29        2.92        UT/VE    N-770-1  A-2           179                 28 RV-30 1-121-C        ISI-RBB01 SHT. I   LOOP #3 RPV OUTLET NOZZLE TO SAFE-END                29        2.92        UT/yE    N-770-1  A-2           179                 28 RV-301-121-D         ISI-RBB01 SHT. I   LOOP #4 RPV OUTLET NOZZLE TO SAFE-END                29        2.92        UT/VE    N-770-1  A-2           179                 28 RV-302-12 I-A        ISI-RBB0I SI-IT. 1 SAFE-END TO LOOP #1 RPV INLET NOZZLE                 27.5      2.79          UT     N-770-1  B179                             28, RV-302-121-B         IS1-RBBOI SHT. I   SAFE-END TO LOOP #2 RPV INLET NOZZLE                 27%5      2.79          UT     N-770-I  B179                             28, RV-302-121-C         ISI-RBBOI SHT. I   SAFE-END TO LOOP #3 RPV INLET NOZZLE                 27.5                                                  179                28, 2.79          UT     N-770-1  B RV-302-121-D         ISI-RBB01 SHT. I   SAFE-END TO LOOP #4 RPV INLET NOZZLE                 27.5      2.79          UT                            179                28, N-770-1  B TBB03-MWT090-WOL-DM  ISI-TBB03 SHT. 1   SURGE NOZZLE TO SAFE-END WELD OVERLAY                 14  See I, Note 21     UIT    N-770-1 DM-R    See I, Note 18 BB-01-MW7090-WOL-SS  BB-05-01           SURGE NOZZLE SAFE-END TO PIPE WELD OVERLAY            14  See I, Note 21     UT     I3R-05   SS-P    See I, Note 18 CH-107-101          ISI-RBB01 SHT. 1 RV VENT PENETRATION                                                           VE    N-729-1  B4. 10                        22 CH-1 12-201         ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    I                                                      VE    N-729-1  B4.10                         22 CH- 112-202-2       IS1-RBB01 SHT. 1 RV CRDM PENETRATION    2                                                      VE    N-729-1  84.10                         22 CH-1 112-202-3      ISI-RBB01 SHT. 1 RV CRDM PENETRATION    3                                                      VE    N-729-1  B4.10                         22 CH-1 12-202-4       ISI-RBBO1 SI-T. 1 RV CRDM PENETRATION    4                                                      VE    N-729-1  B4.10                         22 CH-1 12-202-5       ISI-RBB01 SI-T. 1 RV CRDM PENETRATION    5                                                      VE    N-729-1  B4.10                         22 CH-1 12-203-6       ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    6                                                      VE    N-729-1  B4. 10                        22 CH-1-i12-203-7      ISI-REBB0I SHT. 1 RV CRDM PENETRATION    7                                                      VE    N-729-1  B4.10                         22 Cl-i- 112-203-8     ISI-RBB01 SHT. 1 RV CRDM PENETRATION    8                                                      VE    N-729-1  B4.10                         22 CH-1 112-203-9      ISI-RBB01 SHT. 1 RV CRDM PENETRATION    9                                                      VE    N-729-1  B4.10                         22 CH-112-204-10       ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    10                                                     VE    N-729-1  B4.10                         22 CH-1 12-204-11      ISI-RBBO1 SHT. 1 RV CRDM PENETRATION     11                                                    VE    N-729-1  B4.10                         22 CH-1 12-204-12      ISI-RBBO1 SHT. I RV CRDM PENETRATION     12                                                    VE    N-729-1  B4.10                         22 CH-1 12-204-13      ISI-RBB01 SHT. I RV CRDM PENETRATION     13                                                    VE    N-729-1  B4.10                         22 CH-1 12-205-14      ISI-RBB01 SHT. 1 RV CRDM PENETRATION     14                                                    VE    N-729- I B4.10                         22 CH-1 12-205-15      ISI-RBB0 1 SHT. I RV CRDM PENETRATION     15                                                    yE    N-729-1  B4.10                         22 CH-1 12-205-16      ISI-RIBB01 SHT. I RV CRDM PENETRATION     16                                                    VE    N-729-1  B4.10                         22 WCRE-30                                                                                                                                                      Revision 0 4.1.4 Reactor Coolant System (BB)
Page 42 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE    BB-3 j~eid 3Examinations f
[System: BB Relief Request or Component Name    Drawing Number   Component Description                                 Size Thickness NDE Method Category  Item  Cal Block         Notes CH-1 12-205-17   ISI-RBB01 SHT. 1 RV CRDM PENETRATION     17                                               VE     N-729-1  B4.10                     22 CH-1 12-206-18   ISI-RBBOI SHT. 1 RV CRDM PENETRATION     18                                               VE     N-729-1I B4.10                     22 CH-i112-206-19   ISI-RBB01 SHT. 1 RV CRDM PENETRATION     19                                               VE     N-729-1  84.10                     22 CH-1 12-206-20   ISI-RBB0I SRT. 1 RV CRDM PENETRATION    20                                                VE     N-729-1  B4.10                     22 CR-I112-206-2 1  ISI-RBB01 SHT. 1 RV CRDM PENETRATION    21                                                VE     N-729-1  B4.10                     22 CH-1 12-207-22   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    22                                                VE     N-729-1  B4.10                     22 CR-i 112-207-23  ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    23                                                VE     N-729-1  B4.10                     22 Cl-I- 112-207-24 ISI-RBB01 SHT. 1 RV CRDM PENETRATION    24                                                VE     N-729-1  B4.10                     22 CR-i112-207-25   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    25                                                VE     N-729-1  B4.10                     22 CR-i 112-207-26  ISI-RBB01 SHT. 1 RV CRDM PENETRATION    26                                                VE     N-729-1  84.10                     22 CR-I 112-207-27  ISI-RBB01 SHT. 1 RV CRDM PENETRATION    27                                                VE     N-729-I  84.10                     22 CH-1 12-207-28   ISI-RBB01 SRT. 1 RV CRDM PENETRATION    28                                                VE     N-729-I  B4.10                     22 CR-i112-207-29   ISI-RBB0 1 SHT. I RV CRDM PENETRATION    29                                                VE     N-729-1  B4.10                     22 CH-1 12-208-30   ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    30                                                VE     N-729-1  84.10                     22 CH-1 12-208-31   ISI-REBB01 SHT. 1 RV CRDM PENETRATION    31                                                VE     N-729-1  84.10                     22 CR-i112-208-32   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    32                                                VE     N-729-1  84.10                     22 CR-I112-208-33   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    33                                                VE     N-729-1  84.10                     22 CR-i112-208-34   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    34                                                VE     N-729-1  B4.10                     22 CR-I112-208-35   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    35                                                VE     N-729-1  B4.10                     22 CH-1 12-208-36   ISI-RBB0 1 SHT. I RV CRDM PENETRATION    36                                                VE     N-729-I  B4.10                     22 CH-1 12-208-37   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    37                                                VE     N-729-1  B4.10                     22 CH-1 12-209-3 8  ISI-RBB01 SHT. 1 RV CRDM PENETRATION    38                                                VE     N-729-1  B4.I10                    22 CH-i-i12-209-39  ISI-RBB01 SHT. 1 RV CRDM PENETRATION    39                                                VE     N-729-1  B4.10                     22 CR-i112-209-40   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    40                                                VE     N-729-1  B4. 10                    22 CR-i112-209-41   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    41                                                VE     N-729-I  B4.10                     22 CH-1 12-210.-42  ISI-RBB01 SHT. I RV CRDM PENETRATION    42                                                VE     N-729-I  84.10                     22 CH-1 12-210-43   ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    43                                                VE     N-729-1  84.10                     22 CH-1 12-210-44   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    44                                                VE     N-729-1  B4. 10                    22 CR-I112-210-45   ISI-RBB0 1 SHT. I RV CRDM PENETRATION    45                                                VE     N-729- I B4. 10                    22 CR-I112-210-46   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    46                                                VE     N-729-1  B4.10                     22 CH-1 12-210-47   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    47                                                VE     N-729-1  B4.10                     22 CR-i112-210-48   ISI-RBB01 SRT. I RV CRDM PENETRATION    48                                                VE     N-729-1  B4.10                     22 CR-i112-210-49   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    49                                                VE     N-729-1  B4.10                     22 CR-I112-211-50   ISI-RBB01 SHT. I RV CRDM PENETRATION    50                                                VE     N-729-1I B4.10                     22 CH-1 12-211-51   ISI-RBB01 SHT. I RV CRDM PENETRATION    51                                                VE!    N-729-1I B4.10                     22 CR-I112-211-52   ISI-RBB01 SHlT. 1 RV CRDM PENETRATION    52                                                VE     N-729-1  B4.10                     22 CH-112-211-53    ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    53                                                VE     N-729-1  B4. 10                    22 CR-i112-212-54   ISI-RBB01 SLIT. 1 RV CRDM PENETRATION    54                                                VE     N-729-1  B4. 10                    22 CH-1 12-212-55   ISI-RBB01 SHT. I RV CRDM PENETRATION    55                                                VE     N-729-1  B4.10                     22 CR-i112-212-56   ISI-RBB01 SilT. 1 RV CRDM PENETRATION    56                                                VE     N-729-1  B4.10                     22 CR-i112-212-57   ISI-RBB01 SHT. I RV CRDM PENETRATION    57                                                VE     N-729-1  B4.10                     22 CH-i112-212-58   ISI-RBBOi SHT. I RV CRDM PENETRATION    58                                                VE     N-729-1  B4. 10                    22 WCRE-30                                                   4.1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 43 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3 I~eiod3 xaminations ]
Relief Request or Component Name   Drawing Number   Component Description                                Size Thickness NDE Method Category Item    Cal Block         Notes CH-1 12-212-59  ISI-RBB01 SHT. 1 RV CRDM  PENETRATION   59                                               VE     N-729-1  B4.10                       22 CH-1 12-212-60  ISI-RBB0 1 SHT. 1 RV CRDM  PENETRATION   60                                               VE     N-729-1  B4.10                       22 CH-1 12-212-61  ISI-RBB01 SHT. 1 RY CRDM  PENETRATION   61                                               YE     N-729-1  B4. 10                      22 CH-1 12-213-62  ISI-RBB0I SHT. 1 RV CRDM  PENETRATION   62                                               VE     N-729-1  B4.10                       22 Cl-I-i12-213-63 ISI-RBB01 SHT. 1 RV CRDM  PENETRATION   63                                               VE     N-729-1  B4.10                       22 CH-1 12-213-64  ISI-RBB0 1 SHT. 1 RV CRDM  PENETRATION   64                                               YE     N-729-1  B4.10                       22 CH-1 12-213-65  ISI-RBB0 1 SHT. 1 RV CRDM  PENETRATION   65                                               VE     N-729-1  B4.10                       22 CH-1 12-214-66  1SI-RBB01 SHT. 1 RV CRDM  PENETRATION   66                                               VE     N-729-1  B4.10                       22 CH-1 12-214-67  ISI-RBB01 SHT. I RV CRDM  PENETRATION   67                                               VE     N-729-1  B4.10                       22 CH-1 12-214-68  ISI-RBB01 SHT. I RV CRDM  PENETRATION   68                                               VE     N-729-1  B4.10                       22 CH-1 12-214-69  ISI-RBB0 1 SHT. 1 RV CRDM  PENETRATION   69                                               VE     N-729-1  B4.10                       22 CH-1 12-214-70  ISI-RBB01 SHT. 1 RV CRDM  PENETRATION   70                                               VE     N-729-1  84.10                       22 CH-1 12-214-71  ISI-RBB01 SLIT. 1 RV CRDM  PENETRATION   71                                               VE     N-729-1  B4. 10                      22 CH-1 12-214-72  ISI-RBB01 SHT. 1 RV CRDM  PENETRATION   72                                               VE     N-729-1  B4.10                       22 CH-112-214-73   ISI-RBB0I SHT. 1 RV CRDM  PENETRATION   73                                               YE     N-729-1  B4. 10                      22 CH-1 12-215-74  ISI-RBB01 SHT. 1 RV CRDM  PENETRATION   74                                               YE     N-729-1  B4.10                       22 CH-1 12-215-75  ISI-RBB01 SHT. I RV CRDM  PENETRATION   75                                               YE     N-729-1  B4.10                       22 CH-1 12-215-76  ISI-RBB01 SIT. 1 RV CRDM  PENETRATION   76                                               YE     N-729-1  B4.10                       22 CH-1 12-215-77  ISI-RBB01 SHT. I RV CRDM  PENETRATION   77                                               YE     N-729-1  B4.10                       22 CH-1 12-215-78  ISI-RBB0 1 SHT. I RY CRDM  PENETRATION   78                                               YE     N-729-1  B34.10                      22 RV-201-151-1    ISI-RBB01 SHT. I RV BMI PENETRATION I                                                    YE     N-722-1  B 15.80                     23 RV-201-151-2    ISI-RBB0 1 SHT. 1 RY BMI PENETRATION 2                                                    YE     N-722-I  B 15.80                     23 RV-201-151-3    ISI-RBB01 SHT. 1 RV BMI PENETRATION 3                                                    YE     N-722-1  B 15.80                     23 RV-201-151-4    ISI-RBB01 SHT. 1 RY BMI PENETRATION 4                                                    YE     N-722-1  B 15.80                     23 RV-201-151-5    ISI-RBB01 SHT. I RY BMI PENETRATIONS5                                                    YE     N-722-1  815.80                      23 RV-201I-151-6   ISI-RBB01 SHT. I RV BMI PENETRATION 6                                                    YE     N-722-1I B 15.80                     23 RV-201-151-7    ISI-RBB0 1 SIT. I RY BMI PENETRATION 7                                                    YE     N-722-1  B 15.80                     23 RV-201-151-8    ISI-RBB01 SHT. 1 RY BMI PENETRATION 8                                                    YE     N-722-1  B 15.80                     23 RV-20 1-151-9   ISI-RBB01 SHT. 1 RV BMI PENETRATION 9                                                    YE     N-722-1  B 15.80                     23 RV-201-151-10   ISI-RBB01 SIT. 1 RV BMI PENETRATION 10                                                   YE     N-722-1  B 15.80                     23 RV-201-151-1 1  ISI-RBB01 SHT. 1 RY BMI PENETRATION 11                                                   YE     N-722-1  B 15.80                     23 RV-201-151-12   ISI-RBB01 SHT. 1 RY BMI PENETRATION 12                                                   VE     N-722-1  B 15.80                     23 RV-201-151-13   ISI-RBB01 SHT. 1 RY BMI PENETRATION 13                                                   YE     N-722-1  B 15.80                     23 RV-201-151-14   ISI-RBB01 SIT. 1 RY BM1 PENETRATION 14                                                   YE     N-722-1  B15.80                      23 RV-201-151-15   ISI-RBB01 SHT. 1 RY BMI PENETRATION 15                                                   YE     N-722-1  B15.80                      23 RV-201-151-16   ISI-RBB01 SHT. I RV BMI PENETRATION 16                                                   YE     N-722-1  B 15.80                     23 RV-201-151-17   ISI-RBB01 SHT. 1 RY BMI PENETRATION 17                                                   VE     N-722-1  815.80                      23 RV-201-151-18   ISI-RBB01 SHT. I RY BMI PENETRATION 18                                                   YE     N-722-1  B 15.80                     23 RV-201-151-19   ISI-RBB01 SHT. I RY BMI PENETRATION 19                                                   YE     N-722-1  815.80                      23 RV-201-151-20   ISI-RBB01 SHT. 1 RY BMI PENETRATION 20                                                   VE     N-722-1I 815.80                      23 RV-201 - 151-21 ISI-RBB01 SI-T. 1 RY BMI PENETRATION 21                                                   VE     N-722-1  B 15.80                     23 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                      Revision 0 Page 44 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BB-3 Ieod3ExaminationsI
[System: BB Relief Request or Component Name                                                                              Size Thickness NDE Method Category Item    Cal Block         Notes Drawing Number     Component Description RV-201-151-22  ISI-RBB0 1 SHT. I  RV BMI PENETRATION 22                                                       VE     N-722-I  B 15.80 RV-201-*151-23 ISI-RBB01 SHT. 1  RV BMI PENETRATION 23                                                       VE     N-722-1  B15.80 RV-201-*151-24 ISI-RBB01 SHT. 1  RV BMI PENETRATION 24                                                       VE     N-722-1  B15.80 RV-201-151-25  ISI-RBB01 SHT. 1  RV BMI PENETRATION 25                                                       VE     N-722-1  B15.80 RV-201-151-26  ISI-RBB01 SHT. 1  RV BMI PENETRATION 26                                                       VE     N-722-1  B 15.80 RV-201-151-27  ISI-RBB01 SHT. 1  RV BMI PENETRATION 27                                                       VE     N-722-1  B15.80 RV-201-1 51-28 ISI-RIBB01 SHT. 1  RV BMI PENETRATION 28                                                       VE     N-722-I  B 15.80 RV-201--151-29 IS1-RBBO1 SHT. I  RV BMI PENETRATION 29                                                       VE     N-722- l B 15.80 RV-201-l51-30  ISI-R.BB01 SI-T. 1  RV BMI PENETRATION 30                                                       VE     N-722-1  B 15.80 RV-201--151-31 ISI-RBB01 SHT. I  RV BMI PENETRATION 31                                                       VE     N-722-1  B15.80 RV-201-151-32  ISI-RIBB0I SI-T. I  RV BMI PENETRATION 32                                                       VE     N-722-1  B15.80 RV-201-151-33  ISI-RBB01 SHT. 1  RV BMI PENETRATION 33                                                       VE     N-722-1  B 15.80 RV-201-151-34  ISI-RBB01 SHT. 1  RV BMI PENETRATION 34                                                       VE     N-722-1  B15.80 RV-201-151-35  ISI-RBB01 SilT. 1  RV BMI PENETRATION 35                                                       VE     N-722-1  B 15.80 RV-201-l 51-36 ISI-RBB01 SHT. 1  RV BMI PENETRATION 36                                                       VE     N-722- I B 15.80 RV-201-l151-37 ISI-RBB01 SHT. I  RV BMI PENETRATION 37                                                       VE     N-722-1  B15.80 RV-201-151-38  ISI-RBB01 SHT. 1  RV BMI PENETRATION 38                                                       VE     N-722-1  B15.80 RV-201-15I-39  ISI-RBBO1 SHT. 1  RV BMI PENETRATION 39                                                       VE     N-722-1  B 15,80 RV-20N1-51-40  ISI-R.BB01 SIIT. I  RV BMI PENETRATION 40                                                       VE     N-722-1  B 15.80 RV-201-151-41  1SI-RBB01 SHlT. 1  RV BMI PENETRATION 41                                                       VE     N-722-1  B 15.80 RV-201-*151-42 ISI-RBB0 1 SI-T. I  RV BMI PENETRATION 42                                                       VE     N-722- l B 15.80 RV-20 1-151-43 ISI-RIBB01 SHT. I  RV BMI PENETRATION 43                                                       VE     N-722-1  B 15.80 RV-201-151-44  ISI-RBB01 SHT. I  RV BMIE PENETRATION 44                                                      VE     N-722-1I B15.80 RV-201I-I51-45 1S1-RBB0 1 SHlT. 1  RV BMI PENETRATION 45                                                       VE     N-722-1  B15.80 RV-201-151-46  ISI-RIBB01 SHT. 1  RV BMI PENETRATION 46                                                       VE     N-722-1  B 15.80 RV-201-151-47  ISI-RBB01 SHT. 1  RV BMI PENETRATION 47                                                       VE     N-722-1  B 15.80 RV-201-151-48  ISI-RBB01 SHT. 1  RV BMI PENETRATION 48                                                       VE     N-722- 1 B 15.80 RV-201-151-49  ISI-RBB0I SHT. 1  RV BMI PENETRATION 49                                                       VE     N-722-1  B 15.80 RV-20N1-51-50  ISI-RBB01 SHT. I  RV BMI PENETRATION 50                                                       VE     N-722-I  B 15.80 RV-201-151-51  ISI-RBB01 SI-T. 1  RV BMI PENETRATION 51                                                       VE     N-722-1  B 15.80 RV-201-151-52  ISI-RBB01 SHT. 1  RV BMI PENETRATION 52                                                       VE     N-722-1  B15.80 RV-201-151-53  ISI-RBB01 SHT. 1  RV BMI PENETRATION 53                                                       VE     N-722-1  B 15.80 RV-201-151-54  ISI-RIBB01 SHT. 1  RV BMI PENETRATION 54                                                       VE     N-722-1  B 15.80 RV-201 -151-55 ISI-RBB01 SHT. 1  RV BMI PENETRATION 55                                                       VE     N-722-I  B 15.80 RV-201-151-56  ISI-RBB01 SHT. 1  RV BMI PENETRATION 56                                                       VE     N-722-1I B 15.80 RV-20I- 151-57 ISI-R.BBOI SilT. 1  RV BMI PENETRATION 57                                                       VE     N-722-1  B 15.80 RV-20l- 151-58 ISI-R.BB01 SHT. 1  RV BMI PENETRATION 58                                                       VE     N-722-1  B15.80 RV-30 1-121-A   ISI-RBB01 SHT. I LOOP  #1 RPV OUTLET   NOZZLE  TO SAFE-END                29       2.92      VE     N-722-1  B 15.90                    24 RV-301-12 1-B   ISI-RBB0I SHT. 1 LOOP  #2 RPV OUTLET   NOZZLE  TO SAFE-END                29       2.92      VE     N-722-1  B 15.90                    24 RV-301-12 1-C   ISI-RBB01 SI-T. 1 LOOP  #3 RPV OUTLET   NOZZLE  TO SAFE-END                29       2.92      VE     N-722-1  B15.90                     24 RV-301-121-D    ISI-RBB0 1 SHT. I LOOP  #4 RPV OUTLET   NOZZLE  TO SAFE-END                29       2.92      VE     N-722-1  B 15.90                    24 WCRE-30                                                    4.1.4 Reactor Coolant System (BB)                                                        Revision 0 Page 45 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3 Ieid3Examinations
[  Sytem:BB            IRelief                       Request or Size   Thickness NDE Method  Category Item      Cal Block    Notes Component Name    Drawing Number    Component Description RV-302-12 1-B     ISI-RBB0 1 SHT. 1 SAFE-END TO LOOP #2 RPV INLET NOZZLE                      27.5       2.79      VE     N-722-1   B1 5.95                  25 RV-302-12 1-C     ISI-RBB01 SHT. 1  SAFE-END TO LOOP #3 RPV INLET NOZZLE                      27.5       2.79      VE     N-722-1   B15.95                   25 BB-0 1-S 102-TW-T BB-01-01          LOOP  # 1 NARROW  RANGE THERMO WELL,    TOP                                    VE     N-722-1   B15.200                  26 BB-01-S 102-TW-I  BB-01-01          LOOP  #1 NARROW   RANGE THERMO WELL,    INSIDE                                 VE     N-722-1   B15.200                  26 BB-01 -S 102-TW-O BB-01-01          LOOP  #1 NARROW   RANGE THERMO WELL,    OUTSIDE                                VE     N-722-1   B 15.200                 26 BB-0 1-S202-TW-T  BB-02-01          LOOP  #2 NARROW   RANGE THERMOWELL,     TOP                                    VE     N-722-1   B 15.200                 26 BB-0 1-S202-TW-I  BB-02-01          LOOP  #2 NARROW   RANGE THERMOWELL,     INSIDE                                 VE     N-722-1   B 15.200                 26 BB-01 -S202-TW-O  BB-02-0 1         LOOP  #2 NARROW   RANGE THERMOWELL,     OUTSIDE                                VE     N-722-1   B 15 .200                26 BB-01 -S302-TW-T  BB-03-0 1         LOOP  #3 NARROW   RANGE THERMO WELL,    TOP                                    VE     N-722-1   B 15.200                 26 BB-0 1-S302-TW-I  BB-03-01          LOOP  #3 NARROW   RANGE THERMO WELL,    INSIDE                                 VE     N-722-1   B 15.200                 26 BB-01 -S302-TW-O  BB-03-01          LOOP  #3 NARROW   RANGE THERMO WELL,    OUTSIDE                                VE     N-722-1   B 15.200                 26 BB-0 1-S402-TW-T  BB-04-01          LOOP  #4 NARROW   RANGE THERMO WELL,    TOP                                    VE     N-722-1   B 15.200                 26 BB-0 I-S402-TW-I  BB-04-0 1         LOOP  #4 NARROW   RANGE THERMO WELL,    INSIDE                                 VE     N-722-1   B 15.200                 26 BB-01-S402-TW-O   BB-04-0l          LOOP  #4 NARROW   RANGE THERMO WELL,    OUTSIDE                                VE     N-722-1   B15.200                  26 BB-01 -$201 -TW-T BB-01-01          LOOP #2 NARROW RANGE TI-ERMO WELL, TOP                                         VE      N-722-1  B 15.205                 25 BB-0 I-S301-TW-T  BB-04-01          LOOP #3 NARROW RANGE THERMO WELL, TOP                                          VE      N-722-1  B15.205                  25 HB-24-W502        BB-06-01          2" ELBOW T02" PIPE                                        2         0.344      UT      MRP-146  DH            156        27 HB-24-W5 12       BB-06-01          2' ELBOW T02" PIPE                                        2         0.344      UT      MRP-146  DH-           156        27 BG-23-W596A       BG-03-23          2" ELBOW T02" PIPE                                        2         0.344      UT      MRP-146  DH            156        27 BG-21-F027A       BG-01-21          3" PIPE TO 3" NOZZLE ON BB-56-BCA-27 1/2"                 3         0.438      UT      MRP-146  U-/H~         112        27 WCRE-30                                                     4.1.4 Reactor Coolant System (BB)                                                          Revision 0 Page 46 of 46

WOLF CREEK GENERATING STATION THIRD INTERVAL IST PROGRAM PLAN 4.1.5 Chemical and Volume Control System (BG)
A.      Applicable System Piping and Instrument Drawings
: 1. M-12BG01-Chemical and Volume Control System
: 2. M-12BG03-Chemical and Volume Control System 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 Generating Station Interval 4".
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 4".
D.       Applicable ISI Isometrics and ISI 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-01-01 Sheet 1        Chemical and Volume Control Normal Charging Line Containment Penetration
: 2. M-189-50BG-01-21 Sheet 1        Chemical and Volume Control Normal and Alternate Charging Lines 3     M-1 89-50BG-02-22 Sheet 1       Chemical and Volume Control Letdown Line 4     M-189-50BG-02-22 Sheet 2        Chemical and Volume Control Letdown Line Containment Penetration
: 5. M-189-50BG-03-23 Sheet 1        Chemical and Volume Control Excess Letdown Line
: 6. M-189-5013G-04-09 Sheet 1       Chemical and Volume Control RCP Seal Water Injection Containment Penetration
: 7. M-189-50BG-05-24 Sheet 1        Chemical and Volume Control Auxiliary Spray Line
: 8. M-189-50BG-06-02 Sheet 1        Chemical and Volume Control Centrifugal Charging Pump Suction
: 9. M-189-50BG-06-02 Sheet 2        Chemical and Volume Control CCP Discharge (HPSI Discharge)
: 10. M-189-50BG-06-10 Sheet 1 Chemical and Volume CCP Discharge to Seal Water Injection Filters 11i. M-189-50ISI-PUMPS Sheet 1 ISI Pumps WCRE-30                  4.1.5 Chemical and Volume Control System (BG)                        Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.5 Chemical and Volume Control System (BG)
E.        Summary of Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table 1 is a sunmmary 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 1S1 Database.
TABLE 1 SECTION XI AND AUGMENTED COMPONENT 

==SUMMARY==
AN]) SCHEDULE COMPONENT OR ITEM                 CODE             CODE             AUG.              AUG        TOTAL IN           EXAMS BY PERIOD & INTERVAL DESCRIPTION               CATEGORY          ITEM NO.       CATEGORY           ITEM NO.       SYSTEM       P.1   P__2   P.3       INTERVAL PIPING WELDED                   C-C             C3.20               --                             4          1     0     01 ATTACHMENTS PUMPS WELDED                    C-C             C3.30               --                             80               1     0              1 ATTACHMENTS PIPING COMPONENTS                  F-A             FI.10               --                            15         3      2     1              6 SUPPORTS PIPING COMPONENTS                  F-A             F1.20               --                            27          1     2     2              5 SUPPORTS SUPPORTS OTHER                   F-A             F1.40               --                            82                2     0              4 THAN PIPING SUPPORTS PIPING WELDS SUBJECT                 R-A             Ril.11                                            18         1      2     2              5 TO THERMAL FATIGUE                 Note 1           Note 1 PIPING WELDS NOT                  R-A             R1.20              --                            173         4      4     4              12 SUBJECT TO A DAMAGE                 Note 1           Note 1 MECHANISM PIPING WELDS SUBJECT                                                 USAR               3.6.2         76          0      0     0              0 TO HELB REQUIREMENTS              _  _   _  _ _     _    _   _  _     _  _     _  _      _  _   _ _ _  _  _   _ _ _    _   __  _   _   _ _   _ _   _  _  _   _
Note 1: See Section H for an explanation of Category R-A and Item R1 .XX nomenclature.
WCRE-30                                                  4.1.5 Chemical and Volume Control System (BG)                                              Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.5         Chemical and Volume Control System (BG)
F. Augmented ISI Requirements 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 Pipinu- 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-33 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-5O00 and IWB-5000, the Class 1 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 XI, 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 4.2.1i H. Risk Informed ISI Program A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class 1 and 2 piping welds at WCGS. 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-1 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 through 4-4 of TR-1 12657 Rev. B-A.
Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table BG-l (Period 1 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-30                4.1.5 Chemical and Volume Control System (BG)                            Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BG-1
[Period 1 Examinations SSystem: BG Relief Request or Component Name Drawing 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-23-W593     BG-03-23        2"x2"x3/4" TEE TO 2" PIPE                                 2       0.344      UT     R-A      RI~ll      156           1,2 BG-23-W584     BG-03-23        2" TEE TO 2" PIPE                                         2       0.344      UIT    R-A      R1.20      156 BG-02-F045     BG-06-02 SHT. 2 4" PIPE TO 4" ELBOW                                       4       0.531      UT     R-A      RL.20      114 1
BG-02-FW3 12   BG-06-02 SHT. 2 4" PIPE TO 4" ELBOW                                       4       0.531      UT     R-A      R1.20      114 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-H001     BG-05-24        PIPING SUPPORT                                            2                 VT-3    F-A      FI.10 BG-2 I-R017    BG-01-21        PIPING SUPPORT                                            3                 VT-3    F-A      F!I0 BG-24-R003     BG-05-24        PIPING SUPPORT                                            2                 VT-3    F-A      FI.!
BG-02-A002     BG-06-02 SHT. 1 PIPING SUPPORT                                            8                 VT-3    F-A      F 1.20 PBG05A-SUP-1   BG-06-02 SHT. 1 CHARGING PUMP A SUPPORT                                   6                         F-A      F1.40 VT-3 PBG05A-SUP-2   BG-06-02 SHT. 1 CHARGING PUMP A SUPPORT                                   6                         F-A      F 1.40 WCRE-30                                              4.1.5 Chemical and Volume Control System (BG)                                               Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTHINTERVAL 1SI PROGRAM PLAN TABLE BG-2 F Period2Eaiations I SSystem:  BG Relief Request or Size    Thickness NDE Method          Item  Cal Block          Notes Component Name Drawing Number  Component Description                                                             Category PBG05A-SUP-3   BG-06-02 SHT. 1 CHARGING PUMP A INTEGRALLY WELDED ATTACH.            6                     PT     C-C      C3.30 BG-2 l-F013B   BG-01-21        3" PIPE TO VALVE 8378A                               3          0.438      UT     R-A      RI 11     112          1,2 BG-22-FW327A   BG-02-22 SET. 1 3" ELBOW TO 3" PIPE'"                                3          0.438      UIT    R-A      RI ll     112          1,2 BG-21-FW3 14   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      UIT    R-A      R1.20     114 BG-02-S056-A   BG-06-02 SHT. 2 4" TEE TO 4" PIPE                                    4          0.531      UT     R-A      R1.20     114 BG-10-FW066    BG-06-10        3" X 2" REDUCER TO 2" PIPE                           2          0.344      UIT    R-A      R1.20     156 BG-2 l-H008    BG-01-21        PIPING SUPPORT                                       3                    VT-3    F-A      FI.10 BG-22-H007     BG-02-22 SHT. 1 PIPING SUPPORT                                       3                    VT-3    F-A      FI.10 BG-02-R016     BG-06-02 SHT. 1 PIPING SUPPORT                                       6                    VT-3    F-A      F1.20 BG- 10-C528    BG-06-10        PIPING SUPPORT                                       2                    VT-3    F-A      F1.20 PBG05A-SUP-3   BG-06-02 SET. 1 CHARGING PUMP A SUPPORT                              6                    VT-3    F-A      FI.40 PBQ05A-SUP-4   BG-06-02 SET. I CHARGING PUMP A SUPPORT                              6                    VT-3    F-A      F1.40 WCRE-30                                             4.1.5 Chemical and Volume Control System (BG)                                             Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BG-3 SPeriod 3 Examinations
[System: BG Relief Request or Component Name Drawing Number   Component Description                                      Size Thickness NDE Method Category Item   Cal Blo'      ck   Notes BG-24-FW553A   BG-05-24         BBV084 SAFE END TO 2" X 2" X 3/4' TEE                      2       0.344      UT     R-A      RI.11      156           1,2 BG-23-W594A    BG-03-23         2' PIPE TO 2" X 2" X 3/4" TEE                              2       0.344      UT     R-A      RI ll      156           1,2 BG-24-FW554    BG-05-24         2" X 2" X 3/4" TEE TO 2" PIPE                              2       0.344      UT     R-A      R1.20      156 BG-10-F003     BG-06-10         3" X2" REDUCER TO 2" PIPE                                  2       0.344      UT     R-A      R1.20      156 BG-02-S040-A   BG-06-02 SHlT. 2 4" ELBOW TO 4" PIPE                                        4       0.531      UT     R-A      R1.20      114 BG-02-S046-B   BG-06-02 SHlT. 2 4" TEE TO 4" X 3" REDUCER                                  4       0.531      UT     R-A      R1.20      114 BG-22-H008     BG-02-22 SHIT. 1 PIPING SUPPORT                                             3                 VT-3    F-A      FI.10 BG-02-C0 13    BG-06-02 SHT. 1  PIPING SUPPORT                                             8                 VT-3    F-A      F 1.20 BG-02-H007     BG-06-02 SHT. 1  PIPING SUPPORT                                             6                 VT-3    F-A      F1.20 WCRE-30                                                4.1.5 Chemical and Volume Control System (BG)                                                Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.6 Steam Generator Blowdown System (BM)
A. Applicable System Piping and Instrument Drawings
: 1. M-12BMO01-Steam Generator Blowdown System B. Classification of Components Details of the classification of the Steam Generator Blowdown System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
D. Applicable 151 Isometrics and 1SI 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-189-50 series.
: 1. M-189-50BM-01-01 Sheet 1 Steam Generator Blowdown Loop A & D
: 2. M-189-50BM-01-02 Sheet 1 Steam Generator Blowdown Loop B & C WCRE-30                4.1.6 Steam Generator B lowdown System (BM)                            Revision 0 Page 1 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.6 Steam Generator Blowdown System (BM~)
E. Summary of Components Subject To Section XI and Augmented NDElScheduled For Examination Table 1 is a sunmmary 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. P1__    P.22    P_.3      TNTERVAL PIPING WELDS SUBJECT                                             USAR             3.6.2          36        0      0       0                0 TO HELB REQUIREMENTS            __ _   _  _   _  _____           __  _  _  _  _  _   _   _  _ __   _   _ _  __   _ _   _  _ _   _ _  _ _  _    _   _   _  _ _
WCRE-30                                              4.1.6 Steam Generator Blowdown System (BM)                                                 Revision 0 Page 2 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.6 Steam Generator Blowdown System (BM)
F. Augmented IS1 Requirements The following Augmented ISI requirements apply to the Steam Generator Blowdown 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-33 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 XI, 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 RM-SI Program is not applicable to the BM system.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table BM-1 (Period 1 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-30                  4.1.6 Steam Generator Blowdown System (BM)                            Revision 0 Page 3 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.7 Borated Refueling Water System (&sect;BN)
A. Applicable System Piping and Instrument Drawings
: 1. M-12BN0 1-B orated Refueling Water System B. Classification of Components Details of the classification of the Borated Refueling Water System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the B orated Refueling Water System. These drawings are part of the M-189-50 series.
1    M-189-50BN-01-01 Sheet 1         Borated Refueling Water Storage Supply
: 2. M-189-50BN-01-01 Sheet 2         Borated Refueling Water Storage Supply
: 3. M-189-50BN-01-01 Sheet 3         Borated Refueling Water Storage Supply WCRE-30                    4.1.7 B orated Refueling Water System (BN)                            Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.7 Borated Refueling Water System (RN)
E.       Summary of 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 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       P1    P__2    P3         INTERVAL PIPING WELDED                   C-C            C3.20               --                         4          1     0       01 ATTACHMENTS PIPING WELDS NOT                  R-A            R1.20               --                        127         0     0       0                0 SUBJECT TO A DAMAGE               Note 1           Note 1 MECHANISM PIPING COMPONENTS                  F-A            F1.20              --                         24          1     2       2                5 SUPPORTS Note 1: See Section H for an explanation of Category R-A and Item R1.XX nomenclature.
WCRE-30                                                   4.1.7 Borated Refueling Water System (BN)                                           Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1o7 Borated Refueling Water System (RN)
F.      Augmented ISI Requirements No Augmented IS1 requirements apply to the Borated Refueling Water System.
G.      System Pressure Testing In accordance with Section XI, IWA-5000 and IWC-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.
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 1 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.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table BN-1 (Period 1 Examinations), Table BN-2 (Period 2 Examinations),
and Table BN-3 (Period 3 Examinations).
WCRE-30                    4.1.7 Borated Refueling Water System (BN)                         Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BN-I
[Period 1 Examinations Relief Request or Component Name Drawing Number  Component Description                                      Size Thickness NDE Method Category Item  Cal Block         Notes BN-01-A001     BN-01-0I SHT. 2 INTEGRAL PIPING ATTACHMENTS                                                   PT     C-C      C3.20 14 BN-01-A001                                                                                                  VT-3    F-A      F1.20 BN-01-01 SHT. 2 PIPING SUPPORT WCRE-30                                              4.1.7 B orated Refueling Water System (BN)                                                 Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BN-2 I eid2Examinations
[System: BN Relief Request or Component Name Drawing Number  Component Description                                      Size Thickness NDE Method Category Item  Cal Block         Notes BN-01 -H003    BN-0l-01 SHT. 1 PIPING SUPPORT                                            24                 VT-3    F-A      F1.20 BN-0OI-C005    BN-01-01 SHT. 2 PIPING SUPPORT                                            24                 VT-3    F-A      F1.20 WCRE-30                                              4.1.7 B orated Refueling Water System (BN)                                                 Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BN-3 IPeriod 3 Examinations L2Systm: BNJ 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                                                  8VT-3                 F-A      F 1.20 BN-0 l-R001    BN-01-01 SILT. 3 PIPING SUPPORT                                             12                 VT-3    F-A      FI1.20 WCRE-30                                               4.1.7 B orated 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- 12EFO01-Essential Service Water System
: 2. M-12EF02-Essential Service Water System
: 3. M-K2EF0 1-Essential Service Water System
: 4. M-K2EFO3-Essential Service Water System B. Classification of Components 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 4".
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 4".
B. Applicable ISI Isometrics and lSI 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-189-50EF-01-01            Sheet 1  Essential Service Water "A" Train Supply
: 2.        M-189-50EF-01-01            Sheet 2  Essential Service Water "A" Train Supply
: 3.        M-189-50EF-01-02            Sheet 1  Essential Service Water "A" Train Supply
: 4.         M-189-50EF-01-02            Sheet 2  Essential Service Water "A" Train Supply
: 5.         M-189-50EF-01-03            Sheet 1  Essential Service Water "A" Train Return
: 6.        M-189-50EF-01-03            Sheet 2  Essential Service Water "A" Train Return
: 7.        M-189-50EF-01-07            Sheet 1  Essential Service Water "A" Train Return
: 8.        M-189-50EF-01-08            Sheet 1  Essential Service Water "A" Train Supply
: 9.        M-189-50EF-01-09            Sheet 1  Essential Service Water Containment Cooling "A" Train Supply
: 10.       M-189-50EF-01-10            Sheet 1 Essential Service Water Containment Cooling "A" Train Return
: 11.       M-1 89-50EF-02-0 1          Sheet 1 Essential Service Water "B" Train Supply
: 12.       M-1 89-5OEF-02-0 1          Sheet 2 Essential Service Water "B" Train Supply
: 13.       M-1 89-5OEF-02-0 1          Sheet 3 Essential Service Water "B" Train Return
: 14.       M- 189-5OEF-02-04           Sheet 1 Essential Service Water "B" Train Supply
: 15.       M-1 89-5OEF-02-05           Sheet 1 Essential Service Water "B" Train Return
: 16.       M-1 89-50EF-02-05           Sheet 2 Essential Service Water "B" Train Return
: 17.       M-1 89-5OEF-02-06           Sheet 1 Essential Service Water "B" Train Supply
: 18.       M-1 89-5OEF-02-08           Sheet 1 Essential Service Water "B" Train Supply
: 19.       M-189-5OEF-02-08            Sheet 2 Essential Service Water "B" Train Supply
: 20.       M-189-5OEF-02-09            Sheet 1 Essential Service Water Containment Cooling "B" Train Supply
: 21.       M-189-50EF-02-10            Sheet 1 Essential Service Water Containment Cooling "B" Train Return
: 22.       M-189-50EF-03-0 1           Train A & B Underground Supply and Return Piping In Vaults WCRE-30                             WCRE-304.1.8 Essential Service Water System (EF)                           Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.8 Essential Service Water System (EF)
E.       Summary of 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 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     P1    P._2     P_33       INTERVAL PIPING WELDED                 C-C            C3.20                --                           4       0      1       01 ATTACHMENTS VESSEL WELDED                 D-A             D1.10               --                            41             1       0                 2 ATTACHMENTS PIPING WELDED                D-A             D1.20               -                            83       4      3       3                10 ATTACHMENTS PUMP WELDED                  D-A             D 1.30               --                           2       0      0       1                 1 ATTACHMENTS PIPING COMPONENT                F-A             F1.20                --                           3       0      1      0                  1 SUPPORTS PIPING COMPONENT                 F-A            F1.30                --                         258       9      9      11                29 SUPPORTS EQUIPMENT SUPPORTS                F-A             F1.40               --                           61              2      0                  3 (Other Than Piping)___                                              ____      _____
PIPING WELDS NOT                R-A             RI.20               --                           26       0      0      0                  0 SUBJECT TO A DAMAGE               Note 1           Note I MECHANISM Note 1: See Section H for an explanation of Category R-A and Item R1.XX nomenclature.
WCRE-30                                                       4.1.8 Essential Service Water System (EF)                                           Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.8 Essential Service Water System (EF)
F. Augmented ISI Requirements No Augmented 1SI requirements apply to the Essential Service Water System.
G. System Pressure Testing 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.
In accordance with Section XI, IWA-5000 and IWD-5000, the Class 3 pressure retaining components within the Essential Service Water System will receive a system leakage test per IWD-5 220 every 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 1 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-l1. No welds in the EF system were selected for examination in the RI-ISI program.
I. Components and Component Supports Selected/Scheduled For Examinntion The components and component supports selected for examination during Interval 4 are included in Table EF-1 (Period 1 Examinations), Table EF-2 (Period 2 Examinations),
and Table EF-3 (Period 3 Examinations).
WCRE-30                   4.1.8 Essential Service Water System (EF)                         Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL IS1 PROGRAM PLAN TABLE EF-1 SPeriod 1 Examinations
[System:  EF Relief Request or Cal Block          Notes Component Name    Drawing Number   Component Description                               Size  Thickness    NDE Method Category  Item FEF02A-SUPPORT- 1 EF-01-01 SHT. 1  VESSEL INTEGRAL ATTACHMENTS                         30                    VT-I    D-A      DI.10 EF-0 1-C004       EF-01-03 SHT. 2  PIPING INTEGRAL ATTACHMENTS                         30                    VT-I    D-A      D1.20 EF-01-C005        EF-02-01 SHT. 2  PIPING INTEGRAL ATTACHMENTS                         30                    VT-i    D-A      D1.20 EF-01-C005        EF-02-01 SHT. 2  PIPING SUPPORT                                      30                    VT-3    F-A      F 1.30 EF-01-C004        EF-01-03 SHT. 2  PIPING SUPPORT                                      30                    VT-3    F-A      F 1.30 EF-07-C003        EF-01-08         PIPING SUPPORT                                      8                     VT-3    F-A      F 1.30 K-EF-1 1-H007     EF-02-01 SHT. 1  PIPING SUPPORT                                      30                    VT-3    F-A      F 1.30 EF-05-HOI11       EF-02-05 SHT. 1  PIPING SUPPORT                                      24                    VT-3    F-A      FI1.30 EF-04-R009        EF-02-06         PIPING SUPPORT                                      14                    VT-3    F-A      F 1.30 EF-0 8-CO013      EF-02-08 SHT. 1  PIPING SUPPORT                                      8                     VT-3    F-A      F1.30 EF-203-H005       EF-03-0 1 SHT. 1 PIPING SUPPORT                                      30                    VT-3    F-A      F1.30 EF-203-H004       EF-03-0 1 SHT. 1 PIPING SUPPORT                                      30                    VT-3    F-A      FI.30 EF-203-H005       EF-03-01 SI-T.I  PIPING INTEGRAL ATTACHMENTS                         30                            D-A      D 1.20 VT-I EF-203-H004       EF-03-01 SHT.I   PIPING INTEGRAL ATTACHMENTS                         30                            D-A      D 1.20 PEF1lA-SUPPORT- 1 EF-01-01 SHT. 1  ESW PUMP A SUPPORT                                  30                    VT-3    F-A      F1.40 WCRE-30                                                         4.1.8 Essential Service Water System (EF)                                           Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EF-2 IPeriod 2 Examinations ISystem: EF      ]
Relief Request or Cal Block         Notes Component Name    Drawing Number   Component Description                               Size  Thickness  NDE Method Category Item GN-01I-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. I  PIPING INTEGRAL ATTACHMENTS                         24                  VT-I    D-A      D1.20 EF-06-A0 14       EF-02-06         PIPINiG INTEGRAL ATTACHMENTS                         8                  VT-I    D-A      D1,20 EF-203-H01 8      EF-03-01 SHT.I   PIPING INTEGRAL ATTACHMENTS                         30                  VT-I    D-A      D01.20 EF-02-R017        EF-01-09         PIPING SUPPORT                                       14                 VT-3    F-A      F1.20 EF-06-C026        EF-O1-02 SHT. 2  PIPING SUPPORT                                       8                  VT-3    F-A      F1.30 EF-03-C004        EF-01-03 SHT, l  PIPING SUPPORT                                      24                  VT-3    F-A      F1,30 EF-03-H004        EF-01-03 SHT. 2  PIPING SUPPORT                                       16                 VT-3    F-A      FI.30 EF-05-R005        EF-02-05 SHT. 1  PIPING SUPPORT                                      24                  VT-3    F-A      F1.30 EF-06-A014        EF-02-06         PIPING SUPPORT                                       8                  VT-3    F-A      F1.30 EF-203-H01 8      EF-03-01 SHT,1   PIPING SUPPORT                                       30                 VT-3    F-A      F1.30 EF-01-C001        EF-01-01 SHT.2   PIPING SUPPORT                                       30                 VT-3    F-A      F1.30 EF-01-C007        EP-02-01 SHT.2   PIPING SUPPORT                                       30                 VT-3    F-A      F1,30 EF-08-C002        EF-01-08         PIPING SUPPORT                                       8                  VT-3    F-A      F1.30 FEF02A-SUPPORT- 1 EF-01-01 SHT. 1  VESSEL SUPPORT                                       30                 VT-3    F-A      F1.40 FEF02A-SUPPORT-2  EF-01-01 SILT. 1 VESSEL SUPPORT                                       30                 VT-3    F-A      F1.40 WCRE-30                                                         4.1.8 Essential Service Water System (EF)                                         Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EF-3
[Period 3 Examinations    ]
[System:   EF Relief Request Component Name                                                                              Size Thickness NDE Method Category Item   Cal Block     or Notes Drawing Number    Component Description EF-03-R021         EF-01-03 SHT. 1   PIPING INTEGRAL ATTACH-MENTS                           24                VT-I    D-A      DI.20 EF-03-C016         EF-01 -03 SHT. 2  PIPING INTEGRAL ATTACHMENTS                            8                         D-A      D1.20 VT-i EF-203-H024        EF-03-0I SHT.I    PIPING INTEGRAL ATTACI-MvENTS                          24                        D-A      D1.20 VT-1 PEF01 A-SUPIORT- 1 EF-01-01 SHT. 1   ESW PUMP INTEGRAL ATTACHMENT                           30                        D-A      D1.30 VT-3 K-EF-l 1l-RO0l     EF-01-01 SHT. 1   PIPING SUPPORT                                         30                        F-A      F 1.30 VT-3 K-EF-1 i-R003      EF-01-01 SHT. I   PIPING SUPPORT                                         30                        F-A      F!1.30 VT-3 K-EF- I 1 -R00OS   EF-01-01 SHT. I   PIPING SUPPORT                                         30                        F-A      F1.30 VTr-3 EF-01 -C002        EF-0l-01 SHT. 2   PIPING SUPPORT                                         30                        F-A      F1.30 EF-02-A0 10        EF-01-01 SI-IT. 2 PIPING SUPPORT                                         18                VT-3    F-A      F1.30 EF-03-R021         EF-01-03 SHT. 1   PIPING SUPPORT                                         24                VT-3    F-A      F1.30 EF-03-C016         EF-01-03 SHT. 2   PIPING SUPPORT                                         8                 VT-3    F-A      F 1.30 EF-07-C009         EF-01-07          PIPING SUPPORT                                         8                 VT-3    F-A      F1.30 EF-05-R013         EF-02-05 SHT. 1   PIPING SUPPORT                                         24                VT-3    F-A      F 1.30 EF-06-H001         EF-02-06          PIPING SUPPORT                                         8                 VTr-3   F-A      F1.30 EF-203-H024        EF-03-0 1 SHT. 1  PIPING SUPPORT                                         24                        F-A      F1.30 WCRE-30                                                        4.1.8 Essential Service Water System (EF)                                          Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.9 Component Cooling Water System (EG)
A. Applicable System Piping and Instrument Drawings
: 1. M-12EG0 1-Component Cooling Water System
: 2. M-12EG02-Component Cooling Water System
: 3. M-12EG03-Component Cooling Water System B. Classification of Components Details of the classification of the Component Cooling Water System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
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 Cooling Water System. These drawings are part of the M-189-50 series.
: 1.      M-189-50EG-01-01           Sheet 1      Component Cooling Water "A" Train CCW Heat Exchanger
: 2.       M- 189-50EG-01-02          Sheet 1      Component Cooling Water "A" Train Supply
: 3.       M- 189-50EG-01-02          Sheet 2      Component Cooling Water "A" Train Return
: 4.       M-1 89-50EG-02-03          Sheet 1      Component Cooling Water "B" Train CCW Heat Exchanger
: 5.       M-1 89-50EG-02-03          Sheet 2      Component Cooling Water "B" Train
: 6.       M- 189-50EG-02-05          Sheet 1      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 1      Component Cooling Water Common Header
: 9.      M- 189-50EG-03-07          Sheet 1      Component Cooling Water Common Header
: 10. M- 189-50EG-04-01          Sheet 1      Component Cooling Water RHR Heat Exchanger Supply
: 11. M- 1 89-50EG-04-0 1        Sheet 2      Component Cooling Water RHR Heat Exchanger Return
: 12. M-189-50EG-05-06           Sheet 1      Component Cooling Water Letdown Heat Exchanger Supply
: 13. M- 189-50EG-05-06          Sheet 2      Component Cooling Water Letdown Heat Exchanger Return WCRE-30                            4.1.9 Component Cooling Water System (EG)                      Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.9 Component Cooling Water System (EG)
E. Summary of 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 1SI 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        P1    P2       P3         INTERVAL VESSEL WELDED               D-A             Dl.10               --                        10          4      2       0                 6 ATTACHMENTS PIPING WELDED               D-A             D 1.20              --                       47           2     2        2                 6 ATTACHMENTS PIPING COMPONENT              F-A             F1.30               --                       209          5     11       8                24 SUPPORTS EQUIPMENT SUPPORTS              F-A             F1.40               --                       20           4     2       4                 10 (OTHER THAN PIPING)
WCRE-30                                                4.1.9 Component Cooling Water System (EG)                                               Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.9 Component Cooling Water System (EG)
F. Augmented ISI Requirements No Augmented ISI requirements apply to the Component Cooling Water System.
G. System Pressure Testing In accordance with Section XI, 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-5220 every 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 EG system.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table EG-1 (Period 1 Examinations), Table EG-2 (Period 2 Examinations),
and Table EG-3 (Period 3 Examinations).
WCRE-30                  4.1.9 Component Cooling Water System (EG)                          Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EG-1 IPeriod 1 Examinations Component Name Drawing Number  Component Description                                  Size Thickness NDE Method Category Item   Relief Request    Notes EEGO1lA-SUP-1  EG-01-0 l       CCW HX INTEGRAL ATTACHMENT                                               VT-i    D-A      DI.10 EEGOIA-SUP-2   EG-01-01        CCW HX INTEGRAL ATTACHMENT                                               VT-I    D-A EEG01A-SUP-3   EG-01-01        CCW HX INTEGRAL ATTACHMENT                                               VT-i    D-A EEGO1A-SUP-4   EG-01-O1        CCW H-X INTEGRAL ATTACHMENT                                              VT-i    D-A EG-0i-R023     EG-01-01        PIPING INTEGRAL ATTACHMENTS                                              VT-i    D-A      D1.20 20 EG-02-A005     EG-01-02 SHT. 1 PIPING INTEGRAL ATTACHMENT                             12                VT-I    D-A      D1.20 EG-01i-R023    EG-01-01        PIPING SUPPORT                                         20                VT-3    F-A      FI.30 EG-02-A005     EG-01-02 SHT. 1 PIPING SUPPORT                                         12                VT-3    F-A      F1.30 EU-I 8-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      F 1.30 EG-06-H002     EG-03-06        PIPING SUPPORT                                         12                VT-3    F-A      F1.30 EEG01IA-SUP-i  EG-01-01        CCW H-X SUPPORT                                                          VT-3    F-A      Ft1.40 EEGO 1A-SUP-2  EG-01-01        CCW H-X SUPPORT                                                          VT-3    F-A      Ft1.40 EEG01A-SUP-3   EG-01-01        CCW f-IX SUPPORT                                                         VT-3    F-A      F 1.40 EEG01 A-SUP-4  EG-O1-01        CCW HX SUPPORT                                                           VT-3    F-A      Ft.40 WCRE-30                                               4.1.9 Component Cooling Water System (EG)                                                Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   EG-2 F  eiod 2ExaminationsI
[System:  EG Component Name    Drawing Number   Component Description                               Size  Thickness NDE Method Category Item   Relief Request    Notes EBGO01-SUPPORT-i1 EG-05-06         LETDOWN HX INTEGRAL ATTACHMENT                                         VT-i    D-A EBG01I -SUPPORT-2 EG-05-06         LETDOWN FIX INTEGRAL ATTACHMENT                                        VT-i    D-A      DI.10 EG-04-A001        EG-04-01 SHT. 2  PIPING INTEGRAL ATTACHMENTS                         18                 VT-i    D-A      D1.20 EG-06-C016        EG-05-06 SHT. 1  PIPING INTEGRAL ATT7ACHMENT                         6                  VT-i    D-A      D1.20 EG-1 8-COO01      EG-01-02 SI-T. 1 PIPING SUPPORT                                      12                 VT-3    F-A      F 1.30 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-H007        EG-04-0I SHT. 1  PIPING SUPPORT                                      18                 VT-3    F-A      F 1.30 EG-04-A001        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      Ft1.30 EG-06-C016        EG-05-06 SHT. 1  PIPING SUPPORT                                      6                  VT-3    F-A      F1.30 EG-03-R01 8       EG-02-03 SHT. 1  PIPING SUPPORT                                      20                 VT-3    F-A      F 1.30 EG-01-R03i        EG-04-01 SHT. 1  PIPING SUPPORT                                      18                 VT-3    F-A      F 1.30 EG-01-R026        EG-01-01         PIPING SUPPORT                                      20                 VT-3    F-A      F 1.30 EG-03-R019        EG-02-03 SHT. 2  PIPING SUPPORT                                      20                         F-A      F1.30 EBG0 1-SUPPORT-i1 EG-05-06         LETDOWN HIX SUPPORT                                                    VT-3    F-A      F1.40 EBG01-SUPPORT-2   EG-05-06         LETDOWN HIX SUPPORT                                                    VT-3    F-A      F1.40 WCRE-30                                                   4.1.9 Component Cooling Water System (EG)                                              Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1ST PROGRAM PLAN TABLE EG- 3 I eid3Examinations
[System:  EG Component Name Drawing Number    Component Descrip~tion                                 Size Thickness NDE Method Cateqory Item   Relief Request    Notes EG-07-C021     EG-03-07          PIPING INTEGRAL ATTACHMENT                             12                VT-i    D-A      DI1.20 EG-01-C001     EG-01-01          PIPING INTEGRAL ATTACHMENTS                            20                VT-i1   D-A      D1.20 EG-02-1-005    EG-0l-02 SHlT. 1  PIPING SUPPORT                                         12                VT-3    F-A      F1.30 EG-1 8-H-003   EG-0 1-02 SHT. 2  PIPING SUPPORT                                         12                VT-3    F-A      FL1.30 EG-03-H-005    EG-02-03 SHlT. 2  PIPING SUPPORT                                         20                VT-3    F-A      FI.30 EG-05-C001     EG-02-05 SHlT. 1  PIPING SUPPORT                                         12                VT-3    F-A      FI.30 EG- 18-H006    EG-02-05 SHT. 1   PIPING SUPPORT                                         12                VT-3    F-A      F1.30 EG-07-C021     EG-03-07          PIPING SUPPORT                                         12                VT-3    F-A      F1.30 EG-01-C001     EG-01-01          PIPING SUPPORT                                         20                VT-3    F-A      F1.30 EG-07-R026     EG-03-07          PIPING SUPPORT                                         12                VT-3    F-A      F1.30 PEG01IA-SUP-I  EG-01-01          PUMP SUPPORT                                           IS                VT-3    F-A      F1.40 EEC0 IA-SUP-I1 EG-01-02 SHlT. 1  FUEL POOL COOLING HX SUPPORT                                             VT-3    F-A      FI.40 EEC01A-SUP-2   EU-0 1-02 SHlT. 1 FUEL POOL COOLING HX SUPPORT                                             VT-3    F-A      F1.40 EEC01 A-SUP-3  EG-01-02 SHT. 1   FUEL POOL COOLING U-X SUPPORT                                            VT-3    F-A      F1.40 WCRE-30                                                    4.1.9 Component Cooling Water System (EG)                                            Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.10 Residual Heat Removal System (&sect;EJ)
A. Applicable System Piping and Instrument Drawings
: 1. M- 12EJ0 1-Residual Heat Removal System B. Classification of Components Details of the classification of the Residual Heat Removal System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
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- 189-50EJ-01-01           Sheet 1      Residual Heat Removal "A" Train RHR Pump Suction
: 2.        M-189-50EJ-01-01            Sheet 2      Residual Heat Removal "A" Train RHR Pump Discharge
: 3.        M-1 89-50EJ-0 1-01          Sheet 3      Residual Heat Removal "A" Train RHR Pump Suction
: 4.        M-189-50EJ-01-01            Sheet 4      Residual Heat Removal "A" Train RHR Pump Discharge to Safety Injection
: 5.        M-1 89-50E J-01-01          Sheet 5      Residual Heat Removal Return to Refueling Water Storage Tank
: 6.        M- 189-50E J-01-04          Sheet 1      Residual Heat Removal "A" Train RHR Pump Suction
: 7.        M-1 89-5OEJ-02-02           Sheet 1      Residual Heat Removal "B" Train RHR Pump Suction
: 8.        M-1 89-50EJ-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-1 89-5OEJ-02-02           Sheet 4      Residual Heat Removal "B" Train RHR pump Discharge to Safety Injection
: 11.       M- 189-50EJ-02-02           Sheet 5      Residual Heat Removal "B" Train RHR Pump Discharge to Safety Injection
: 12.       M-1 89-50EJ-02-04           Sheet 1      Residual Heat Removal "B" Train RHR Pump Suction
: 13.       M-l189-50EJ-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 Discharge to Safety Injection Loop No. 2 & 3
: 15.       M-1 89-501S1-EEJ01A         Sheet 1      RHR Heat Exchanger "A" EEJO01A
: 16.       M-1 89-501SI-EEJ01B         Sheet 1      RHR Heat Exchanger "B" EEJ01B
: 17.       M-1 89-501SI-PUMPS          Sheet 1      ISI Pumps WCRE-30                           4.1.10 Residual Heat Removal System (EJ)                            Revision 0 Page 1 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.10 Residual Heat Removal System (Li)
E.      Summary of Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table 1 is a sunmmary 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 1SI 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     P1__    P__2    P.33        INTERVAL PRESSURE RETAINING               B-G-2           B7.70               --                           6      *        *      *         *See Paragraph I, BOLTING-VALVES                                                                                                                       Notes 1 & 3 VALVE BODY                   B-M-2          B 12.50              --                           6      *        *      *         *See Paragraph I, EXCEEDING NPS 4                                                                                                                      Notes 2 & 3 PRESSURE RETAINING                C-A            CI.10               --                           2      0        0      0                Note 2 VESSEL WELDS-SHELL PRESSURE RETAINING                C-A           CI1.20               --                           2      0        0      0                Note 2 VESSEL WELDS-CIRC.
PRESSURE RETAINING                C-B            C2.33               --                           4      0        0      0                Note 2 NOZZLE WELDS-VES.
VESSEL WELDED                  C-C            C3.10               --                           2      0        0      1                  1 ATTACHMENTS PIPING WELDED                  C-C            C3.20               --                         43       2        1      2                  5 ATTACHMENTS PUMP WELDED                   C-C            C3.30               --                           6      0        0      11 ATTACHMENTS VESSEL WELDED                  D-A           DI.10                --                          10      0        3      2                  5 ATTACHMENTS PIPING COMPONENTS                 F-A            FI.10--                                         13       1       2      2                  5 SUPPORTS PIPING COMPONENTS                 F-A            F1.20               --                         131      7        7      9                 23 SUPPORTS WCRE-30                                                     4.1.10 Residual Heat Removal System (EJ)                                               Revision 0 Page 2 of 14

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

==SUMMARY==
AND SCHEDULE COMPONENT OR ITEM DESCRIPTION IJCATEGORY CODE       ICODE             1 AUG. 1AUG 1TOTAL IN [ P1 ITEM NO. jCATEGORY jITEM NO. JSYSTEM EXAMS BY PERIOD & INTERVAL P2     P3        INTERVAL EQUIPMENT SUPPORTS                 F-A              F1.40              -              -20                      3     4      3              10 (OTHER TH-AN PIPING)____________
PIPING WELDS SUBJECT                R-A              R1.11                                          19         0      0      66 TO THERMAL FATIGUE                 Note 1            Note 1 PIPING WELDS NOT                 R-A              R1.20              --                         504         14     15    18             47 SUBJECT TO A DAMAGE                Note 1            Note 1 MECHANISM__                  _   _  _    __    _  _  _     _____          _____        ___       __    __
RHR MIXING TEE                                                 MRP- 192       MRP192           10         0      10     0              10 WELDS Note 1: See Section H for an explanation of Category R-A and Item R1 .XX nomenclature.
Note 2: Code Case N-706-1 is utilized for the examination of these components. These components are in the scope of STS PE-043A/STS PE-043C system leakage tests that are performed every inspection period as required by Examination Category C-H.
WCRE-30                                                       4.1.10 Residual Heat Removal System (E J)                                          Revision 0 Page 3 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.10 Residual Heat Removal System (EJ)
F. Augmented ISI Requirements The following Augmented 1S1 requirements apply to the Residual Heat Removal System:
: 1. MRP-192. Material Reliability Program: Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants- This document provides recommendations for the evaluation and inspection of locations downstream of RHR mixing tees that may be susceptible to thermal fatigue. Downstream welds within four pipe diameters of the mixing tee should be examined. MRP letter 2015-0 19 added the recommendation that the welds of the mixing tee to the upstream piping should also be examined. The WCGS Residual Heat Removal weld locations determined to be affected by this have been identified with Category = MRP-192 and Item Number         = MRPI192. These locations require a volumetric examination every 6 years. These examinations are to be performed in accordance with the recommendations of MRP- 192.
G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWB-5000, the Class 1 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.
In accordance with Section Xl, 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 Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Program A Risk Informed Inservice Inspection (RI-IST) Program has been applied to Code Class 1 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-l1, 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-1 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 through 4-4 of TR-i 12657 Rev. B-A.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table EJ-1 (Period 1 Examinations), Table EJ-2 (Period 2 Examinations), and Table EJ-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. 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 Category B-G-2, Notes 1 and 2.
: 2. Examination of the valve internal surface is required only when a valve is disassembled for maintenance or repair. The 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 method and that perform a similar function in the system. Examination may be alternatively performed on another valve within the group. Ifra valve has not been disassembled, examination is deferrable to subsequent periods. (Reference PIR 97-2539)
WCRE-30                             4.1.10 Residual Heat Removal System (E J)                              Revision 0 Page 4 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN
: 3. WCNOC procedures require that the ISI Coordinator be informed whenever a Class 1 component is disassembled for repair or maintenance and that the 1S1 Coordinator specify if a VT-i and/or VT-3 exam is required. Whenever a component is required to have a B-G-2 or B-M-2 exam performed, the 1SI Coordinator shall revise the applicable Table El-i, EJ-2, or EJ-3 and Table i to reflect the component being examined. Reference procedures AP i6A-003, ASME Section XI Repair and Replacement Program; and AI i6C-007, Work Order Planning.
: 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 Thermal Fatigue identified as the degradation mechanism.
: 6. These welds have been selected in accordance with the recommendations of MRP-192 and MRP letter 20i5-019. See Paragraph F above. The examinations of these welds are to include any/all associated long seam welds.
: 7. Weld end prep is not per MS-6 standards and there is no counter bore. Reference CCP 013539 Rev 2.
WCRE-30                   4.1.10 Residual Heat Removal System (El)                           Revision 0 Page 5 of i4

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EJ-1
[Period 1 Examinations ISystem:  EJ Relief Request or r*, ..... Cn* hl,,*b.*=                                                           C-.;-     Th;-.U,,n.*   Ni-nE hA.-hnfk   fl.,+,,,,,-
'.UllllJ.llI lll. LIdlIIU  l.JlIdWlIl* I'*IUr'IL) F
* II[U Ll, .u*SUIJ.I                                  ,uii1puiiI  [ielultiuii I'I.,L   UI~.*I.I IU  +,*~;      U V  I*II  x..l   lkI            *U+
EJ-04-A002                EJ-01-01 SHT. 4           PIPING INTEGRAL ATT'ACHMENTS                           6                               PT        C-C             C3.20 EJ-04-R008                EJ-02-04 SHT. 3           PIPING INTEGRAL ATTACHMENTS                            6                               PT        C-C             C3.20 EJ-04-C021                EJ-01-04                  PIPING SUPPORT                                         12                             VT-3       F-A             FI.10 EJ-0t -HO013              EJ-O01-01 SHIT. 3         PIPING SUPPORT                                         10                             VT-3       F-A             F 1.20 E J-01 -H0 14             EJ-01-01 SHT. 4           PIPING SUPPORT                                         10                             VT-3       F-A             F 1.20 EJ-04-A002                EJ-01-O1 SLIT. 4          PIPING SUPPORT                                         6                              VT-.3      F-A             F 1.20 EJ-04-C013                EJ-01-OI SHT. 4           PIPING SUPPORT                                         6                              VT-3       F-A             F 1.20 EJ-03-C007                EJ-02-02 SILT. 3          PIPING SUPPORT                                         8                              VT-3       F-A             F 1.20 EJ-03-RO15                E J-02-02 SHT. 3          PIPING SUPPORT                                         8                              VT-3       F-A             F 1.20 EJ-04-R008                E J-02-04 SHIT. 3         PIPING SUPPORT                                         6                              VT-3       F-A             Fl1.20 PEJ01IA-SUP-1             EJ-01-01 S1HT. 2          RHR PUMP A SUPPORT                                     8               0.322          VT-3       F-A             F1.40 PEJ01 A-SUP-2             EJ-01-0I SI-T. 2          RHR PUMP A SUPPORT                                     8               0.322          VT-3       F-A             FI.40 PEJ01 A-SUP-3             EJ-01-01 SHT. 2           RHR PUMP A SUPPORT                                     8               0.322          VT-3       F-A             Fl1.40 EJ-04-S0 16-B             E J-02-04 SI-IT. I        12" PIPE TO 12' ELBOW                                  12              1.125           UTl       R-A             R1.20       126 WCRE-30                                                                     4.1.10 Residual Heat Removal System (EJ)                                                                           Revision 0 Page 6 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL IS1 PROGRAM PLAN TABLE EJ-1 IPeriod 1 Examinations ISystem: EJ Relief Request or C'. n nnn~nmt NIknm            I*r*l^llnn   Ms imhor   C'nmnnn~n.+f lnrin+.nn, Size Thickness  NDE Method Categjory  Item  Cal Block          Notes
..... F ......................           I1 .........  ..... r ............. r .....                                                                   m   i EJ-01-FW342                    EJ-01-01 SHLT. 4        10" ELBOW TO 10" PIPE                                           10       0.365      UT     R-A        RI.20     204          4 EJ-01-FW343                    EJ-01-01 SHT. 4         10" PIPE TO 10" ELBOW                                           10       0.365      UT     R-A        RI.20     204 EJ-01-S025-B                   EJ-01-01 SHT. 5         10" PIPE TO 10" ELBOW                                           10       0.365      UT     R-A        R1.20     204 EJ-04-FW31 2                   EJ-01-01 SHT. 4        6' PIPE TO 10" X 10' X 6' TEE                                    6        0.7 19     UT     R.-A       R1.20     117 E J-01 -S025-C                 EJ-01-01 SHT. 5         10' ELBOW TO 10" PIPE                                           10       0.365      UT     R-A        R1.20     204 EJ-02-FW339                    EJ-02-02 SHT. 2         10" X 8" REDUCER TO 10" PIPE                                     10      0.365      UT     R-A        R1.20     204 EJ-02-S034-C                   EJ-02-02 SHT. 4         10" PIPE TO 10" ELBOW                                            10      0.365      UT     R-A        R1.20     204 EJ-02-S034-D                   E J-02-02 SHT. 4       10" ELBOW TO 10" PIPE                                             10    0.365        UT     R-A        R1.20     204 EJ-04-S025-B                   EJ-01-0l SHT. 4         10" X 10" X 6" TO 10" PIPE                                       10                 UT     R-A        R1.20     122 012 EJ-01-S016-B                   EJ-01-01 SHT. 3         8" PIPE TO 8" ELBOW                                                                 UT     R-A        RI.20     203 0.322 E J-01 -SO016-C                EJ-0l-01 SHT. 3         8" ELBOW TO 8" PIPE                                             8                   UT     R-A        R1.20     203 0.322 EJ-03-S003-F                   EJ-02-02 SiHT. 3        8' ELBOW TO 8" PIPE                                             8                   UT     R-A        R1.20     203 0.322 EJ-03-S003-H                   E J-02-02 SLIT. 3       8" ELBOW TO 8" PIPE                                                                 UT     R.-A       R1.20     203 WCRE-30                                                                                4.1.1l0 Residual Heat Removal System (E J)                                                  Revision 0 Page 7 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE E J-2
[Period 2 Examinations Relief Request or Cal Block         Notes Component Name     Drawing Number     Component Description                                  Size Thickness NDE Method Category Item EJ-03-R006         E J-02-02 SHT. 3   PIPING INTEGRAL ATTACHMENT                             8                  PT     C-C      C3.20 EEJ01 A-SUJPPORT-3 ISI-EEJ01A SliT. 1 SUPPORT LUG TO SHELL WELD                                                VT-1    D-A      DI.10 EEJ01 A-SUPPORT-4  ISI-EEJ01A SHT. 1 SUPPORT LUG TO SHELL WELD                                                 VT-i    D-A      DI.10 EEJ01 A-SUPPORT-5  ISI-EEJ01A SHT. 1 SUPPORT LUG TO HEAD WELD (HEAD)                                           VT-1    D-A      DI.10 EJ-04-R01 8        E J-01-04          PIPING SUPPORT                                                           VT-3    F-A      F1.10 12 EJ-04-R012         E J-02-04 SilT. 1  PIPING SUPPORT                                         12                VT-3    F-A      Fi.1 EJ-01l-H001        EJ-01-01 SLIT. 1   PIPING SUPPORT                                         14                VT-3    F-A      F1.20 EJ-01I-R029        EJ-0 1-01 SHT. 4   PIPING SUPPORT                                         10                VT-3    F-A      FI1.20 EJ-04-H002         EJ-01-01 SHAT. 4   PIPING SUPPORT                                         10                VT-3    F-A      F1.20 EJ-02-R027         E J-02-02 SHT. 2   PIPING SUPPORT                                         10                VT-3    F-A      Fl1.20 EJ-03-R005         EJ-02-02 SHT. 3    PIPING SUPPORT                                         8                 VT-3    F-A      F1.20 EJ-03-R006         EJ-02-02 SHiT. 3   PIPING SUPPORT                                         8                 VT-3    F-A      F1.20 EJ-02-R012         E J-02-04 SHT. 1   PIPING SUPPORT                                          12               VT-3    F-A      F1.20 EEJ01 A-SUPPORT-3  ISI-EEJ01A SHlT. 1 RHR H-X SUPPORT                                                          VT-3    F-A      F1.40 WCRE-30                                                       4.1.10 Residual Heat Removal System (EJ)                                                 Revision 0 Page 8 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL IS1 PROGRAM PLAN TABLE E J-2 SPeriod 2 Examinations
[System: EJ Relief Request or Size Thickness NDE Method Category Item   Cal Block          Notes Component Name    Drawing Number    Component Description EEJ01IA-SUPPORT-4 ISI-EEJ01A SHT. I RHR H-X SUPPORT                                                              VT-3    F-A      F1.40 EEJ01lA-SUPPORT-5 ISI-EEJ01A SHT. I RHR HX SUPPORT                                                               VT-3    F-A      F1.40 PEJ01IA-SUP-4     EJ-01-01 SHIT. 2  RHR PUMP A SUPPORT                                                           VT-3    F-A      F1.40 EJ-04-FO34        EJ-01-04          12" PIPE TO 12' ELBOW                                       12     1.125      UT     R-A      RI.20      126          4 EJ-02-S008-B      EJ-02-02 SHT. I   14" ELBOW TO 14" PIPE                                       14     0.438      UT     R-A      R1.20      192          4 EJ-02-FW3 17      EJ-02-04 SHT. 1   12" ELBOW TO 12" PIPE                                       12     0.375      UT     R-A      RI .20     183          4 EJ-02-S00 1-C     EJ-02-04 SHT. 1   12" PIPE TO 12" ELBOW                                       12     0.375      UT     R-A      R1.20      183          4 EJ-04-F01 9       EJ-02-04 SHT. I   12" PIPE TO 12" PIPE                                        12      0.5       UT     R-A      R1.20      128          4 EJ-0 1-SO018-B    EJ-01-01 SHiT. 3  10" X 10" X 10" TEE TO 10" PIPE                             10     0.365      UT     R-A      RI.20      204          4 EJ-0 1-SO018-C    EJI-01-O1 SHT. 3  10" PIPE TO 10" X 8" REDUCER                                10     0.365      UT     R-A      RI.20      204          4 EJ-01-S024-D      EJ-01-01 SHT. 4   10" PIPE TO 10" TEE                                          10    0.365      UT     R-A      R1.20      204          4 E J-0 1-S024-F    EJ-01-01 SHT. 4   10" TEE TO 10" PIPE                                          10    0.365      UT     R-A      R1.20      204          4 EJ-02-F050        EJ-02-02 SHIT. 5  10" PIPE TO 10" ELBOW                                        10    0.365      UT     R-A      R1.20      204           4 EJ-02-S022-B      EJ-02-02 SILT. 3  10" PIPE TO 10" X 10" X 8" TEE                               10    0.365      UT     R-A      R1.20      204           4 WCRE-30                                                         4.1.10 Residual Heat Removal System (EJ)                                                 Revision 0 Page 9 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   E J-2
[ Peiod 2Examinations SSystem: EJ Relief Request or Drawing Number   Component Description                                    Size  Thickness NDE Method Category  Item    Cal Block          Notes Component Name EJ-02-S022-D    E J-02-02 SHT. 3  10" X 10" X 8' TEE TO 10' PIPE                                     0.365     UT     R-A       RI.20       204 EJ-02-S045-B    EJ-02-02 SHT. 5   10" ELBOW TO 10" PIPE                                              0,365     UIT    R-A       R1.20       204 EJ-02-FW3 11    EJ-02-02 SirT. 3  8" PIPE TO 10" X 10" X 8" TEE                                     0.322      UT     R-A       R1.20       203 EJ-01-S0 10-B   EJ-01-01 SHT. 2   8" PIPE TO 10" X 8" EXPANDER                                      0.322      UT     k-A       R1.20       203 E J-01 -SO 17-D EJ-01-01 SET. 3  10" X 10" X 8" TEE TO 10" PIPE                                   0.365        UT     MRP-1 92 MRP1 92      204 EJ-0 1-S017-F   EJ-01-01 SHT. 3  10" PIPE TO 10" ELBOW                                            0.365        UT     MRP-1 92 MR.P192      204 EJ-0 1-S017-G   EJ-01-01 SHT. 3  10" ELBOW TO 10" PIPE                                            0.365        UT     MRP-1 92 MRIP192      204 EJ-01-S0 17-B   EJ-01-01 SHT. 3  10" PIPE TO 10" X 10" X 8" TEE                                   0.365        UT     MRP-1 92 MR.P192      204 E J-01 -F017    EJ-01-01 SHT. 3  8" PIPE TO 10" X 10" X 8" TEE                                    0.322        UIT    MRP- 192 MR.PI92      203 EJ-02-S022-D    E J-02-02 SHT. 3 10" X 10" X 8" TEE TO 10" PIPE                                   0.365        UT     MRP- 192 MRP 192      204 EJ-02-FW320     EJ-02-02 SHT. 3   10" PIPE TO 10" ELBOW                                            0.365       UT     MRP- 192 MRP192       204 EJ-02-S022-G    EJ-02-02 SHT. 3  10" ELBOW TO 10" PIPE                                            0,365        UT     MRP-1 92 MRP1 92      204 EJ-02-S022-B    EJ-02-02 SHT, 3   10" PIPE TO 10" X 10" X 8" TEE                                    0.365      UT     MRP- 192  MRP 192     204          6 EJ-02-FW311I    EJ-02-02 SHT. 3   8" PIPE TO 10" X 10" X 8" TEE                                     0.322      UT     MRP- 192  MRP 192     203          6 WCRE-30                                                       4.1.10 Residual Heat Removal System (EJ)                                                  Revision 0 Page 10 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE E J-3
[   Prio 3Examinations SSystem: EJ Relief Request or Cal Block         Notes Component Name    Drawing Number    Component Description                                 Size  Thickness NDE Method Category Item EEJ01A-S KIRT-w   ISI-EEJ01A SHT. I SUPPORT SKIRT WELD                                                        PT     C-C      C3.10 E J-0 I-C015      EJ-01-01 SHT. 3   PIPING INTEGRAL ATTACHMENTS                                               PT     C-C      C3.20 EJ-02-C012        EJ-02-02 SHT. 4   PIPING INTEGRALATTACHMENTS (8 LUGS)                   10                  PT     C-C      C3.20 PEJ01IA-SUP-I     EJ-01-01 SHIT. 2  RHR PUMP A INTEGRALLY WELDED ATT'ACHMENTS             8                   PT     C-C      C3.30 EEJ01A-SUPPORT-1  ISI-EEJ01A SHT. 1 SUPPORT LUG TO SHELL WELD                                                VT-1    D-A      DI.10 EEJ01 A-SUPPORT-2 ISI-EEJ0IA SHT. 1 SUPPORT LUG TO SHELL WELD                                                VT-i    D-A      DI.10 EJ-04-H007        E J-0 1-04        PIPING SUPPORT                                        12                 VT-3    F-A      FI.10 EJ-04-C020        E J-02-04 SHT. 1  PIPING SUPPORT                                        12                 VT-3    F-A      FI.10 E J-01l-C01 5     EJ-01-01 SHT. 3   PIPING SUPPORT                                                           VT-3    F-A      F1.20 E J-01I-R017      EJ-01-01 SHT. 1   PIPING SUPPORT                                        12                 VT-3    F-A      Ft.20 E J-01 -R019      Er-cl-cl SHT. 1   PIPING SUPPORT                                        14                 VT-3    F-A      F 1.20 EJ-02-R022        EJ-02-02 SHT. 3   PIPING SUPPORT                                        10                 VT-3    F-A      F1.20 EJ-02-C012        E J-02-02 SHT. 4  PIPING SUPPORT                                        10                 VT-3    F-A      F 1.20 EJ-04-R010        E J-02-04 SHT. 2  PIPING SUPPORT                                        6                  VT-3    F-A      F1.20 WCRE-30                                                     4.1.10 Residual Heat Re:moval System (EJ)                                                Revision 0 Page 11 o )f14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EJ-3 I eid3Examinations
[System: EJ Relief Request or Size Thickness NDE Method                 Cal Block          Notes Component Name     Drawing Number    Component Description                                                               Category Item EJ-04-C0I11        EJ-02-04 SHT. 3   PIPING SUPPORT                                            6                 VT-3    F-A      F 1.20 E J-0 1-C0 14      EJ'-01-01 SHT. 2  PIPING SUPPORT                                            10                VT-3    F-A      Ft.20 EJ-01-H006         EJ-01-01 SHT. 2   PIPING SUPPORT                                            10                VT-3    F-A      F 1.20 EEJ01A-SKIRT-w     ISI-EEJO1A SHT. 1 RHR HX SUPPORT                                                              VT-3    F-A      F1.40 EEJ01 A-SUPPORT-i1 ISI-EEJ01A SHT. 1 RHR H-X SUPPORT                                                             VT-3    F-A      F1.40 EEJ01 A-SUPPORT-2  ISI-EEJ01A SHT. 1 RI-R H-X SUPPORT                                                            VT-3    F-A      F1.40 EJ-04-F048A        EJ-01-04          12" PIPE TO VALVE HV-870 I1A                              12       1.125     UT     R-A      RI 11      126          4, 5 EJ-04-S016-G       EJ-02-04 SHT. 1   12" PIPE TO 12" ELBOW                                     12       1.125     UT     R-A      RI 11      126          4, 5 EJ-04-S0 16-H      EJ-02-04 SHT. 1   12' ELBOW TO 12" PIPE                                     12       1.125     UT     R-A      RI~ll      126          4,5 EP-0 1-MW7 152     EJ-01-01 SHT. 4   6" PIPE TO VALVE 8818A                                   6        0.719      UT     R-A      RI.I1      117          4,5,7 EP-02-MW7 162      EJ-02-04 SHT. 2   6" PIPE TO VALVE 8818C                                   6        0.719      UT     R-A      RI.II      117          4,5,7 EP-01 -MW7165      EJ-02-04 SHT. 2   6" PIPE TO VALVE 8818D                                   6        0.719      UT     R-A      RI 11      117          4,5,7 EJ-04-S014-D       EJ-02-04 SHT. 1   12" ELBOW TO 12" PIPE                                     12       1.125     UT     R-A      R1.20      126          4 E J-01 -F005       EJ-01-01 SHT. 1   14" PIPE TO 14" ELBOW                                     14      0.438      UT     R-A      R1.20      192          4 WCRE-30                                                        4.1.10 Residual Heat Removal System (EJ)                                                  Revision 0 Page 12 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EJ-3 SPeriod 3 Examinations Relief Request or Component Name Drawing Number    Component Description                                       Size Thickness NDE Method Category Item   Cal Block          Notes E J-01-FW3I111 EJ-01-01 SHT. 1   12" ELBOW TO 12" PIPE                                       12      0.375      UT     R-A      R1.20      183          4 EJ-01-FW333    EJ-01-01 SHT. 1   12" PIPE TO 12" PIPE                                        12      0.375      UT     R-A      R1.20      183          4 EJ-0I-S021-E   EJ-01-01 SHT. 2   10" PIPE TO 10' ELBOW                                       10      0.365      UT     R-A      R1.20      204          4 EJ-01 -S021 -F EJ-01-01 SHT. 2   10" ELBOW TO 10" PIPE                                       10      0.365      UT     R-A      RI.20      204          4 EJ-01-S026-E   El-0 1-01 SHlT. 5 8" PIPE TO 8" ELBOW                                         8       0.322      UT     R-A      R1.20      203          4 EJ-02-F021     E J-02-02 SHT. 2  10" TEE TO 10" PIPE                                         10      0.365      UT     R-A      R1.20      204          4 EJ-02-F031     E J-02-02 SHT. 4  10" TEE TO 10" PIPE                                         10      0.365      UT     R-A      Ri1.20     204          4 EJ-02-S0 16-H  E J-02-02 SHT. 2  10" PIPE TO 10" TEE                                         10      0.365      UT     R-A      R1.20      204          4 EJ-02-S0 16-K  E J-02-02 SilT. 2 10" TEE TO 10" PIPE                                         10      0.365      UT     R-A      R1.20      204          4 EJ-02-S023-B   EJ-02-02 SHT. 4   10" PIPE TO 10" TEE                                         10      0.365      UT     R-A      R1.20      204          4 EJ-02-S023-D   EJ-02-02 SHT. 4   10" TEE TO 10" PIPE                                         10      0.365      UIT    R-A      RI.20      204          4 EJ-04-F043     EJ-01-01 SHlT. 4  10" PIPE TO 10" X 10" X6" TEE                               10       1.00      UT     R-A      R1.20      122          4 EJ-04-FW91I0A  EJ-02-04 SHlT. 2  10" PIPE TO 10" X 10" X 6" TEE                              10       1.00      UT     R-A      R1.20      122          4 EJ-04-SO01-D   EJ-02-04 SHlT. 2  10" ELBOW TO 10" PIPE                                       10       1.00      UT     R-A      R1.20      122          4 WCRE-30                                                      4.1.10 Residual Heat Removal System (EJ)                                                  Revision 0 Page 13 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE E J-3
[System: EJ Relief Request or Size   Thickness NDE Method Category  Item   Cal Block          Notes Component Name   Drawing Number    Component Description EJ-04-S00I-G     EJ-02-04 SHT. 2   10" X 10' X 6" TEE TO 10" PIPE                          10        1.00      UT     R-A       R1.20      122 EJ-04-FW371      EJ-02-04 SILT. 2  10" X10" X6" TEE TO 6" PIPE                            6         0.7 19     UT     R-A       RI.20      117          4 E J-01-S017-D   EJ-01-01 SHlT. 3  10OX 10" X8" TEE TO 10" PIPE                            10      0.365        UT     MRP- 192 MR.PI92     204          6 E J-0 1-SO 17-F EJ-0I-01 SHT. 3   10" PIPE TO 10" ELBOW                                   10      0.365        UT     MRP-1 92 MRP 192     204          6 EJ-01-S017-G    EJ-01-0I SilT. 3  10" ELBOW TO 10" PIPE                                   10      0.365        UIT    MRP-1 92 MRP192      204          6 EJ-02-S022-D    EJ-02-02 SHT. 3   10" X10" X8" TEE TO 10"PIPE                             10      0.365        UT     MRP-1 92 MRPI92      204          6 EJ-02-FW320     EJ-02-02 SHlT. 3  10" PIPE TO 10" ELBOW                                   10      0.3 65       UT     MRP-1 92 MRP192      204          6 EJ-02-S022-G    EJ-02-02 SHlT. 3  10" ELBOW TO 10" PIPE                                   10      0.365        UT     MRP-1 92 MRP192      204          6 WCRiE-30                                                      4.1.10 Residual Heat Removal System (EJ)                                                 Revision 0 Page 14 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.11 High Pressure Coolant Injection System (EM~)
A.      Applicable System Piping and Instrument Drawings
: 1. M-l2EM01-High Pressure Coolant Injection System
: 2. M-12EM02-High Pressure Coolant Injection System*
* Except for ASME Class 2 components listed in Section 4.3 B.      Classification of Components Details of the classification of the High Pressure Coolant Injection System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
Note: for purposes of determining which EM system components are exempt based on size (i.e, NPS 4 inch vs NPS 11/2'/  inch for High Pressure Safety Injection systems), the pumps in the EM system, PEM01A and PEM01B, are defined as Intermediate Pressure Safety Injection Pumps (reference USAR Table 6.2.1-3). Thus, the NPS 4 inch exemption is applied. The Centrifugal Charging Pumps (CCPs), PBG05A 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 11/2'/   inch exemption rule. See the ISI Classification Basis Document for definition of which lines fall under each exemption.
D. Applicable ISI 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-189-50 series.
: 1.      M-189-50EM-01-01        Sheet 1        High Pressure Coolant Injection Safety Injection Pump "A" Suction
: 2.      M-189-50EM-02-01        Sheet 1        High Pressure Coolant Injection Safety Injection Pump "B" Discharge
: 3.      M-189-50EM-03-05        Sheet 1        High Pressure Coolant Injection Safety Injection Pumps to RH-R System
: 4.      M-189-50EM-04-03        Sheet 1        High Pressure Coolant Injection Safety Injection Pumps to RCS
: 5.      M-189-50EM-05-01        Sheet 1        High Pressure Coolant Injection Safety Injection Pump Suction Cross Tie
: 6.      M-189-50EM-05-01        Sheet 2        High Pressure Coolant Injection Safety Injection Pump Suction Cross Tie to CVCS
: 7.      M-189-50EM-06-02        Sheet 1        High Pressure Coolant Injection HPSI Discharge to RCS
: 8.      M-189-50EM-06-02        Sheet 2        High Pressure Coolant Injection HPSI Discharge to RCS
: 9.      M-189-50EM-06-03        Sheet 1        High Pressure Coolant Injection HPSI Discharge to RCS
: 10. M-189-50ISI-PUMPS Sheet 1              ISI Pumps WCRE-30                   4.1.11 High Pressure Coolant Injection System (EM)                                  Revision 0 Page 1 of 11

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1S1 PROGRAM PLAN 4.1.11 High Pressure Coolant Injection System (EMI)
E. Summary of 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 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       P1_!  P.2   P__3       INTERVAL PRESSURE RETAINING           B-G-2            B7.50               --                             4         *      *    *        *See Paragraph I, BOLTING-PIPING                                                                                                                 Notes 1 & 4 PRESSURE RETAINING           B-G-2            B7.70               --                             4*               *    *        *See Paragraph I, BOLTING-VALVES                                                                                                                  Notes 2 & 4 VALVE BODY              B-M-2            B 12.50             --                             4*                *   *        *See Paragraph I, EXCEEDING NPS 4                                                                                                                 Notes 3 & 4 PRESSURE RETAINING            C-A             C1.20                --                            20               0    22 VESSEL WELDS-CIRC.
PRESSURE RETAINING            C-B             C2.21                --                            20                1   12 NOZZLE-SHELL WELD VESSEL WELDED              C-C              C3.10               --                            4         0       1   0                 1 AT1TACHMENTS PIPING WELDED              C-C             C3.20               --                            24         1       1   1                3 ATITACHMENTS PIPING COMPONENTS             F-A             FI. 10              --                            76         7      6    7               20 SUPPORTS PIPING COMPONENTS             F-A             FI.20               --                            83         4      5    5                14 SUPPORTS WCRE-30                                                  4.1.11 High Pressure Coolant Injection System (EM)                                  Revision 0 Page 2 of 11

WOLF CREEK GENERATING STATION FOURTH 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]_  P_.2  P.33     INTERVAL EQUIPMENT SUPPORTS                                                                                                                    4 (OTHER THAN PIPING)
PIPING WELDS SUBJECT                                                                                                                   0 TO THERMAL FATIGUE PIPING WELDS SUBJECT                                                                                                                   2 TO IGSCC or TGSCC PIPING WELDS NOT                                                                                                                     3 SUBJECT TO A DAMAGE MECHANISM Note 1: See Section H for an explanation of Category R-A and Item R1.XX nomenclature.
WCRE-30                                                   4.1.11 High Pressure Coolant Injection System (EM)                               Revision 0 Page 3 of 11

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.11 High Pressure Coolant Injection System (EM)
F. Augmented 1SI Requirements No Augmented 1S1 requirements apply to the High Pressure Coolant Injection System.
G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWB-5000, the Class 1 pressure retaining components within the High Pressure Coolant Injection System will receive a system leakage test per IWB-5220 prior to plant startup following each refueling outage.
In accordance with Section XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining components within the High Pressure Coolant Injection System will receive a system leakage test per IWC-5 220 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 1 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-1 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 through 4-4 of TR-1 12657 Rev. B-A.
Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table EM-i (Period 1 Examinations), 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 Category B-G-2, Notes 1 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 ofbolted connection is required only once during the interval. See Category B-G-2, Notes 1 and 2.
: 3. Examination of the valve internal surface is required only when a valve is disassembled for maintenance or repair. The 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 that perform 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-30                           4.1.11 High Pressure Coolant Injection System (EM)                      Revision 0 Page 4 ofl11

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN
: 4. WCNOC procedures require that the IS1 Coordinator be informed whenever a Class 1 component is disassembled for repair or maintenance and that the ISI Coordinator specify' if a VT-1 and/or VT-3 exam is required. Whenever a component is required to have a B-G-2 or B-M-2 exam performed, the 1SI Coordinator shall revise the applicable Table EM-i, EM-2, or EM-3 and Table i to reflect the component being examined. Reference procedures AP 16A-003, ASME Section XI Repair and Replacement Program; and Al 16C-007, Work Order Planning.
: 5. These welds have been selected per the RM-SI Program. The requirements for examination of these welds are included in Paragraph H above.
: 6. These welds have IGSCC identified as the degradation mechanism.
WCRE-30                    4.1.11 High Pressure Coolant Injection System (EM)                Revision 0 Page 5 of ii

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE    EM-I ISystem: EM Relief Request or Cal Block         Notes Component Name    Drawing Number   Component Description                                   Size  Thickness   NDE Method Category Item EM-01-A003        EM-05-01 SHT. I  PIPING INTEGRAL ATTACHMENTS                             6                     PT     C-C      C3.20 EM-05-R001        EM-03-05         PIPING SUPPORT                                          6                    VT-3    F-A      Fl.10 EM-03-C012        EM-04-03         PIPING SUPPORT                                          6                    VT-3    F-A      FI.10 EM-03-C013        EM-04-03         PIPING SUPPORT                                          6                    VT-3    F-A      FI.10 EM-03-A005        EM-06-03         PIPING SUPPORT                                          1.5                  VT-3    F-A      Fl.10 EM-03-C033        EM-06-03         PIPING SUPPORT                                          1.5                  VT-3    F-A      Fl. 10 EM-03-R01 5       EM-06-03         PIPING SUPPORT                                          1.5                  VT-3    F-A      FI.10 EM-03-R01 8       EM-06-03         PIPING SUPPORT                                          1.5                  VT-3    F-A      FI,1 EM-0Ol-H015       EM-02-01         PIPING SUPPORT                                          8                    VT-3    F-A      F 1.20 EM-01l-A003       EM-05-0l SHT. 1  PIPING SUPPORT                                          6                    VT-3    F-A      F1.20 EM-01-C016        EM-05-0 1 SHT. 2 PIPING SUPPORT                                          6                    VT-3    F-A      F1,20 EM-02-R005        EM-06-02 SHT. 2  PIPING SUPPORT                                          3                    VT-3    F-A      F 1.20 TEM0 1-SUPPORT-i1 EM-06-02 SHT. 2  B.I.T. TANK SUPPORT                                                          VT-3    F-A      F1.40 WCRE-30                                                   4.1.11 High Pressure Coolant Injection System (EM)                                           Revision 0 Page 6 of 11

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EM-I I eid1Examinations Ssystem: EM Relief Request or Component Name                                                                                                     Category Item  Cal Bloc      ck   Notes Drawing Number Component Description                                    Size Thickness   NDE Method EM-05-S005-B   EM-03-05       6" PIPE TO 6" ELBOW                                      6       0.719        UT     R-A      RI.20     117              5 EM-05-S005-C   EM-03-05       6" ELBOW TO 6" PIPE                                       6      0.719        UT     R-A      R1.20     117              5 WCRE-30                                              4.1.11 High Pressure Coolant Injection System (EM)                                           Revision 0 Page 7 of l11

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EM-2 I   erod2Examinations I
[System:  EM Relief Request or Size   Thickness  NDE Method          Item  Cal Block          Notes Component Name  Drawing Number  Component Description                                                               Category TEM0 1--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-06-02 SHT. 2 VESSEL INTEGRAL ATTACHMENTS                                                  PT     C-C      C3.10 EM-02-R010      EM-06-02 SHT. l PIPING INTEGRAL ATTACHMENTS                            4                     PT     C-C      C3.20 EM-05-C008      EM-03-05        PIPING SUPPORT                                         2                    VT-3    F-A      FI.10 EM-05-R004      EM-03-05        P]PING SUPPORT                                         2                    VT-3    F-A      FI.10 EM-03-C008      EM-06-03        PIPING SUPPORT                                         3                    VT-3    F-A      FI.10 EM-03-C035      EM-06-03        PIPING SUPPORT                                         1.5                  VT-3    F-A      FI.10 EM-03-C047      EM-06-03        PIPING SUPPORT                                         1.5                  VT-3    F-A      FI.I EM-03-R01 6     EM-06-03        PIPING SUPPORT                                         1.5                  VT-3    F-A      FI.10 WCRjE-30                                              4.1.11 High Pressure Coolant Injection System (EM)                                          Revision 0 Page 8 of 11

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EM-2 IPeriod 2 Examinations ISystem: EM Relief Request or Size Thickness   NDE Method          Item   Cal Block          Notes Component Name   Drawing Number   Component Description                                                                Category EM-01-C044       EM-01-01         PIPING SUPPORT                                           8                   VT-3    F-A      F1.20 EM-01-C017       EM-05-01 SHT. l  PIPING SUPPORT                                           6                   VT-3    F-A      F 1.20 EM-01-H003       EM-05-01 SHT. 1  PIPING SUPPORT                                           6                   VT-3    F-A      F 1.20 EM-01-H016       EM-05-01 SHT. 1  PIPING SUPPORT                                          6                    VT-3    F-A      F1.20 EM-02-RO1O       EM-06-02 SiLT. 1 PIPING SUPPORT                                          4                    VT-3    F-A      FI.20 TEM01 -SUPPORT-2 EM-06-02 SlT. 2  B.I.T. TANK SUPPORT                                                          VT-3    F-A      FI.40 TEM01-SUPPORT-3  EM-06-02 SHT. 2  B.I.T. TANK SUPPORT                                                          VT-3    F-A      F1.40 EM-03-S01 5-B    EM-04-03         6" PIPE TO 6" ELBOW                                     6        0.719        UT     R-A      R1.20      117          5 WCRE-30                                                  4.1.11 High Pressure Coolant Injection System (EM)                                           Revision 0 Page 9 of 11

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EM-3 SSystem:  EM Relief Request or Size    Thickness  NDE Method           Item  Cal Block         Notes Component Name  Drawing Number  Component Description                                                               Category EM-02-H002      EM-06-02 SHT. 2 PIPING INTEGRAL ATTACHMENTS                           4                      PT     C-C      C3.20 TEM01-SEAM-2-W  EM-O6-O2 SHT. 2 TOP HEAD TO SHELL WELD                                NA           2.00      UT     C-A      C 1.20     144 TEM01 -SEAM-3-W EM-06-02 SHT. 2 BOFIqOM HEAD TO SHELL WELD                            NA           2.00      UT     C-A      C 1.20     144 TEM01 - W       EM-06-02 SHT. 2 OUTLET NOZZLE TO TOP HEAD WELD                        NA           2.00     UT/PT   C-B      C2.21      144 EM-05-R002      EM-03-05        PIPING SUPPORT                                                              VT-3    F-A      F1.1 EM-03-C016      EM-04-03        PIPING SUPPORT                                        2                     VT-3    F-A      FI.1 EM-03-HO04      EM-O4-03        PIPING SUPPORT                                        6                     VT-3    F-A      FI.1 EM-03-RO05      EM-04-03        PIPING SUPPORT                                        6                     VT-3    F-A      FI.10 EM-03-RO08      EM-04-03        PIPING SUPPORT                                        2                     VT-3    F-A      FI.1 EM-03-CO29      EM-06-03        PIPING SUPPORT                                         1.5                  VT-3    F-A      FI.10 EM-O3-CO34      EM-C6-O3        PIPING SUPPORT                                         1.5                  VT-3    F-A      FlICI EM-0 1-CO015    EM-05-01 SHT. 1 PIPING SUPPORT                                        6                     VT-3    F-A      F 1.20 EM-01-CO36      EM-O5-01 SHT. I PIPING SUPPORT                                        6                     VTr-3   F-A      FI1.20 WCRE-30                                               4.1.11 High Pressure Coolant Injection System (EM)                                           Revision 0 Page 10 ofll1

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EM-3 SSse:EM Relief Request or Component Name  Drawing Number   Component Description                                 Size   Thickness   NDE &#xa3;Method Category Item   Cal Block         Notes 3
EMv-32-R007     EMv-06-02 SriT.i rlr*ltG SUPPRT.Jr                                     4                      V?-     F-A      P1.23 EM-02-R01 1     EM-06-02 SHT. 1  PIPING SUPPORT                                        4                      VT-3    F-A      F1 .20 EM-02-H002      EM-06-02 SHT. 2  PIPING SUPPORT                                        4                      VT-3    F-A      F 1.20 TEM01-SUPPORT-4 EM-06-02 SHT. 2  B.I.T. TANK SUPPORT                                                          VT-3    F-A      F 1.40 EM-03-S01 1-F   EM-04-03         6" PIPE TO 6" ELBOW                                   6                       UT     R-A      RI.16      117 0.7 19                                                5,6 EM-03-S01 1-G   EM-04-03         6" ELBOW TO 6" PIPE                                   6         0.7 19        UT     R-A      Ri. 16     117          5, 6 WCRE-30                                                4.1.11 High Pressure Coolant Injection System (EM)                                            Revision 0 Page 11 of 11

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.12 Containment Spray System (EN)
A. Applicable System Piping and Instrument Drawings
: 1. M- 12EN0 1-Containment Spray System B. Classification of Components Details of the classification of the Containment Spray System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
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-01-01          Sheet 1 Containment Spray "A" Train Pump  Suction
: 2.       M- 189-50EN-01-01          Sheet 2 Containment Spray "A" Train Pump Discharge
: 3.       M-189-50EN-01-01           Sheet 3 Containment Spray "A" Train Pump Bypass
: 4.       M-1 89-50EN-02-02          Sheet 1 Containment Spray "B" Train Pump Suction
: 5.       M-1 89-50EN-02-02          Sheet 2 Containment Spray "B" Train Pump Discharge
: 6.       M-1 89-50EN-02-02          Sheet 3 Containment Spray "B" Train Pump Bypass
: 7.       M-1 89-50ISI-PUMPS         Sheet 1 ISI Pumps WCRE-30                   4.1.12 Containment Spray System (EN)                                     Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.12 Containment Spray System (EN)
E.      Summary of Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table 1 is a sumimary 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       P1. P__2     P__3        INTERVAL PIPING WELDED                 C-C             C3.20              --                          7          1     0       1                 2 ATTACHMENTS PUMP WELDED                  C-C             C3.30                              -60                          0       11 ATTACHMENTS PIPING                   F-A             F1.20              --                          24         3     1       26 SUPPORTS SUPPORTS OTHER THAN                F-A             F1.40--63                                                       0       03 PIPING SUPPORTS PIPING WELDS NOT                 R-A             R1.20              --                         137         0     0       00 SUBJECT TO A DAMAGE MECHANISM.                 Note 1           Note 1 Note 1: See Section H for an explanation of Category R-A and Item R1 .XX nomenclature.
WCRE-30                                                      4.1.12 Containment Spray System (EN)                                              Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.12 Containment Spray System (EN)
F. Augmented ISI Requirements No Augmented IS1 requirements apply to the Containment Spray System.
G. 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-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 1 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-578-1 .No welds in the Containment Spray System were selected for examination in the RI-ISI program.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table EN- 1 (Period 1 Examinations), Table EN-2 (Period 2 Examinations),
and Table EN-3 (Period 3 Examinations).
WCRE-30                    4.1.12 Containment Spray System (EN)                             Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EN-I IPeriod 1 Examinations
[System:  EN Relief Request or Item   Cal Block         Notes Component Name Drawing Number   Component                                           Size Thickness NDE Method Category EN-01I-A003    EN-01-01 SHiT. 3 PIPING INTEGRAL ATTACHMENTS                         6                  PT     C-C      C3.20 EN-02-H005     EN-02-02 SHIT. 2 PIPING SUPPORT                                       10               VT-3    F-A      F 1.20 EN-0OI-A003    EN-01-01 SHiT. 3 PIPING SUPPORT                                      6                 VT-3    F-A      F1.20 EN-01-C005     EN-01-01 SHT. 2  PIPING SUPPORT                                       10               VT-3    F-A      F 1.20 PEN01lA-SUP-I  EN-01-01 SIIT. 1 CONTAINMENT SPRAY "A" PUMP SUPPORT                   12               VT-3    F-A      F1.40 PEN01 A-SUP-2  EN-01-01 SliT. 1 CONTAINMENT SPRAY "A" PUMP SUPPORT                   12               VT-3    F-A      F1.40 PEN01A-SUP-3   EN-O1-01 SLIT. 1 CONTAINMENT SPRAY "A" PUMP SUPPORT                   12               VT-3    F-A      FI1.40 WCRE-30                                                  4.1.12 Containment Spray System (EN)                                                Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EN-2 SPeriod 2 Examinations SSystem:   EN 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               VT-3    F-A      Fl1.20 WCRE-30                                           4.1.12 Containment Spray System (EN)                                                Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EN-3
[Sse  EN Relief Request or Item   Cal Block         Notes Component Name Drawing Number   Component                                          Size Thickness NDE Method Category EN-02-R007     EN-02-02 SHlT. 2 PIPING INTEGRAL ATTACHMENTS                        10                 PT     C-C      C3.20 PEN01lA-SUP-I  EN-01-01 SHT. l  CS PUMP A INTEGRALLY WELDED ATTACHMENTS            12                 PT     C-c      C3.30 EN-01-R008     EN-0l-0l SLIT. 1 PIPING SUPPORT                                     12                VT-3    F-A      FI.20 EN-02-R007     EN-02-02 SHT. 2  PIPING SUPPORT                                     10                VT-3    F-A      F 1.20 WCRE-30                                                  4.1.12 Containment Spray System (EN)                                               Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.13 Accumulator Safety Injection System (EP)
A. Applicable System Piping and Instrument Drawings
: 1. M- 12EP0 1-Accumulator Safety Injection System B. Classification of Components Details of the classification of the Accumulator Safety Injection System components for ISI are in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
C. Nonexempt and Exempt ASME Class Components A listing of Nonexempt and Exempt ASME Class components is included in "Inservice Inspection Classification Basis Doctument Wolf Creek Generating Station Interval 4".
D. Applicable IST Isometrics and 1SI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Accumulator Safety Injection System. These drawings are part of the M-189-50 series.
: 1.       M-189-50EP-01-O1             Sheet 1         Accumulator   Safety Injection  Loop 1
: 2.       M-189-5OEP-02-02             Sheet 1         Accumulator   Safety Injection  Loop 2
: 3.       M-1 89-50EP-03-02            Sheet 1         Accumulator   Safety Inj ection Loop 3
: 4.       M-189-50EP-04-0l             Sheet 1         Accumulator   Safety Injection  Loop 4 WCRE-30                   4.1.13 Accumulator Safety Injection System (EP)                                Revision 0 Page 1 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI 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 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 1S1 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      P1  P2     P3         INTERVAL PRESSURE RETAINING                B-G-2           B7.50               -               -2                      *    *      *       *See Paragraph I, BOLTING-PIPING                                                                                                                    Notes 1 & 4 PRESSURE RETAINING                B-G-2            B7.70              --                            12        *    *     *        *See Paragraph I, BOLTING-VALVES                                                                                                                     Notes 2 &4 VALVE BODY                    B-M-2           B 12.50             --                            12        *   *      *        *See Paragraph I, EXCEEDING NPS 4                                                                                                                    Notes 3 & 4 PIPING COMPONENT                   F-A            Fi.l 0             -                            29         3   2      4                9 SUPPORTS PIPING WELDS SUBJECT                 R-A "          Rl.16              --                            12        0   0      22 TO IGSCC OR TGSCC                Note 1          Note 1 PIPING WELDS NOT                   R-A            RI.20              --                           109        0   2      02
 'SUBJECT TO A DAMAGE                Note 1          Note 1 MECHANISM Note 1: See Section H for an explanation of Category R-A and Item R1 .XX nomenclature.
WCRE-30                                                         4.1.13 Accumulator Safety Injection System (EP)                                    Revision 0 Page 2 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.13 Accumulator Safety Injection System (EP)
F.      Augmented 1SI 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 1 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.
In accordance 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 1 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 fr'om Code Case N-578-1l 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-1 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 through 4-4 of TR-112657 Rev. B-A.
I. Components and Component Supports Selected/Schleduled For Examination The components and component supports selected for examination during Interval 4 are included in Table EP-1 (Period 1 Examinations), Table EP-2 (Period 2 Examinations),
and Table EP-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 Category B-G-2, Notes 1 and 3.
: 2. Examination of Pressure Retaining Bolting is performed in accordance with Category B-G-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 Category B-G-2, Notes 1 and 2.
: 3. Examination of the valve internal surface is required only when a valve is disassembled for maintenance or repair. The 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 that perform 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-30                 4.1.13 Accumulator Safety Injection System (EP)                           Revision 0 Page 3 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN
: 4. WCNOC procedures require that the ISI Coordinator be informed whenever a Class 1 component is disassembled for repair or maintenance and that the ISI Coordinator specify if a VT-i and/or VT-3 exam is required. Whenever a component is required to have a B-G-2 or B-M-2 exam performed, the ISI Coordinator shall revise the applicable Table EP-1, EP-2, or EP-3 and Table i to reflect the component being examined. Reference procedures AP 16A-003, ASME Section Xl Repair and Replacement Program; and Al 16C-007, Work Order Planning
: 5. These welds have been selected per the RI-ISI Program. The requirement for examination of these welds is given in Paragraph H above.
: 6. These welds have IGSCC identified as the degradation mechanism.
WCRE-30 4.1.13 Accumulator Safety Injection System (EP)                       Revision 0 Page 4 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EP-I SPeriod 1 Examinations
[System:   EP Relief Request or Cal Block         Notes Component Name Drawing Number Component Description                                 Size  Thickness  NDE Method Category item EP-02-H006     EP-02-02       PIPING SUPPORT                                        10                  VT-3    F-A      FI.10 EP-0I-H006     EP-04-0 1      PIPING SUPPORT                                        2                   VT-3    F-A      FI.10 EP-0I1-R008    EP-04-0 t      PIPING SUPPORT                                        2                   VT-3    F-A      FI.I WCRE-30                                              4.1.13 Accumulator Safety Injection System (EP)                                           Revision 0 Page 5 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE EP-2
[System:  EP Relief Request or Size   Thickness  NDE Method          Item  Cal Block         Notes Component Name Drawing Number Component Description                                                              Category EP-01I-1004    EP-04-01       PIPING SUPPORT                                        10                   VT-3    F-A      FI.10
*EP-0 l-R005    EP-04-01       PIPING SUPPORT                                        10                   VT-3    F-A      FI.10 EP-l0 -S004-C  EP-0 I-01      10" PIPE TO 10" ELBOW                                 10                    UT     R-A      R1.20    122            5 EP-01-S004-D   EP-01-01       10" ELBOW TO 10" PIPE                                 10                    UT     R-A      RI.20    122            5 WCRE-30                                               4.1.13 Accumulator Safety Injection System (EP)                                           Revision 0 Page 6 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EP-3 SSystem:  EP Relief Request or Cal Block         Notes Component Name Drawing Number Component Description                                Size   Thickness  NDE Method Category Item EP-01-R013     EP-01-0Ol      PIPING SUPPORT                                       10                   VT-3    F-A      FI.10 EP-0 1-C004    EP-04-01       PIPING SUPPORT                                       2                    VT-3    F-A EP-0Ol-RO01    EP-04-O01      PIPING SUPPORT                                       6                    VT-3    F-A      FI.10 EP-0 1-HO010   EP-01-01       PIPING SUPPORT                                       6                    VT-3    F-A      FI.10 EP-0 1-S003-K  EP-01-01       10" PIPE TO 10" ELBOW                                10                    UT     R-A      Rl.16     122          5, 6 EP-01 -S003-L  EP-01-01       10" ELBOW TO 10" PIPE                                10          1         UT     R-A      Rl.16     122          5, 6 WCRE-30                                              4.1.13 Accumulator Safety Injection System (EP)                                           Revision 0 Page 7 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.14 Auxiliary Feedwater Pump Turbine System (FC)
A. Applicable System Piping and Instrument Drawings
: 1. M-12FC02-Auxiliary Feedwater Pump Turbine System B. Classification of Components Details of the classification of the Auxiliary Feedwater Pump System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
D. Applicable ISI Isometrics and ISI 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 1    Auxiliary Turbines Auxiliary Feedwater Pump Turbine Steam Supply Piping WCRE-30            4.1.14 Auxiliary Feedwater Pump Turbine System (FC)                                  Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.14 Auxiliary Feedwater Pump Turbine System (FC)
E. Summary of 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 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      P_.1   P__2     P_3       INTERVAL PIPING WELDS SUBJECT               --                            USAR           3.6.2           17        2        1      25 TO HELB REQUIREMENTS            __  _     _  _   __    _  _ _     __  _  _  _    __  _   _ _  _   _ _  _ _ _  _   _  _   _ _   _ _ _ _   _   _   _   _  _ _
WCRE-30                                       4.1.14 Auxiliary Feedwater Pump Turbine System (FC)                                              Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.14 Auxiliary Feedwater Pump Turbine System (FC)
F. Augmented ISI Requirements The following Augmented 1S1 requirements apply to the Auxiliary Feedwater Pump System:
: 1. WCGS USAR Sections 3.6.1, Postulated Pipin* 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 Pipine- 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-33 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-1 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 Figure 4-1 through 4-4 of TR-1 12657 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.
Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table FC-1 (Period 1 Examinations), Table FC-2 (Period 2 Examinations),
and Table FC-3 (Period 3 Examinations).
WCRE-30             4.1.14 Auxiliary Feedwater Pump Turbine System (FC)                       Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE FC-1 SPeriod 1 Examinations
[System:   FC Relief Request or Component Name Drawing Number Component Description                                   Size Thickness NDE Method Category Item Cal Block         Notes FC-01-F022     FC-01-0[       VALVE V001 TO 4" PIPE                                   4       0.337      UT     USAR     3.6.2     159 FC-0I-F023     FC-01-01       4" PIPE TO VALVE V024                                   4       0.337      UT     USAR     3.6.2     159 WCRE-30                                      4.1.14 Auxiliary Feedwater Pump Turbine System (FC)                                            Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE FC-2 I eid2Examinations
[System:  FC Relief Request or Component Name Drawing Number Component Description                                    Size   Thickness NDE Method Category Item  Cal Block         Notes FC-01-S02 1-C  FC-01-01       4" PIPE TO 4" ELBOW                                           40.337          UT     USAR     3.6.2     159 WCRE-30                                        4.1.14 Auxiliary Feedwater Pump Turbine System (FC)                                              Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE FC-3
[System:  FC Relief Request or Component Name Drawing Number Component Description                                 Size  Thickness NDE Method Category Item  Cal Block         Notes FC-0l-F026     FC-01-01       4" PIPE TO VALVE V002                                 4        0.337      UT     USAR     3.6.2     159 FC-0]-F027      FC-01-0I       VALVE V025 TO 4" PIPE                                 4        0.337      UT     USAR     3.6.2     159 WCRE-30                                              Auxiliary Feedwater Pump Turbine System (FC)
WCRE-304.1.14                                                                                  Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.15 Containment Cooling System (GN)
A. Applicable System Piping and Instrument Drawings
: 1. M- 12GN0 1-Containment Cooling System B. Classification of Components Details of the classification of the Containment Cooling System components for 1SI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
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-01-01            Sheet 1          Containment Cooling System  "A" Train Supply
: 2.       M-189-50GN-01-01            Sheet 2          Containment Cooling System  "A" Train Return
: 3.       M-189-50GN-01-01            Sheet 3          Containment Cooling System  "A" Train Cooler "A" Supply and Return Headers
: 4.       M-189-50GN-01-01            Sheet 4          Containment Cooling System  "A" Train Cooler "C" Supply and Return Headers
: 5.       M-1 89-50GN-02-02           Sheet 1          Containment Cooling System  "B" Train Supply
: 6.       M-1 89-50GN-02-02           Sheet 2          Containment Cooling System  "B" Train Return
: 7.       M-1 89-50GN-02-02           Sheet 3          Containment Cooling System  "B" Train Cooler "B" Supply and Return Headers
: 8.       M-1 89-50GN-02-02           Sheet 4          Containment Cooling System  "B" Train Cooler "D" Supply and Return Headers WCRE-30                4.1.15 Containment Cooling System (GN)                                  Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH 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 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 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        P1_   P2       P__3       INTERVAL PIPING WELDED              D-A             D1.20               --                        41           1     2       2                 5 ATT[ACHMENTS PIPING COMPONENT             F-A             F1.30               --                        112         4      3       7                14 SUPPORTS WCRE-30                                                4.1.15 Containment Cooling System (GN)                                              Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.15 Containment Cooling System (GN)
F. Augmented 1S1 Requirements No Augmented ISI requirements apply to the Containment Cooling System.
G. System Pressure Testing In accordance with Section XI, JWA-5000 and IWD-5000, the Class 3 pressure retaining components within the Containment Cooling System will receive a system leakage test per IWD-5220 every 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 Containment Cooling System.
Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table GN-1 (Period 1 Examinations), Table GN-2 (Period 2 Examinations),
and Table GN-3 (Period 3 Examinations).
WCRE-30                4.1.15 Containment Cooling System (GN)                           Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE GN-1 I eid1Examinations SSystem: GN Component Name Drawing Number   Component Description                                  Size Thickness NDE Method Category Item   Relief Request    Notes GN-01-C017     GN-0 1-01 SHT. 2 PIPING INTEGRAL ATTACHMENTS                             14               VT-i    D-A      D1.20 GN-0l-C003     GN-01-01 SHT. 1  PIPING- SUPPORT                                        14                VT-3    F-A      F 1.30 GN-O1-C01!7    GN-01-01 SHT. 2  PIPING SUPPORT                                         14                VT-3    F-A      F 1.30 GN-02-H001     GN-02-02 SHT. 2  PIPING SUPPORT                                         10                VT-3    F-A      FI.30 M-620-003-24   GN-02-02 SHT. 4  PIPING SUPPORT                                        6                  VT-3    F-A      FI.30 WCRE-30                                                 4.1.15 Containment Cooling System (GN)                                                 Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE GN-2 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                        8                    VT-i    D-A      D1.20 M-620-003- l 0 GN-0I-0I SHT. 3  PIPING INTEGRAL ATTACHMENTS                        8 "VT-I                      D-A      D1.20 M-620-003-09   GN-0I1-01 SHT. 3 PIPING SUPPORT                                     8                    VT-3    F-A      F1.30 M-620-003-1 0  UN-O1-O1 SHT. 3  PIPING SUPPORT                                      8                   VT-3    F-A      F 1.30 GN-02-C006     GN-02-02 SHT. 1  PIPING SUPPORT                                      10                  VT-3    F-A      F1.30 WCRE-30                                                 4.1.15 Containment Cooling System (GN)                                                 Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE GN-3 IPeriod 3 Examinations ISystem:   GN Component Description                                 Size Thickness NDE Method Category item   Relief Request     Notes Component Name Drawing Number M-620-003-1 3  GN-01 -01 SHT. 3 PIPING INTEGRAL ATTACHMENTS                           6                 VT-i    D-A      D1.20 M-620-003-14   GN-01-0 1 SHT. 3 PIPING INTEGRAL ATTACHMENTS                           6                 VT-I    D-A      D1.20 GN-01l-C016    GN-01-01 SHT. I  PIPING SUPPORT                                         14               VT-3    F-A      F 1.30 M-620-003-1 3  GN-01-01 SHT. 3  PIPING SUPPORT                                         6                VT-3    F-A      F 1.30 M-620-003-I4   GN-01-0 1 SHT. 3 PIPING SUPPORT                                        6                 VT-3    F-A      F1.30 GN-02-C026     GN-02-02 SIHT. 1 PIPING SUPPORT                                         10               VT-3    F-A      F 1.30 GN-01 -R001    GN-01-01 SHT. 1  PIPING SUPPORT                                         14               VT-3    F-A      F 1.30 GN-0 l-R005    GN-01-01 SHT. 2  PIPING SUPPORT                                         14               VT-3    F-A      F 1.30 GN-0 l-R008    GN-02-02 SHIT. 1 PIPING SUPPORT                                         10               VT-3    F-A      F 1.30 WCRE-30                                                 4.1.15 Containment Cooling System (GN)                                                 Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.16 Standby Diesel Generator Systems jKJ)
A. Applicable System Piping and Instrument Drawings
: 1. M- 12KJ 01-Standby Diesel Generator Cooling System
: 2. M-12KJ02-Standby      Diesel Generator "A" Intake Exhaust, F.O. & Start Air System
: 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
: 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 ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
D. Applicable 1SI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Standby Diesel Generator Systems. These drawings are part of the M-189-50 series.
: 1.       M- 189-50K J-01-01      Sheet 1    Standby Diesel Engine  Diesel Generator "A" Cooling Water Piping
: 2.        M-189-50KJ-01-01        Sheet 4    Standby Diesel Engine  Diesel Generator "A" Exhaust Piping
: 3.        M-1 89-50KJ-02-04       Sheet 1    Standby Diesel Engine  Diesel Generator "B" Cooling Water Piping
: 4.        M- 189-50K J-02-04      Sheet 4    Standby Diesel Engine  Diesel Generator "B" Exhaust Piping WCRE-30               4.1.16 Standby Diesel Generator Systems (K J)                                 Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.16 Standby Diesel Generator Systems (KJ)
E.      Summary of Components Subject To Section XJ 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 1S1 Database.
TABLE 1 SECTION XI AND AUGMENTED COMPONENT 

==SUMMARY==
AND SCHEDULE COMPONENT OR ITEM            CODE             CODE              AUG.          AUG        TOTAL TN          EXAMS BY PERIOD & INTERVAL DESCRIPTION           CATEGORY         ITEM NO.        CATEGORY        ITEM NO.      SYSTEM       P1L   P2       P3         INTERVAL VESSEL WELDED              D-A             DI.10               -              -12                    2      2      2                  6 ATTACHMENTS PIPING WELDED              D-A             D1.20               --                         10         I      1      0                  2 ATTACHMENTS PIPING COMPONENT             F-A             F1.30               --                         28         1      1       1                 3 SUPPORTS EQUIPMENT SUPPORTS             F-A             F1.40               --                         12         2      2      2                  6 (OTHER THAN PIPING)
WCRE-30                                               4.1.16 Standby Diesel Generator Systems (K J)                                           Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.16 Standby Diesel Generator Systems (KJ)
F. Augmented ISI Requirements The following Augmented 1SI requirements apply to the Standby Diesel Generator Systems:
: 1. USNRC Reuulatorv Guide 1.137. Revision 0 - Fuel-Oil Systems for 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 implementation of the testing and VT-2 examinations required by Articles IWD-2000 and IWD-5000 of ASME Section XI, 2007 Edition with the 2008 Addenda.
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-5 220 every 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 Standby Diesel Generator Systems.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table KJ- 1 (Period 1 Examinations), Table K J-2 (Period 2 Examinations),
and Table KJ-3 (Period 3 Examinations).
WCRE-30                   4.1.16 Standby Diesel Generator Systems (KJ)                     Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE KJ-1 IPeriod 1 Examinations Component Name Drawing Number     Component Description                               size Thickness   NDE Method Category Item   Relief Request     Notes EKJ06A-SUP- 1  KJ1-01-01 SI-IT. 1 JACKET WATER EKJ06A INTEGRAL ATTACHMENT                                   VT-i  D-A      DI.10 EKJ06A-SUP-2   KJ1-01-01 SHT. 1   JACKET WATER EKJ06A INTEGRAL ATTACHMENT                                   VT-1  D-A      DI.10 KJ-01-C016     K J-02-04 SHT. 4   PIPING INTEGRAL ATTACHMENT                          42                    VT-I  D-A      D1.20 KJ-01-C016     KJ-02-04 SHT. 4    PIPING SUPPORT                                      42                    VT-3  F-A      F 1.30 EKJ06A-SUP- 1  KJ1-01-01 SHIT. 1  JACKET WATER HX SUPPORT                                                   VT-3  F-A      F 1.40 EKJ06A-SUP-2   KJ1-01-01 SHT. 1   JACKET WATER HX SUPPORT                                                   VT-3  F-A      F1.40 WCRE-30                                                       4.1.16 Standby Diesel Generator Systems (K J)                                      Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   KJ-2 IPeriod 2 Examinations
[System:  KJ Component Name Drawing Number   Component Description                                Size  Thickness  NDE Method Category Item   Relief Request    Notes EKJ03A-SUP-l1  KJ-01-01 SHT. I  INTERCOOLER HIX INTEGRAL ATTACHMENT                                        VT-1  D-A      DI.10 EKJ03A-SUP-2   KJ-01-01 SHT. 1  INTERCOOLER HX INTEGRAL ATTACHMENT                                         VT-i  D-A      DI.10 KJ-01-R008     KJ-01-01 SHT. 4  PIPING INTEGRAL ATTACHMENTS                          28                    VT-i  D-A      D1.20 KJ-0 1-RO08    KJ-0l=01 SHT. 4  PIPING SUPPORT                                       28                    VT-3  F-A      F 1.30 EKJO3A-SUP-1   KJ-01-01 SHT. 1  INTERCOOLER H-X SUPPORT                                                    VT-3  F-A      F1.40 EKJ03A-SUP-2   KJ=01-01 SHlT. 1 INTERCOOLER HX SUPPORT                                                     VT-3  F-A      F 1.40 WCRE-30                                                      4.1.16 Standby Diesel Generator Systems (KJI)                                      Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   KJ-3
[System:  KJ Component Name Drawing Number    Component Description                               Size   Thickness  NDE Method Category Item   Relief Request    Notes EKJ04A-SUP- 1  1(1-01-01 SHT. 1  LUBE OIL EKJ04A INTEGRAL ATTACHMENT                                       VT-I   D-A      DI.10 EKJ04A-SUP-2   KJ3-01-01 SilT. 1 LUBE OIL EKJ04A INTEGRAL ATTACHMENT                                       VT-i   D-A      DI.10 K.J-01l-R004   KJ-02-04 SHlT. 4  PIPING SUPPORT                                      28                    VT-3   F-A      F1.30 EKJ04A-SUP-1   KJ3-01-01 SHT. 1  LUBE OIL COOLER HX SUPPORT                                                VT-3   F-A      F1.40 EKJ04A-SUP-2   KJ3-01-01 SHT. 1  LUBE OIL COOLER 1-X SUPPORT                                               VT-3   F-A      FI1.40 WCRE-30                                                       4.1.16 Standby Diesel Generator Systems (KJ)                                       Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI 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) 4.2.2     Chemical and Volume Control System (M-12BG02) 4.2.3      Chemical and Volume Control System (M-12BG04) 4.2.4      Chemical and Volume Control System (M-12BG05) 4.2.5      Fuel Pool Cooling and Clean-Up System (M-12EC01) 4.2.6      Fuel Pool Cooling and Clean-Up System (M-12EC02)*
4.2.7      Miscellaneous Buildings HVAC (M-12GF0 1) 4.2.8      Fuel Building HVAC (M-12GG02) 4.2.9      Control Building HVAC (M-12GK01) 4.2.10     Auxiliary Building HVAC (M-12GK03) 4.2.11     Auxiliary Building HVAC (M-12GL01, M-12GL02, M-12GL03) 4.2.12     Containment Hydrogen Control System (M- 12GS01)*
4.2.13     Liquid Radwaste System (M-12HB01)*
4.2.14     Emergency Fuel Oil System (M-12JE01) 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-12SJ01) 4.2.18     Nuclear Sampling System (M-12SJ04)
* Except for ASME Class 2 components listed in Section 4.3 B.        Classification of Components Details of the classification of the components subject to ASME Section XI System Pressure Testing are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
            *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 4".
D.        System Pressure Testing In accordance with Section XI, IWA-5000 and IWB-5000, the Class 1 pressure retaining components included on the P&IDs of Section A will receive a system leakage test per IWB -5220 prior to plant startup following each refueling outage.
In accordance with Section XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining components included on the P&IDs of Section A will receive a system leakage test per IWC-5 220 each inspection period.
In accordance with Section XI, IWA-5000 and IWD-5000, the Class 3 pressure retaining components included on the P&IDs of Section A will receive a system leakage test per IWD-5 220 each inspection period.
Procedures used to perform System Pressure Testing are listed in Table 4.2.1 WCRE-30                   4.2 Systems Subject to Section XI Pressure Testing Only                      Revision 0 Page 1 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE 4.2-1 SYSTEM PRESSURE TESTING PROCEDURES Procedure Number                         Procedure Title STS P-021A Train A Emergency Diesel Fuel Oil and Keep Warm System STS P-021A Pressure Test STS P-021B Train B Emergency Diesel Fuel Oil and Keep Warm System Pressure Test STS PE-021C      Train A Emergency Diesel FO, LO, J Wtr, Intclr, Roc Arm, Crank Vac, Air In & Exh Train B Emergency Diesel FO, LO, J Wtr, Intclr, Roc Arm, STS P-021D Crank Vac, Air In & Exh ST S PE-021E     Train A Emergency Fuel Oil Transfer System Pressure Test STS  P E-021F    Train B Emergency Fuel Oil Transfer System Pressure Test STS  PE-021G     Train A Emergency Diesel Air Start System Pressure Test STS  PE-021H     Train B Emergency Diesel Air Start System Pressure Test STS  PE-040A     Reactor Coolant System Pressure Test STS  PE-040C     Reactor Coolant System Pressure Test (10 Year)
STS  PE-040E     RPV Head Bare Metal Inspection STS  PE-041A     Steam Generator System Pressure Test (Ctmt)
STS  P E-041D    Steam Generator System Pressure Test (Non-Ctmt)
STS  PE-042A     CVCS Normal Ops (Ctmt)
STS  PE-042B     CVCS VCT Tank Room Chemical and Volume Control System NCP Discharge Header STS P-042C Pressure Test STS P-042D Chemical and Volume Control System CCP A Discharge Header Pressure Test Chemical and Volume Control System CCP B Discharge Header STS P-042E Pressure Test STS PE-042F      CVCS Normal Ops (Aux Bldg)
STS PE-042G      LID Reheat Heat Exchanger STS PE-042H      CVCS Excess Letdown Piping Pressure Test STS P0421  CVCS Boric Acid Tank A and Boric Acid Transfer Pump A Pressure Test CVCS Boric Acid Tank B and Boric Acid Transfer Pump B STS P-042J Pressure Test STS PE-042K      CVCS Immediate Borate Test STS PE-043A      RHR Train A Normal Ops STS P-043B Residual Heat Removal System Hot Leg Discharge and CCP/SI Pump 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-58, 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 Train 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-30                     4.2 Systems Subject to Section XI Pressure Testing Only Revision 0 Page 2 of 3

WOLF CREEK GENERATING STATION FOURTH 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 P-049C   A Train Underground Essential Service Water System Piping STS P-049C   Flow Test B Train Underground Essential Service Water System Piping STS PE-049D       FlwTs STS PE-049FloA TriEsetaSevcWaeSytmnValsPsueTest 515 PE-049F       B Train Essential Service Water System In Vaults Pressure Test STS PE-049A       CompoinEsentiCol Sring Water System PEG ValAPressure s       Test STS P E-O50B      Component Cooling Water System PEG01C Pressure Test STS PE-O5OC       Coinponent Cooling Water System PEG01B Pressure Test STS PE-O5OD       Component Cooling Water System PEG01D Pressure Test STS P-050E   Pressure Test of CCW System RHR Heat Exchangers, and in STS P-050E   Containment Service Loop STS PE-O051       Borated Refueling Water Storage Pressure Test STS PE-052A       Auxiliary Feedwater Pump Turbine Pressure Test STS PE-053A       A Train Auxiliary Feedwater Pressure Test STS P-053B   Auxiliary Feedwater Pressure Test Using Turbine Driven AFW 515 P-053B   Pump STS PE-053C       Essential Service Water To Auxiliary Feedwater Pressure Test STS P-053D   Auxiliary Feedwater Pressure Test Using Condensate Storage 515 P-053D   Tank 5T5 PE-053E       B Train Auxiliary Feedwater Pressure Test STS PE-053F       Essential Service Water to MDAFP A Pressure Test STS PE-053G       Essential Service Water to MDAFP B Pressure Test STS PE-053H       Essential Service Water to TDAFP Pressure Test STS P-055E   Containment Hydrogen Analyzer A Piping through P-1O1 and P-STS P-055E   97 Pressure Test Containment Hydrogen Analyzer B Piping Through P-99 and P-STS P-055F   56 Pressure Test Pressure Test of Containment Hydrogen Control Piping Through STS PE-055G       Pl1adP9 Pressure Test of Containment Hydrogen Control Piping Through STS PE-055H       P99ad-5 Pressure Test of Floor and Equipment Drain Piping Between LF STS PE-055Q       HV-105 and LF HV-106 Pressure Test of Nuclear Sampling Piping through P-64, P-69, STS PE-055W       adP9 WCRE-30                     4.2 Systems Subject to Section XI Pressure Testing Only       Revision 0 Page 3 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.3     WCGS SYSTEMS EXCLUDED FROM SECTION XI PRESSURE TESTING PER iWA-5110(c)
A. Applicable Components The following ASME Class 2 components are excluded from Section XI System Pressure Testing per IWA-5 110(c):
P&ID Number                Line Number(s)                 Penetration M-12BB02                   B B- 103-HCB- 1"                   P-62 M- 12BL0 1                 BL-028-HCB-3"                      P-25 M-12BM01                   BM-053-HBB-3"                      P-78 M-12EC02                   EC-067-HCB-6"                      P-53 M-12EC02                   EC-072-HCB-6"                      P-54 M-12EC02                   EC-08 1-HCB-3"                     P-55 M-12EM01                   EM-071-BCB-3/4"                    P-92 M-12EP01                   EP-055-FBB- 14"                    P-45 M-12GP01                   GP-001-HBB-6"                      P-34 M-12GP01                   GP-003-HBB-I"                      P-5 1 M-12GP01                   GP-005-HBB-1"                      P-5 1 M-12GS01                   GS-025-HBB-6"                      P-65 M-12GT01                   GT-007-HBB-36"                     V-i160 M-12GT0 1                  GT-004-HBB-36"                     V-i161 M-12GT01                   GT-029-HB B-i8"                    V-i161 M-12GT01                   GT-034-HBB-i18"                    V-160 M- 12GT0 1                 GT-033-HBB-1 8"                    V-160 M-12GT01                   GT-030-HBB-1 8"                    V-i161 M-12HB01                   HB-015-HCB-3"                      P-26 M-12HB01                   HB-025-HBB-3/4"                    P-44 M-12HD01                   HD-0 15-HBB-2"                     P-43 M-12KA01                   KA-244-HCB-1 1/2"                  P-30 M-12KA01                   KA-259-HCB-1 1/2"                  P-30 M-1 2KA02                  KA-05 1-HBB-4"                     P-63 M-12KA02                   KA-261-HBB-I"                      P-63 M-12KA05                   KA-732-HB B- 1"                    Personnel Hatch M-12KA05                   KA-733-HB B- 1"                    Personnel Hatch M-12KB01                   KB-001-HCB-2"                      P-98 M- 12KC02                  KC-560-HBB-4"                      P-67 M-12LF09                   LF-842-HCB-6"                      P-32 M-12SJ04                   SJ-024-BCB-l"                      P-57 B.      Classification of Components Details of the classification of the components that are excluded from Section XI System Pressure Testing per IWA-5 110(c) are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
C.      ASME Class Components A listing of the ASME Class 2 components excluded from Section XI System Pressure Testing per IWA-5 110(c) is included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
WCRE-30     4.3 WCGS Systems Excluded From Section XI Pressure Testing Per IWA-5 110(c)             Revision 0 Page 1 of 1

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Attachment A Assessment of the Surface Condition of Dissimilar Metal Welds This attachment provides the report that assesses the surface condition of dissimilar metal (DM) welds scheduled for examination under the requirements of ASME Section XI, Appendix VIII, Supplement 10. The report also addresses the effect that mitigation strategies will have on the ability to perform required examinations.
Scope:
The welds at Wolf Creek that are currently scheduled for examination under Supplement 10 are the DM welds connecting the RV nozzles to the safe-ends of the loop piping. These welds are divided into two groups: The hot leg DM welds, and the cold leg DM welds. The 4 hot leg DM welds have essentially the same configuration, and the 4 cold leg DM welds have essentially the same configuration. The primary difference between the two groups is the length of the safe end. See the measurements and profiles documented in References 4 and 5 (these profiles are discussed in the "Assessment" below). The longer safe ends of the cold leg nozzles allow more coverage to be obtained if examinations are performed from the OD.
NOTE: The DM welds connecting the safe ends to the pressurizer nozzles were overlaid in RF15, Fall 2006. The pressurizer overlaid welds are now examined in accordance with Supplement 11 (as modified by the PDI program) as stated in relief request I3R-05, and are thus excluded from the scope of this document.
B ackground:
The initial PDI examination of the RV DM welds was conducted in RF14, spring of 2005. These exams were conducted from the interior of the RV, on the ID surface of the welds. As part of the examination, ID surface profiling was performed. These profiles are electronically recorded, and are vaulted as part of the RF14 STS PE-300 surveillance data (the profiles are electronically stored with the examination raw data on a hard drive that is in the vault along with the hard copy of the completed surveillance).
The hot leg DM welds were subsequently examined in RF17, and the cold leg DM welds were subsequently examined in RF 18. The exams were performed from the ID, and profiling was again performed (The vendor had refined the profiling software and hardware, resulting in more precise profile data). Again, these profiles are electronically recorded, and are vaulted as part of the RF17/RF1 8 STS PE-300 surveillance data (again the profiles are on a hard drive in the vault with the hard copy of the surveillance).
Assessment:
Measurements and profiles were taken of the OD surface in RF 14 (02-244741-007), and again in RF 16 (06-289464-005) in conjunction with the bare metal visual examinations. The results indicate that it is possible to obtain coverage of the cold leg DM welds from the OD (this is using encoded phased array techniques, not manual examination). However, it is not possible to obtain the required coverage from the OD of the hot leg. This is due to the length of the safe end being longer on the cold leg welds than on the hot leg welds.
As stated in the background above, the subject welds have been examined from the ID, with the ID surface profiles being recorded and vaulted as part of the surveillance data of STS PE-300 performed in RF 14, RFl17 and RF 18 (see background above). The hot leg examinations have achieved 100% coverage in both axial and circumferential directions. The cold leg examinations have achieved 100% coverage in the axial direction (looking for circumferential flaws), but have been limited in the circumferential direction due to presence of internal roughness.
Relief was requested and granted by the NRC to utilize a supplemental eddy current examination in lieu of achieving coverage in the circumferential direction due to the presence of internal surface roughness (reference 6).
The use of the supplemental eddy current on the ID surface is considered to be at least as effective as UT in detecting surface breaking flaws.
WCRE-30                                             Attachment A                                             Revision 0 Page 1 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Surface Condition Improvement:
Due to the location and configuration of these welds, it is not practical to attempt to improve the surface of these welds unless done in conjunction with a mitigation strategy. As noted in the discussion of mitigation strategy effects below, consideration of the examination surface condition is part of the mitigation strategy selection process.
Mitigation strategy effects:
There are four PWSCC mitigation strategies that are being considered for the RV DM welds. Each strategy is listed along with a discussion of the effect the strategy, if implemented, would have on the examination of the weld. The process of selecting a mitigation strategy includes consideration of the post mitigation examination surface.
Mechanical Stress Improvement Process (MSIP'): This process uses a clamp to deform (squeeze) the piping adjacent to the weld, thus changing the ID wetted surface stress from a tensile stress to a compressive stress. Use of this mitigation strategy would require that the weld examination still be performed in accordance with supplement 10.
MSIP has been demonstrated to have negligible effect on subsequent examinations.
Weld Overlay (WOL):
This process involves the application of weld metal over the existing welds. This process will change the examination surface on the GD surface of the welds. It is required that the GD surface meet the examination specifications after the overlay is applied. If post overlay ISI examinations are performed from the GD surface, then the examinations will not be performed in accordance with supplement 10 (they would be performed in accordance with supplement 11I, as modified by the PDI program, or under an NRC approved alternative). The WOL is required to have a final GD configuration and surface that allows the performance of Supplement 11 exams. If post overlay ISI examinations are performed from the ID surface, then the examinations would be performed in accordance with supplement 10. The WGL mitigation will have negligible effect on subsequent ID exams.
Weld Inlav/Cladding:
This process requires that the ID surface of the weld be machined and then weld metal deposited, isolating the Alloy 82/182 weld metal from the primary water. Use of this mitigation strategy would be expected to improve the ID surface. However, limitations in the initial vendor tooling preclude full restoration of the ID surface to allow full coverage of the DM and SS welds. If this mitigation strategy is selected, the examination would still be performed in accordance with supplement 10, but the inability of the vendor tooling to fully restore the ID surface for improving coverage of subsequent exams significantly limits selection of this technique.
Water Jet Peening:
This process is characterized by the production of cavitation bubbles in a submerged jet. The process involves sweeping ultra high-pressure water jets over the surface to be peened so that cavitation bubbles form and collapse on the work piece. This results in a compressive stress region being created on the surface of the metal and to a depth of about 1 mam. Use of this mitigation strategy would not improve the ID surface for examination purposes. If this mitigation strategy is selected, the examination would still be performed in accordance with supplement 10.

== Conclusion:==

The current process that Wolf Creek utilizes to perform examination of the DM welds is satisfactory. Any attempt at surface improvement would need to be in conjunction with a PWSCC mitigation strategy for these locations.
Mitigation strategies are currently being evaluated and the effect of the mitigation on subsequent examinations is a significant consideration in the evaluation process.
WCRE-30                                            Attachment A                                              Revision 0 Page 2 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN

==References:==
: 1. Incoming correspondence 09-00324: Issuance of Nondestructive Evaluation: "Guideline for Conducting Ultrasonic Examinations of Dissimilar Metal Welds"
: 2. EPRI Report 1018181, Guideline for Conducting Ultrasonic Examinations of Dissimilar Metal Welds
: 3. STS PE-300, Inservice Examinations, RFI4, RF17 and RF18 Vaulted Records
: 4. Work order 02-244741-007
: 5. Work order 06-289464-005
: 6. Correspondence 09-00372: Relief Request 13R-06, Alternative to the Examination Requirements of ASME Code Section XI for Class 1 Piping Welds Examined From the Inside of the Reactor Vessel WCRE-30                                         Attachment A                                        Revision 0 Page 3 of 3

Enclosure II Wolf Creek Unit 1 Internal Events PRA Gap Assessment to Support RI-ISI (22 Pages)

Westinghouse Non-Proprietary Class 3 O Westinghouse To:               File                                                                     Date:    December 18, 2014 cc:               David Gerlis Kyle Christiansen Daniel Sadlon From:             Alexander Rubbicco Ext:              860-731-6375 Fax:
Your Ref:         N/A Our Ref:          LTR-RAM-II-14-083, Rev. 0

==Subject:==
Wolf Creek Unit 1 Internal Events PRA Gap Assessment to Support RI-ISI This letter transmits the results of the completed gap assessment completed on the Wolf Creek Unit 1 internal events probabilistic risk assessment. This assessment determined whether the current Rev. 7 model of record meets the supporting requirements in Table 2-2 of EPRI TR 1021467-A to support the Wolf Creek Unit 1 ten year RI-ISI update.
Author:              Electronically Approved*                         Reviewer:           ElectronicallyApproved*
Alexander Rubbicco                                                   David Gerlits Risk Applications and Methods II                                     Risk Applications and Methods II Manager:             ElectronicallyAprvd Daniel Sadlon -
Resource Manager Risk Applications and Methods II This document is the property of and contains Proprietary Information owned by Westinghouse Electric Company LLC and/or its subcontractors and suppliers. It is transmitted to you in confidence and trust, and you agree to treat this document in strict accordance with the terms and conditions of the agreement under which it was provided to you.
                 *Electronically approvedrecords are authenticatedin the electronic document management system.
                                            &#xa9;2014 Westinghouse Electric Company LLC All Rights Reserved

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 2 of 22 Table of Contents 1.0   Background and Purpose ..........................................................................
1.1   Purpose .............................................................................................. 3 1.2   Background ...........................................................................................
1.1   Open Items ..........................................................................................
2.0   Summary of Results and Conclusions .......................................................... 4 3.0   References .......................................................................................... 5 4.0   Methodology......................................................................................... 6 5.0   Results............................................................................................... 6 5.1   Supporting Requirement Evaluation of ASME/ANS RA-Sb-2005 to ASME/ANS RA-Sa-2009........................................................................................... 6 Appendix A: Customer Comments ..................................................................... 21

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 3 of 22 1.0     Background and Purpose 1.1     Purpose This report documents the evaluation of the Wolf Creek Unit 1 internal events probabilistic risk assessment (PRA) model with respect to the supporting requirements required by Table 2-2 in Electric Power Research Institute (EPRI) Technical Report (TR) 1021467-A (Reference 1). The supporting requirements contained in this technical report relate to the PRA standard endorsed in Regulatory Guide 1.200 Rev. 1 (Reference 2). The supporting requirements in the associated table will first be correlated to their appropriate RA-Sa-2009 (Reference 5) supporting requirement equivalent, which is endorsed in Regulatory Guide 1.200, Rev. 2 (Reference 3).
Subsequently, the model will be evaluated based on the intent and wording of the supporting requirements in the American Society of Mechanical Engineers (ASME)/American Nuclear Society (ANS) PRA Standard RA-Sa-2009 (Reference 5). This evaluation follows methodology, guidance and justification found in EPRI TR 1021467-A (Reference 1).
1.2     Background Wolf Creek Nuclear Operating Corporation (WCNOC) developed an EPRI risk-informed in-service inspection (RI-ISI) program for Wolf Creek Generating Station (WCGS). One aspect of a RI-ISI program is to maintain the RI-ISI program as a living program. The RI-ISI program is required to be reviewed and updated every ten years of commercial operation. That analysis allows for WCNOC to update the PRA program to meet the requirements of EPRI TR 1021467-A (Reference 1) Traditional Approach. As part of the application of this methodology the PRA must meet the supporting requirements mentioned in EPRI TR 1021467-A (Reference 1) Traditional Approach. This letter will document whether the current Rev. 7 model of record meets these supporting requirements and will also document any gaps associated with not meeting these requirements.
1.1     Open Items
: 1. The newest HRA document and associated supporting MAAP timings (References 7 and
: 12) have not been formally approved but have been completed and reviewed by Wolf Creek. As part of this open item the dependency analysis has also not been completed.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II- 14-083, Rev. 0 Page 4 of 22 2.0     Summary of Results and Conclusions Evaluating WCNOC current PRA to date against the supporting requirements outlined in the EPRI technical report, as required to be met to implement the technical report's methodology found that many of the required supporting requirements were fulfilled. Noted deficiencies during the 2006 peer review (Reference 6) related to human reliability analysis, initiating events, Level 2 and quantification have been sufficiently rectified by issuance of additional documentation and analysis. This documentation has been issued relatively recently and includes roadmaps for meeting the PRA standard explicitly at Capability Category (CC) I1.
Additionally, many of the supporting requirements required per the EPRI technical report were previously assessed as met during the 2006 peer review at least the required level (often CC-I) or higher.
As such, several supporting requirements were found to no__t meet the entire intent of the supporting requirement. It was assessed that they meet the majority of the intent of the supporting requirement but needed additional analysis to be fully met. This specifically relates to supporting requirements HR-A3 and DA-D3 in which the original F&Os have not been resolved.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 5 of 22 3.0     References
: 1. EPRI TR-1021467-A, "Nondestructive Evaluation: Probabilistic Risk Assessment Technical Adequacy Guidance for Risk-Informed In-Service Inspection Programs," June 2012.
: 2. Regulatory Guide 1.200, Revision 1, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities,"
USNRC, January 2007.
: 3. Regulatory Guide 1.200, Revision 2, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities,"
USNRC, March 2009.
: 4. RA-Sb-2005, "Addenda to ASME RA-S-2002 Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications," American Society of Mechanical Engineers, New York, NY, December 2005.
: 5. ASME/ANS-Ra-Sa-2009, Addenda to ASME/ANS RA-S-2008 Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, ASME, 2009.
: 6. Review of the Wolf Creek Generating Station Probabilistic Risk Assessment Against the Requirements of the ASME PRA Standard (Addenda B), October 2006.
: 7. WCNOC-PSA-HRA, "Wolf Creek Generating Station Human Reliability Analysis           - Post Initiators," Rev. 0-A DRAFT.
: 8. WCNOC-PSA-001, "Wolf Creek Generating Station PSA Initiating Event Analysis," Rev.
1, September 2013.
: 9. PSA-09-005, "WCGS PRA Level 2 Update," Rev. 0.
: 10. WCNOC-PSA-022, "Accident Sequence Quantification," Rev. 0, September 2013.
: 11. PSA-05-0021, "Pre-Initiator Human Reliability Analysis," Rev. 0, March 2006.
: 12. LTR-RAM-II-14-051, "Wolf Creek MAAP Analyses to Support HRA Timings," Rev. 0-A DRAFT.
: 13. WCNOC-PSA-003, "Wolf Creek Generating Station PSA Accident Sequence Analysis,"
Rev. 0, September 2013.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 6 of 22 4.0     Methodology The WCNOC Rev. 7 model of record and any associated supporting documentation will be evaluated based on the supporting requirements as outlined in Table 2-2 of EPRI TR 1021467 (Reference 1). The supporting requirements in this table are based on the ASME/ANS RA-Sb-2005 PRA standard (Reference 4). As it is currently required that PRA models must meet ASME/ANS RA-Sa-2009 (Reference 5) per Regulatory Guide 1.200, Rev. 2 (Reference 3),
the supporting requirements in Table 2-2 of EPRI TR-1 021467 (Reference 1) are assessed and matched to their equivalent ASME/ANS RA-Sa-2009 (Reference 5) requirement.
The next step in this report is to evaluate the WCNOC PRA model and any associated documentation to the supporting requirements (and their 2009 equivalents) found in the EPRI technical report. This was completed by evaluating the results of the 2006 WCNOC PRA review.
Any of the supporting requirements met during this peer review and which were not changed in the update to ASME/ANS RA-Sa-2009 (Reference 5) were again assessed as met. For supporting requirements not met (either partially or fully) or for supporting requirements in which the wording or intent was changed were re-assessed to determine whether they were met at least the level of requirement required by the EPRI TR.
5.0     Results 5.1     Supporting Requirement Evaluation of ASME/ANS RA-Sb-2005 to ASME/ANS RA-Sa-2009 As noted previously, Table 2-2 of EPRI TR 1021467-A (Reference 1) contains the supporting requirements to implement the EPRI Traditional RI-ISI methodology. This table contains the supporting requirements as found in the ASME/ANS RA-Sb-2005 PRA standard (Reference 4).
This section will evaluate this standard to the revised version of the standard (ASME/ANS RA-Sa-2009) (Reference 5) which is the latest PRA standard endorsed by the NRC in Regulatory Guide 1.200 Rev. 2 (Reference 3). This analysis is shown in Table 5.1-1.
Table 5.1-1: Assessment of ASME/ANS RA-Sb-2005 versus ASMEIANS RA-Sa-2009 Capability Required        Category Supporting        Required RA-Sa-2009 Requirement for RI-ISI            Equivalent             Assessment*
AS-Al10           I             AS-Al10          None, no change to text.
AS-A7             Il/I          AS-A7            None, no change to text.
AS-A9             II            AS-A9            None, no change to text.
DA-B1             I              DA-B1           None, no change to text.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 7 of 22 Table 5.1-1: Assessment of ASMEIANS RA-Sb-2005 versus ASMEIANS RA-Sa-2009 Capability Required        Category Supporting       Required        RA-Sa-2009 Requirement for RI-ISI            Equivalent             Assessment*
DA-B2            II/I            DA-B2           None, no change to text.
DA-C7            I               DA-C7           None, no change to text.
DA-C9            II/I            DA-C9           None, no change to text.
HR-B1            I               HR-B1           None, no change to text.
HR-C2            I               HR-C2           None, no change to text.
HR-D2            I               HR-D2           None, no change to text.
HR-D3            I               HR-D3           None, no change to text.
HR-D7            Il/I            HR-D7           None, no change to text.
HR-E3            I               HR-E3           None, no change to text.
HR-E4            I               HR-E4           None, no change to text.
HR-Fl            Il/I            HR-Fl           None, no change to text.
HR-F2            I               HR-F2           None, no change to text.
HR-G1            I               HR-G1           None, no change to text.
HR-G3            I               HR-G3           None, no change to text.
HR-G4            I               HR-G4           None, no change to text.
HR-G5            I               HR-G5           None, no change to text.
HR-HI            I               HR-HI           None, no change to text.
IE-A3a           II/I            IE-A4           None, no change to text.
IE-A4            I               IE-A5           None, no change to text.
IE-A4a           I               IE-A6           None, no change to text.
IE-A6            I               IE-A8           None, no change to text.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 8 of 22 Table 5.1-1: Assessment of ASMEIANS RA-Sb-2005 versus ASMEIANS RA-Sa-2009 Capability Required       Category Supporting       Required      RA-Sa-2009 Requirement      for RI-ISI     Equivalent             Assessment*
IE-A7            I              IE-A9           None, no change to text.
None, minor wording IE-B3            I              IE-B3           change, no impact on PRA.
Wording change, PRA model should be reviewed to assure the new wording is IE-C11           II/I           IE-C13          met.
IE-C12           Il/I           IE-C14          None, no change to text.
None, corrected the referenced table number, no LE-B1                           LE-B1           impact on PRA.
None, minor wording LE-B2            I              LE-B2           change, no impact on PRA.
None, minor wording LE-C1            I              LE-CI           change, no impact on PRA.
LE-C10           I              LE-C13          None, no change to text.
LE-C2a           I              LE-C2           None, no change to text.
None, minor wording LE-C2b           I              LE-C3           change, no impact on PRA.
Only changes to the referenced SR # are made.
No changes have been LE-C3            ILE-C4                         made to those SRs.
LE-C4            I              LE-C5           None, no change to text.
LE-C8a           I              LE-C9           None, no change to text.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 9 of 22 Table 5.1-1: Assessment of ASMEIANS RA-Sb-2005 versus ASME/ANS RA-Sa-2009 Capability Required       Category Supporting      Required     RA-Sa-2009 Requirement      for RI-ISI   Equivalent              Assessment*
LE-C8b          I            LE-C1 0          None, no change to text.
LE-C9a          I            LE-C11I          None, no change to text.
LE-C9b          I            LE-C12           None, no change to text.
LE-DIla         I            LE-D1            None, no change to text.
None, minor wording LE-Dlb          I            LE-D2            change, no impact on PRA.
LE-D2           I            LE-D3            None, no change to text.
LE-D3        -I              LE-D4            None, no change to text.
LE-D4           I            LE-D5            None, no change to text.
LE-D5           I            LE-D6            None, no change to text.
LE-D6           I            LE-D7            None, no change to text.
LE-E2           I             LE-E2           None, no change to text.
LE-E3           I             LE-E3           None, no change to text.
None, reduced back-references from QU-A, B, &
C to QU-A & B. No impact LE-Fla          I            LE-F1            on PRA.
LE-G3           I            LE-G3            None, no change to text.
QU-A2b          I            QU-A3            Minor wording changes.
QU-D3           I            QU-D4            None, no change to text.
QU-D5a          I            QU-D6            None, no change to text.
QU-E3           I            QU-E3            None, no change to text.

Westinghouse Non-Proprietary Class 3 LTR-RAM-JI-I14-083, Rev. 0 Page 10 of 22 Table 5.1-1: Assessment of ASME/ANS RA-Sb-2005 versus ASMEIANS RA-Sa-2009 Capability Required        Category Supporting       Required       RA-Sa-2009 Requirement       for RI-ISI      Equivalent              Assessment*
QU-F3            I              QU-F3             None, no change to text.
SC-A2            I               SC-A2            None, no change to text.
SC-A5            I               SC-.A5           None, no change to text.
SC-B1I           I               SC-BI            None, no change to text.
SC-B2            II              SC-B2            None, no change to text.
SY-A15           Il/I            SY-A16           None, no change to text.
SY-A20           I               SY-A22           None, no change to text.
SY-A4            I               SY-A4            None, no change to text.
SY-A7            II/I            SY-A7            None, no change to text.
SY-B1            I               SY-B1            None, no change to text.
SY-B11I          I               SY-B1 0          None, no change to text.
SY-B2            II/I            SY-B2            None, no change to text.
SY-B7            I               SY-B7            None, no change to text.
 &deg;upoaaes torequirement.
supporting    me woraing to correct errors, reierences, linlKS or etc. are not consiaerea cnanges to tie Based on this assessment the appropriate supporting requirements are assessed starting from the peer review performed at Wolf Creek in 2006. As noted previously this peer review was completed to the ASME/ANS RA-Sb-2005 (Reference 4) version of the PRA standard. The supporting requirements contained in Table 5.1-1 were first evaluated to the previously performed peer review. If the supporting requirement was met and there were no changes to the wording or intent of the supporting requirement from 2005 to 2009, then the supporting requirement will be assessed as met. The supporting requirements required to meet the EPRI RI-ISI are evaluated in Table 5.1-2 and are assessed to determine if they are met or not met based on the current model of record and the associated documentation available at the time of this assessment.
Note: the peer review was completed evaluating the WCNOC PRA model and documentation at CC-Il. Therefore, if a supporting requirement is assessed as previously met, it is at least met at CC-Il or higher. As the EPRI technical report only requires that at most CC-Il be met, no

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 11 of 22 designation is generally given for at what capability category the supporting requirement is met at.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 12 of 22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category       RA-Sa-2009 Requirement         Required for RI-ISI      Equivalent                        2006 Peer Review Assessment AS-A10O                                    AS-A10                  Previously   met and satisfied.
AS-A7                II/I                  AS-A7                   Previously   met and satisfied.
AS-A9                II                    AS-A9                   Previously   met and satisfied.
DA-B1I                                     DA-B1                   Previously   met and satisfied.
DA-B2                Il/I                  DA-B2                   Previously   met and satisfied.
DA-C7                IDA-C7                                        Previously   met and satisfied.
DA-C9                Il/I                  DA-C9                   Previously   met and satisfied.
HR-B1I                                     HR-B1                   Previously   met and satisfied.
In the 2006 peer review only the portion related to generic operating experience was not met. As this is a requirement to meet CC-I I/Ill and CC-I it specifically excludes this portion of the requirement, therefore this SR is met at CC-I and satisfies the EPRI TR requirement for this supporting requirement. This analysis is contained in PSA-05-021, Rev.
HR-C2                IHR-C2                                        0 (Reference 11).
HR-D2                IHR-D2                                        Previously met and satisfied.
HR-D3                IHR-D3                                        Previously met and satisfied.
HR-D7                Il/I                  HR-D7                   Previously met and satisfied.
The inclusion of operator interviews has been completed in Reference 7 and the associated HRA Calculator attachment file. Therefore this supporting requirement is judged to be met at CC-Il which exceeds the requirement found in the HR-E3                                      HR-E3                   EPRI technical report.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 13 of 22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category       RA-Sa-2009 Requirement         Required for RI-ISI      Equivalent                       2006 Peer Review Assessment While it was found during the 2006 peer review that Wolf Creek did not meet CC-Il/Ill, there is no specific requirement or action for meeting CC-I. Therefore it is assessed that this HR-E4                IHR-E4                                       SR is met for use with the EPRI technical report.
HR-Fl                IlI/                  HR-Fl                   Previously met and satisfied.
This has been completed in Reference 7 and the associated HRA Calculator attachment file. Therefore this supporting requirement is judged to be met at CC-Il which exceeds the HR-F2                IHR-F2                                        requirement found in the EPRI technical report.
HR-G1I                                     HR-G1                   Previously met and satisfied.
This has been completed in Reference 7 and the associated HRA Calculator attachment file. Therefore this supporting requirement is judged to be met at CC-Il which exceeds the HR-G3                IHR-G3                                       requirement found in the EPRI technical report Thermal-hydraulic analyses have been performed in Reference 12. This document uses thermal-hydraulic analyses to support associated HRA timings. Therefore, this supporting requirement is assessed to at least meet CC-Il of HR-G4                                      HR-G4                  this supporting requirement.
This has been completed in Reference 7 and the associated HRA Calculator attachment file. Therefore this supporting requirement is judged to be met at CC-Il which exceeds the HR-G5                                      HR-G5                  requirement found in the EPRI technical report.
This has been completed in Reference 7 and the associated HRA Calculator attachment file. Therefore this supporting requirement is judged to be met at CC-Il which exceeds the HR-Hi                                      HR-HI                  requirement found in the EPRI technical report.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 14 of 22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category        RA-Sa-2009 Requirement         Required for RI-ISI       Equivalent                        2006 Peer Review Assessment Met at least CC-li in WCNOC-PSA-001, Section 2.2.2 (Reference 8). Specifically the Licensee Event Reports were evaluated to determine whether any trip or unidentified initiating event occurred. If it was found to be a relevant plant trip or initiating event, it was included in the PRA IE-A3                Il/I                  IE-A3                   model.
A systematic approach for assessing the possibility of an initiating event occurring due to the failure of a system is performed WCNOC-PSA-O01, Rev. 1, Section 2.4, (Reference 8). A system by system evaluation approach was taken to ensure that all system initiating events were IE-A4                                      IE-A5                   considered.
While there is no explicit discussion of maintenance alignments within WCNOC-PSA-OO1 Rev. 1 (Reference 8) review of the system initiator models indicate that maintenance alignments are taken into consideration along with common cause failure. Therefore, CC(-1l is assessed as IE-A4a                           I         IE-A6                   met.
Interviews documented in WCNOC-PSA-OO1, Rev. 1, IE-A6               IIE-A8                                        Appendix A (Reference 8).
Previously not met. Specifically evaluated and addressed in WCNOC-PSA-001, Sections 2.2.2 and 2.2.3 (Reference 8) through review of the licensee event reports, outage history IE-A7                                      IE-A9                   and analysis of similar plants to WCNOC. Met at CC-Il.
Initiating events are created in WCNOC-PSA-O01, Rev. 1, Section 3 (Reference 8). While initiating events are grouped, they are not subsumed and are shown independently.
IE-B3                                      IE-B3                  Therefore this supporting requirement is met at CC-Il.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II- 14-083, Rev. 0 Page 15 of22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category       RA-Sa-2009 Requirement         Required for RI-ISI      Equivalent                         2006 Peer Review Assessment Initiating events are calculated appropriately using generic or plant data as appropriate in WCNOC-PSA-001, Rev. 1, IE-C11               Il/I                  IE-C13                  Section 4 (Reference 8). Met at CC-I/Il.
IE-C12               Il/I                  IE-C14                  Previously met and satisfied.
Met in PSA-09-0005 Sections 3.1.3 and 3.2 (Reference 9) based on the items required to be analyzed which were identified in the ASME/ANS Standard Table 2-2.8-3. Met at LE-B1I                                     LE-B1                   CC-Il.
LE-B2                ILE-B2                                        Previously met and satisfied.
LE-C1i                                     LE-C1                   Previously met and satisfied.
Containment bypass considered and analyzed in PSA                                                                   0005 (Reference 9) in Sections 2, 3.1.3, 3.2.1 3.2.2, 4.1 and LE-C10                                     LE-C13                 6.4.4. Met at CC-II.
Operator actions related to SAMG guidance are included and documented in PSA-09-0005 Section 2 and Section 3 (Reference 9). For example, actions are credited for low pressure injection, reactor coolant system depressurization, thermally induced steam generator tube ruptures, and pressure induced steam generator tube ruptures. Therefore, LE-C2a              _________LE-C2                                this SR is met at CC-Il.
This supporting requirement is met in PSA-09-0005 Section 6.2.4 (Reference 9) which evaluates whether equipment can LE-C2b                                     LE-C3                  be repaired to prevent a release. Met at CC-Il.
Met at CC-Il and evaluated in PSA-09-0005 in Section 3.2 LE-C3                ILE-C4                                       (Reference 9).
LE-C4                ILE-C5                                        Previously met and satisfied.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 16 of 22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category       RA-Sa-2009 Requirement         Required for RI-ISI      Equivalent                       2006 Peer Review Assessment Equipment survivability is considered in PSA-09-0005 Sections 3.2.10 and 3.2.11 (Reference 9). Operator actions credited are usually evaluated to have a relatively high human error probability (e.g., OPA-LEV2-RCSDEP).
LE-C8a                                     LE-C9                   Therefore this SR is met at CC-Il.
Assessed and documented in PSA-09-0005 in Section 6.2.4 LE-C8b               ILE-C10                                       (Reference 9).
No actions, credit or equipment is justified to be operable following the failure of containment. Therefore CC-I is met LE-C9a                                     LE-C1 1                as required by the EPRI technical report.
No actions, credit or equipment is justified to be operable following the failure of containment. Therefore CC-I is met LE-C9b               I                     LE-C12                 as required by the EPRI technical report.
LE-D1A               ILE-D1                                        Previously met and satisfied.
LE-DIB               ILE-D2                                        Previously  met and  satisfied.
LE-D2                ILE-D3                                        Previously  met and  satisfied.
LE-D3                I__________LE-D4                              Previously  met and  satisfied.
LE-D4                I__________LE-D5                              Previously  met and  satisfied.
Met in PSA-09-0005 Section 3.2 with associated sensitivities LE-D5                ILE-D6                                       in Section 6 (Reference 9).
LE-D6                ILE-D7                                        Previously met and satisfied.
WCNOC used split fractions other than 1/0 in developing their accident progression event trees. This is documented LE-E2                                      LE-E2                  in PSA-09-0005, Section 3.2 (Reference 9). Therefore, CC-Il

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 17 of 22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category      RA-Sa-2009 Requirement        Required for RI-ISI      Equivalent                        2006 Peer Review Assessment is assessed as met.
WCNOC has developed P0S and CET evaiuations in Section 3.2 of PSA-09-0005 (Reference 9). Therefore, CC-Il LE-E3                ILE-E3                                       is assessed as met.
Evaluated in the quantitative evaluation performed in PSA-LE-F1A               ILE-F1                                      09-0005 in Section 6.2.3 at CC-II (Reference 9).
Relative contribution of contributors is performed in PSA                                                                  0005 in Sections 6.1 and 6.2 (Reference 9). This supporting LE-G3                                     LE-G3                  requirement is met at CC-Il.
Evaluated in Section 5.0 of WCNOC-PSA-022, Rev. 0.
Additionally SOKC is evaluated by using type codes when QU-A2b                                    QU-A3                   parametric uncertainty is evaluated. This SR is met at CC-Il.
Evaluated in Section 9.0 of WCNOC-PSA-022, Rev. 0 QU-D3                                     QU-D4                  (Reference 10). Met at CC-Il.
Evaluated in Sections 5.0 and 7.0 of WCNOC-PSA-022, QU-D5a                                    QU-D6                  Rev. 0 (Reference 10). Met at CC-Il.
Evaluated in Section 8.1 of WCNOC-PSA-022, Rev. 0 QU-E3                                     QU-E3                  (Reference 10). Met at CC-Il.
Evaluated in Sections 5.0 and 7.0 of WCNOC-PSA-022, QU-F3                IQU-F3                                      Rev. 0 (Reference 10). Met at CC-Il.
SC-A2                ISC-A2                                      Previously met and satisfied.
This supporting requirement is met at CC-I as WCNOC considers a mission time of at least 24 hours in WCNOC-PSA-0003 (Reference 13). As noted in the peer review report, CC-Il could be met with additional documentation SC-A5                                     SC-AS                  upgrades, but these are not needed to meet the

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 18 of 22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category       RA-Sa-2009 Requirement         Required for RI-ISI      Equivalent                        2006 Peer Review Assessment requirements for use of the EPRI technicai report.
SC-B1I                                     SC-B1                   Previously met at CC-I and therefore satisfied.
SC-B2                II                    SC-B2                   Previously met and satisfied.
While it was noted in the peer review this supporting requirement has only partially met the significance of the finding is low. This is mainly related to a documentation issue in which proper referencing of the analysis was not completed. As it is a documentation issue and is rated as a Category D finding, not resolving this finding would not impact the use of the EPRI RI-ISI methodology. Excluding pre-initiator human failure events would only increase the importance and contribution to risk from other components SY-A15               Il/I                  SY-A16                 that make of the system fault tree model.
SY-A20               ISY-A22                                       Previously met and satisfied.
This supporting requirement was previously met in the 2006 peer review at CC-I and therefore meets the requirements SY-A4                I                     SY-A4                  for using the EPRI technical report.
SY-A7                Il/I                  SY-A7                   Previously met and satisfied.
SY-B 1               ISY-B1                                        Previously met and satisfied.
SY-B11i                                    SY-B10                  Previously met and satisfied.
SY-B2                Il/I                  SY-B2                  Previously met and satisfied.
SY-B7                I__________SY-B7                              Previously met and satisfied.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 19 of 22 Additionally, any significant F&Os that were found during the 2006 must be closed out regardless of whether the EPRI RI-ISI technical report specifies that a capability category be met with the exception of internal flooding as it is normally a model on its own that does not impact non-internal flooding parts of the PRA. As the peer review was completed using older methodology, all findings or discrepancies were noted as F&Os and ranked based on a qualitative scale from A to D. Based on the new peer review methodology that is practiced today, C and D level findings are considered non-significant to the results or methodology and are now labeled as "suggestions."
Suggestions are not required to be closed out to submit the PRA for applications while F&Os require that a resolution be created and documented. Based on Table 4-2 of Reference 6, Table 5.1-3 shown below evaluates whether these significant F&Os were properly resolved. All supporting requirements shown in this table were categorized at a B level from Reference 6.
Table 5.1-3: Assessment of the Supporting       Requirements of B Category F&Os RA-Sa-2009 Supporting Requirement               Equivalent               Evaluation IE-A4                                IE-A5                    Previously evaluated in Table 5.1-2.
IE-A4a                               IE-A6                    Previously evaluated in Table 5.1-2.
IE-A7                                IE-A9                    Previously evaluated in Table 5.1-2.
IE-B3                                IE-B3                    Previously evaluated in Table 5.1-2.
The initiating event frequency is calculated using generic and plant specific data in Section 4.0 of Reference 8. Parametric uncertainty values are also provided for each specific IE-C1                                IE-C1                    initiating event.
Initiating event frequencies were calculated based on reactor year in Section 4.0 of Reference 8. Additionally, a plant availability factor is considered in Section 4.2 of I-3IE-C5                                             Reference 8.
Bayesian updating performed in Section 4.2 of I-4IE-C6                                             Reference 8 as appropriate.
Evaluated and documented in Section 4.0 of AS-B3                                AS-B3                    Reference 13.
SC-E31                               SC-B1                    Previously evaluated in Table 5.1-2.
A review and effort to document practices that involve mechanisms that simultaneously affect equipment in diverse systems was not completed. Therefore this supporting HR-A3                                HR-A3                    requirement is not met.
HR-G4                                HR-G4                    Previously evaluated in Table 5.1-2.
HR-H3                                HR-H3                    See open item 1.
Not met, some testing and maintenance events still lack parametric uncertainty values. It is recommended a comprehensive review be performed to ensure all fault tree model data includes the proper parametric uncertainty DA-DJ3                               DA-D3                    values.
QU-A4                                QU-A5                    Met in Section 3.3 of Reference 10.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 20 of 22 Table 5.1-3: Assessment of the Supporting Requirements of B Category F&Os RA-Sa-2009 Supporting Requirement         Equivalent               Evaluation Met in Section 4.0 and associated subsections QU-B2                          QU-B2                    of Reference 10.
Not applicable. A single top-logic linked fault QU-C3                          QU-C3                    tree is used rather than linking of event trees.
Evaluated in Section 5.0 Table 5-6 of QU-D4                          QU-05                    Reference 10.
Met in Section 8.4 of Reference 10 for the QU-E4                          QU-E4                    quantification process.
LE-B1                          LE-B1                    Previously evaluated in Table 5.1-2.
LE-C2a                         LE-C2                    Previously evaluated in Table 5.1-2.
LE-E2                          LE-E2                    Previously evaluated in Table 5.1-2.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 21 of 22 Appendix A: Customer Comments

Westinghouse Non-Proprietary Class 3 LTR-RAMIvI--14-083, Rev. 0 Page 22 of 22 Table A-I: Customer Comments and Resolutions______
Customer Reference  Comment(s):                            Comment        Comment Resolution:                   Resolution Comment  Document                                          Prepared                                             Prepared Number:  SectionByy
: 1. All        Document should be Non-Proprietary JC Patel           Agreed, document classification was   AAR Class 3.                              ______changed            to class 3.                   _____
: 2. All        Several instances of AMSE appear in David             Corrected.                            AAR the document.                         Alford

W~FCREEK      SNUCLEAR OPERATING CORPORATION February 23, 2016 Jaime H. McCoy Vice President Engineering ET 16-0005 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

==Subject:==
Docket No. 50-482: Wolf Creek Generating Station Inservice Inspection Plan and 10 CFR 50.55a Requests 14R-01 and 14R-02 for the Fourth Inservice Inspection Program Interval.
Gentlemen:
Pursuant to American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code Section XI, IWA-1400(c), Wolf Creek Nuclear Operating Corporation (WCNOC) is submitting, for information only, the Inservice Inspection (ISI) Program Plan for the fourth 10-year ISI interval at Wolf Creek Generating Station (WCGS). The ISI Program Plan is included as Enclosure I of this submittal. The fourth 10-year ISI interval began September 3, 2015.
Pursuant to 10 CFR 50.55a(z)(1), WCNOC hereby requests approval by the Nuclear Regulatory Commission (NRC) of 10 CFR 50.55a Request 14R-01 for the fourth 10-year inspection interval of WCNOC's ISI Program, which is included as Attachment I to this submittal. Request 14R-01 requests the continued application of an alternative risk-informed methodology in selecting Class 1 and Class 2 piping welds for examination during the fourth inspection interval. To support this request, Enclosure II of this submittal contains the gap assessment completed by Westinghouse on the WCGS internal events probabilistic risk assessment.
Pursuant to 10 CFR 50.55a(z)(2), WCNOC hereby requests NRC approval of 10 CFR 50.55a Request 14R-02 for the fourth 10-year inspection interval of WCNOC's ISI Program, which is included as Attachment II to this submittal.                        Request 14R-02 requests relief from the requirements of ASME Code Section XI, 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.
WCNOC requests approval of 10 CFR 50.55a Requests 14R-01 and 14R-02 prior to February 28, 2017.
P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831            1ji  .
An Equal Opportunity Employer M/F/HCNVET

ET 16-0005 Page 2 of 2 This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4156, or Cynthia R. Hafenstine (620) 364-4204.
Sincerely, Jaime H-.McCoy JHM/rlt Attachments: II 10 CFR 50.55a Request Number 14R-01 10 CFR 50.55a Request Number 14R-02 II

==Enclosures:==
Wolf Creek Generating Station Inservice Inspection Program Plan Wolf Creek Unit 1 Internal Events PRA Gap Assessment to Support RI-ISI cc:   M. L. Dapas (NRC), wia, wie C. F. Lyon (NRC), wla, wie N. H. Taylor (NRC), w/a, wie Senior Resident Inspector (NRC), w/a, wie

Attachment I to ET 16-0005 Page 1 of 11 Wolf Creek Nuclear Operating Corporation 10 CFR 50.55a Request 14R-O1 Request for Alternative to Selection and Examination Requirements for Class 1 and 2 Piping Welds.

Attachment Ito ET 16-0005 Page 2 of 11 10 CFR 50.55a Request Number l4R-O1 Proposed Alternative In Accordance with 10 CFR 50.55a(z)(1)
Alternative Provides Acceptable Level of Quality and Safety
: 1. ASME Code Component(s) Affected All Code Class I and 2 piping welds previously subject to the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section Xl, Table IWB-2500-1 (Examination Categories B-F and B-J) and Table IWC-2500-1 (Examination Categories C-F-I and C-F-2).
: 2. Applicable Code Edition and Addenda ASME B&PV Code, Section Xl 2007 Edition with 2008 Addenda.
: 3. Applicable Code Requirement ASME Section Xl, Tables IWB-2500-1 and IWC-2500-1 for Examination Categories B-F, B-J, C-F-I and C-F-2 stipulate the selection and examination requirements for Class I and 2 piping welds.
: 4. Reason for Request ASME Section X1 Examination Categories B-F, B-J, C-F-I, and C-F-2 originally contained the requirements for the nondestructive examination of Class I and 2 piping welds. In 2001, a risk-informed (RI) methodology for the inservice inspection (ISI) of Class I and 2 piping welds was applied at the Wolf Creek Generating Station (WCGS).
The RI-ISI process used in this application is described in Electric Power Research Institute (EPRI) Topical Report (TR) 112657, Revision B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure" (Reference 1). 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" (Reference 2).
This RI 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" (Reference 3) and Regulatory Guide 1.178, "An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping" (Reference 4).
The original RI-ISI template, "Risk-Informed Inservice Inspection Program Plan - Wolf Creek Generating Station (Revision 1)" was submitted to the NRC for approval for use during the second ISI interval. The approval was documented in a letter dated December 13, 2001 (ADAMS Accession No. ML013200130).

Attachment I to ET 16-0005 Page 3 of 11 A request to continue to use the RI-ISI methodology on Class 1 and 2 piping welds for the third ISI interval was submitted to the NRC for approval in WCNOC Letter ET 06-0010 dated March 2, 2006 (ADAMS Accession No. ML060720142). This request was approved by the NRC in a letter dated February 21, 2007 (ADAMS Accession No. ML070260538). The purpose of this current request is for the continued application of the RI-ISI methodology on Class 1 and 2 piping welds during the fourth IS1 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 RI-ISI criteria of EPRI TR-112657 during the fourth 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-I and C-F-2).
When WCNOC submitted the 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, Nuclear Energy Institute (NEI) 04-05, "Living Program Guidance To Maintain Risk-Informed Inservice Inspection Programs For Nuclear Plant Piping Systems" (Reference 5) has been developed. As part of the ISI Program Update for the fourth ISI interval at WCGS, an 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 WCGS RI-ISI application as it enters the fourth 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

Attachment I to ET 16-0005 Page 4 of 11
            - Programmatic Changes
            - Procedural Changes
* Changes in Postulated Conditions
            - Physical Conditions
            - Programmatic Conditions The RI-ISI Living Program Evaluation at the end of the third 1SI interval noted the following issue being addressed in the RI-ISI application:
         *In 2015, the Wolf Creek Consequence Evaluation was revised. In the resulting revision, several segments changed consequence rank, causing many welds to change Risk Category and, in most cases, Risk Rank. Table 1 shows a brief summary how many welds changed Risk Rank, and how the Element Selection was updated.
_____ ____       Table_        __  _ _   _ _ _ _  _  _
Change in Risk Rank         Weld Count         Element Selection Low to Medium                259                28 added Medium to High                 16                 2 added Medium to Low                 17                1 removed During the update of the WCGS ISI Program in preparation for the fourth 1SI interval, various 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 Consequence Evaluation revision described above and other minor corrections using the applicable portions of the same RI process that originally established the RI 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 remained within the allowable bounds after incorporating 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.
A summary table of the welds in the RI-ISI Program showing all changes since the original RI-ISI application is provided in Table 2. A summary of the current WCGS PRA update is included in the Appendix to this Request.
Enclosure II to this submittal contains the completed gap assessment on the WCGS internal events probabilistic risk assessment. This assessment determined whether the current model of record meets the supporting requirements in Table 2-2 of EPRI TR 102467-A to support the WCGS 10-year RI-ISI update.

Attachment I to ET 16-0005 Page 5 of 11
: 6. Duration of Proposed Alternative This 10 CFR 50.55a Request is being proposed for use during the fourth inspection interval for WCGS that began on September 3, 2015 and ends on September 2, 2025.
: 7. Precedents The proposed alternative in this 10 CFR 50.55a Request was submitted to the NRC for approval for WCGS' third 10-year ISI interval as Request 13R-01 in WCNOC letter ET 06-0010, dated March 2, 2006 (ADAMS Accession No. ML060720142). This was supplemented by letters dated October 5 and December 20, 2006 (ET 06-0043 and ET 06-0058) (ADAMS Accession Nos. ML062910125 and ML063620090). NRC Approval was documented in a letter from D. Terao, USNRC, to R. A. Muench, WCNOC, 'Third 10-Year Interval Inservice Inspection Program Relief Request 13R-01 (TAC No.
MD0297)," February 21, 2007 (ADAMS Accession No. ML070260538).
: 8. References
: 1. Electric Power Research Institute (EPRI) Topical Report, TR-1 12657, Revision B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure," Final Report, December 1999.
: 2. ASME Code Case N-578-1, "Risk-Informed Requirements for Class 1, 2, and 3 Piping, Method B," Approved March 28, 2000.
: 3. NRC Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions On Plant-Specific Changes to the Licensing Basis,"
Revision 2, May 2011.
: 4. NRC Regulatory Guide 1.178, "An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping," Revision 1, September 2003.
: 5. NEI 04-05, "Living Program Guidance To Maintain Risk-Informed                Inservice Inspection Programs For Nuclear Plant Piping Systems," April 2004.

Attachment I to ET 16-0005 Page 6 of 11 Table 2 Inspection Location Selection Comparison Between ASME Section Xl Code and EPRI TR-112657 by Risk Category System
()   Category Risk Rank Consequence Rank     IDMs Failure Potential Rank IfCode Category 1 st Weld Approved RI-ISI Interval RI-ISI     Other (2) Weld New RI-ISI Interval ISIOhr2 2
Count                               Count        RISI        Ohr AB           4          Medium        High         None          Low       C-F-2      ---                              155            16              -
AB          6a            Low       Medium        None          Low      C-F-2    154              0-                                 --
AE AE(1) 2           High (High)      High TASCS (FAC)
Medium (High)
OF2 CF21
                                                                                         ---                               1 AE            2           High        High        TASCS        Medium     C-F-2    0              0()9          -                      6-AE            2           High        High           "1-T      Medium     C-F-2    0 (3           0~            -3       8             2-AE AE(1)     4         Medium (High)       Hih Hih(FAG)     None          Low (High)    CF2 CF2141      ---                              14             1 AE           4          Medium        High         None          Low      C-F-2    0-             0()4                                 1-AE       5a         Medium       Meim         TASCS        Medium     CF2       1 (3)         (High)                    (FAC)        (High)
AE       6a            Low (3AHih                  Medium        None          Low      C-F-2    108              0                    ----
AL          6a            Low       Medium        None          Low      C-F-2    0              o3)           -*     126             0-BB           2           High        High        TASCS,       Medium       B-J     11              3           -11                    3-
________              ___________         T                                                     ________              _______       ___l-r_
BB           2           High        High        TASCS        Medium       B-J      6              2           -6                     2-BB2                   High                      "I-,       Medium0                  40()0(40                                          4 BB(2)                (High)       High       (PWSCC)      (Medium)      B-F      ()0'-                                                           -
B-F    11(41          01(4)-
BB           2High                   High           "1-1      Medium                                                   19             6-B-J     20              6-BB4 BB(2)
Medium (High)
HihNone, Hih       (PWSCC)
Low (Medium)
B-F4)
B-3 0~            -(83

Attachment I to ET 16-0005 Page 7 of 11 Table 2 Inspection Location Selection Comparison Between ASME Section Xl Code and EPRI TR-112657 by Risk Category Risk                           Failure Potential              1 st  Approved RI-ISI Interval                  New Ri-ISI Interval Syst~em                          Con sequence                         Code                              _ _   _   _ _ _  _  _   _ _I 2
Iaeoy Rak          Rn          DMs         Rank   Category    onWeld       RI-ISI      Other( )       ConWeld      RISI         Ohr2 B-F     13(4           5 (4)-
BB          4        Medium         High       None         Low                                                        261            25 B-J     268             21-BB         6a         Low         Medium       None         Low      B-J       18             0----
BB         7a         Low           Low        None         Low      B-J        ---                                      18            0-BG          2         High          High      TASCS       Medium     B-J        9             2            -9                          3-BG          2         High          High        TT        Medium     B-J       9              3            -9                          2-B-J      26              3           -26                          3-BG          4        Medium         High       None         Low C-F-1     72              9            -73                         9-BG         5a        Medium       Medium        TTF      Medium      B-J       7              2----
B-J       12             0           -0                           0-BG         6a         Low         Medium       None        Low C-F-l     39              0           -39                          0-BG         6b         Low           Low         "1-1     Medium      B-J        -             -           -7                           0-B-J       0             0            -12                          0-BG        7a          Low           Low        None        Low C-F-i     18                                         16            0 BN          4        Medium         High       None        Low      C-F-i      3             0            -5                           0-BN         6a         Low         Medium       None        Low      C-F-i    122             0            -122                         0-EF        6a         Low         Medium       None        Low      C-F-2     26              0            -26                         0-

Attachment I to ET 16-0005 Page 8 of 11 Table 2 Inspection Location Selection Comparison Between ASME Section Xl Code and EPRI TR-112657 by Risk Category Risk                             Failure Potential            1 st Approved RI-ISI Interval         New RI-ISI Interval Syst~em             1           1Consequence                            Code Category       Rank           Rank        DMs         Rank   Category Weld         RI-ISI     Other (2) Weld      R-S             te     2 2
__   _   _- gyIIICount                                                                       Count     R-SI           ter EJ2Hg                      ihTASCS,             Medium     B-J      2           0              -2               0-EJ         2         High           High       TASOS       Medium     B-J      8           2             -8                2               -
B-J      4           1             -4                1               -
EJ         2High                    High         "U        Medium C-F-I    4            3             -5                3               -
B-J    22            3             -22               3               -
EJ         4        Medium          High        None         Low C-F-i  434            44            -432             44               -
B-J      2           0             -2                0               -
EJ        6a          Low          Medium       None         Low C-F-I     1           0             -1                0-EJ        7a         Low            Low         None         Low     C-F-1   47            0             -47               0-EM          2         High           High         Ui       Medium      B-J      8           0            -8                 0-B-J    20            3            -20                3-EM          4        Medium          High        None        Low C-F-i    2            0            -2                 0-EM         5a        Medium         Medium      IGSCC      Medium      B-J    20            2             -10               2-B-J   104            0             -82               0-EM         6a         Low           Medium       None        Low C-F-i  205            0             -220              0-EM         6b         Low            Low        IGSCC      Medium     C-F-I     0           0             -10               0-EM         7a         Low            Low         None         Low      B-J     0            0             -22               0-

Attachment I toET 16-0005 Page 9 of 11 Table 2 Inspection Location Selection Comparison Between ASME Section Xl Code and EPRI TR-112657 by Risk Category Systemn
()    Category Risk Rank Consequence Rank Failure Potential DMs          Rank J   Code Category 1 st Weld Approved RI-ISI Interval RI-ISI     Other  1 21 Weld New RI-ISI Interval RISI       Ohr2
                                             ~"I_____IjCount                                                                                  Count        RISI       Oer   2 C-F-1   38            0                        26             0 EN               6a            Low           Medium             None          Low          C-F-i   93            0            -128                       0-EN               7a            Low             Low              None          Low          C-F=-i   0             0           -9                         0-EP               4           Medium           High              None          Low           B-J    20            2            -20                        2-EP               5a          Medium          Medium            IGSCC        Medium          B-J    12            2            -12                        2-EP               6a            Low           Medium             None          Low           B-J    83            0            -89                        0-GS               7a            Low             Low              None          Low          C-F-2    2            0            -2                         0-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.

Attachment I to ET 16-0005 Page 10 of 11
: 3. Due to a change in ASME Section Xl 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 Code Case N-770-1 (MRP-1 39) as an augmented examination program.
PWSCC       = pressurized water stress corrosion cracking TASCS       = thermal stratification, cycling, and striping TT          = thermal transient FAC         = flow-accelerated corrosion

Attachment Ito ET 16-0005 Page 11 of 11 Appendix to 10 CFR 50.55a Request 14R-01 Wolf Creek Generating Station (WCGS) PRA Summary The WCGS probabilistic risk assessment (PRA) model used to evaluate the consequences of pipe rupture for the Risk-Informed Inservice Inspection (RI-ISI) Program assessment was the most current PRA model update. The WCGS PRA was originally developed to satisfy the requirement of Nuclear Regulatory Commission (NRC) Generic Letter 88-20 that each licensee perform an Individual Plant Examination (IPE) to search for plant specific severe accident vulnerabilities. The results of the WCGS PRA were submitted to the NRC, pursuant to this requirement, in September of 1992. The NRC issued a Staff Evaluation Report (SER) on the WCGS IPE Submittal in November of 1996. The SER on the IPE concluded that the WCGS PRA has met the intent of Generic Letter 88-20. Since completion of the WCGS IPE, the PRA model has been used to support numerous risk-informed applications. These include the following Technical Specification changes:
* Amendment No.155 "Increasing Flexibility in Mode Restraints (TAC No. MC2040)", issued October 7, 2004.
* Amendment No. 163 "Extended Diesel Generator Completion Times (TAC No. MC1257)",
issued April 26, 2006.
* Amendment No. 167 "Extended Containment Isolation Valve Component Times (TAC No.
MC3944)", issued September 28, 2006.
* Amendment No. 173 "Adopting TSTF-372 on Limiting Condition for Operation 3.0.8, Inoperability of Snubbers (TAC No. MD3816)", issued April 17, 2007.
In addition, the PRA model was used to support the Severe Accident Mitigation Alternatives Analysis performed as part of the Environmental Report submitted in WCGS' License Renewal Application (LIRA). This LRA was submitted on September 27, 2006. Renewed facility operating license No. NPF-42 was issued for WCGS on November 20, 2008.
In order to continue to use the PRA model as a tool to support plant programs, periodic updating of the model is necessary. The WCGS PRA model was recently updated in 2013 and again in 2015. These updates included numerous changes to the PRA model to reflect plant modifications, changes to plant specific and generic initiating event frequencies, import of initiating event frequencies for special initiators as fault tree solution files, changes to plant specific component failure rates and test and maintenance unavailability data, an in depth human reliability assessment, and expansion of the modeling scope for a number of systems previously modeled as single failure events.
The following WCGS PRA results were obtained with the updated model:
* Core Damage Frequency (CDF) = 2.98E-06/yr (excludes internal floods)
* Large Early Release Frequency (LERF) = 2.45E-07/yr As a result of the updates to the PRA model, both CDF and LERF lowered significantly.
However, the consequence rank of several individual segments did change, which resulted in an impact to the RI-ISI Program.

Attachment II to ET 16-0005 Page 1 of 6 Wolf Creek Nuclear Operating Corporation 10 CFR 50.55a Request 14R-02 Request for Relief from ASME Code Requirements Regarding Visual Examinations of Class I Supports, Other than Piping Supports

Attachment II to ET 16-0005 Page 2 of 6 10 CFR 50.55a Request Number 14R-02 Proposed Alternative In Accordance with 10 CFR 50.55a(z)(2)
Hardship or Unusual Difficulty Without a Compensating Increase in the Level of Quality or Safety
: 1. ASME Code Component(s) Affected ASME Code Class:           Code Class 1 Components:                Reactor Vessel Supports Component IDs:             RBB01-01 RBB01 -02 RBB01 -03 RBB01 -04
: 2. Applicable Code Edition and Addenda ASME B&PV Code, Section Xl 2007 Edition with 2008 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 percent of Class 1 supports, other than piping supports, be subject to a visual VT-3 examination once every inspection interval.
: 4. Reason for Request Pursuant to 10 CFR 50.55a(z)(2), relief is requested on the basis that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety. Conformance with the applicable inservice inspection requirements would necessitate a design modification to the reactor pressure vessel supports and associated insulation/walk plate to allow 100 percent 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.

Attachment II to ET 16-0005 Page 3 of 6 The Wolf Creek Generating Station (WCGS) 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 these 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.
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.
A design change to the reactor pressure vessel supports and associated insulation/walk plate to allow 100 percent visual examination of the subject supports would be an extensive and costly modification. 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 a hardship without a commensurate increase in quality or safety.
: 5. Proposed Alternative and Basis for Use In lieu of implementing the requirements of Table IWF-2500-1, Category F-A, Item No.
Fl1.40, 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.
: 6. Duration of Proposed Alternative This 10 CFR 50.55a request is being proposed for use during the fourth inspection interval for WCGS that began on September 3, 2015 and ends on September 2, 2025.
: 7. Precedents Previous WCGS Approvals:
10 CFR 50.55a Request 12R-14 was submitted to the NRC for WCGS' second 10-year ISI interval in WCNOC letter WM 95-01 29, dated August 30, 1995. NRC approval was

Attachment II to ET 16-0005 Page 4 of 6 documented in a letter from W. H. Bateman, USNRC, to 0. L. Maynard, WCNOC, "Second Ten-Year Interval Inservice Inspection Program Plan and Associated Requests for Relief, Wolf Creek Generating Station (TAC No. M93381     )," dated  October 24, 1997.
10 CFR 50.55a Request 13R-04 was submitted to the NRC for WCGS' third 10-year ISI interval in WCNOC letter ET 06-0010, dated March 2, 2006 (ADAMS Accession No. ML060720142). NRC approval was documented in a letter from D. Terao, USNRC, to R. A. Muench, WCNOC, "Wolf Creek Generating Station           -  Related to Relief Request No. 13R-04 for the Third 10-Year Interval Inservice Inspection (TAC No. MD0299)," dated June 16, 2006 (ADAMS Accession No. ML061320061).
Other Nuclear Plants Approvals:
10 CFR 50.55a Request No. RR-20 was submitted to the NRC for the H.B. Robinson Steam Electric Plant, Unit 2 in a letter from Duke Energy, dated June 3, 2013 (ADAMS Accession No. ML1317A006). This submittal was supplemented by letter dated January 21, 2014 (ADAMS Accession No. ML14028A260). NRC approval was documented in a letter from L. M. Regner, USNRC, to W. G. Gideon, Duke Energy Progress, Inc., "H.B.
Robinson Steam Electric Plant, Unit 2    -  Request for Relief (RR-20) From ASME Code, Section Xl for the Fourth 10-Year Inservice Inspection Interval (TAC No. MF1967),"
dated June 23, 2014 (ADAMS Accession No. ML14162A094).
10 CFR 50.55a Request No. IR-2-58 was submitted to the NRC for the Millstone Power Station, Unit 3 in a letter from Dominion Nuclear Connecticut, Inc., dated April 19, 2010 (ADAMS Accession No. ML101130187). This submittal was supplemented by letter dated January 20, 2011 (ADAMS Accession No. 110250259).                  NRC approval was documented in a letter from H. K. Chernoff, USNRC, to D. A. Heacock, Dominion Nuclear Connecticut, Inc., "Millstone Power Station, Unit No 3        -  Issuance of Relief Requests IR-2-51 through IR-2-60 Regarding Second 10-Year Interval Inservice Inspection Program Plan (TAC. Nos. ME3809 through ME3818)," dated April 26, 2011 (ADAMS Accession No. ML110691154).

Attachment II to ET 16-0005 Page 5 of 6 (SEE FIGURE 2)
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Attachment I1to ET 16-0005 Page 6 of 6 WAUCWA'Y OVER cue INgJLA ,'lION Rv S
                                    ,'PO0 --
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IN    *~EETE SECTION A-A FIG URE 2

Enclosure I Wolf Creek Generating Station Inservice Inspection Program Plan (200 Pages)

WCRE-3 0 REVISION 0 INSERVICE INSPECTION PROGRAM PLAN WOLF CREEK GENERATING STATION INTERVAL 4 Prepared By:     f*                                    /         11/12/15 Ralph Connell - ISI Coordinator                          Date Technical Review By:                                     /          11/12/15 Dennis Tougaw - 1ST Coordinator                         Date ANTI Review:                                   "                    11/16/15 Adam Grundleger - ANTI                                  Date Approval By:                           -~/                                   11/16/2015 Brian Dorathy - Supervisor                              Date Kay L Smith
                                                     * .*-.+.        Released by Document
                                                              *"''"*"Services. Release Date:
2015.11.23 16:49:09 -0600'

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN REVISION STATUS SHEET REVISION  AFFECTED PAGES             DESCRWPTION/COMMENTS 0           All                   Interval 4 Draft Issued For Final WCGS Review and Comment WCRE-30                ~~Page WCRE-30 1 of 41                                 Revision 0 Rvso

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE OF CONTENTS Section                                            Description                                                Pare REVISION STATUS SHEET................................................................................. 1 TABLE OF CONTENTS ...................................................................................... 2

==1.0     INTRODUCTION AND BACKGROUND==
 .................................................................. 4 1.1     Introduction 1.2     Background 2.0     BASIS FOR INSERVICE INSPECTION PROGRAM PLAN............................................. 7 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 Component/Component Support Scheduling 3.0      INSERVICE INSPECTION PROGRAM DESCRIPTION................................................ 22 3.1     ASME Section XI Requirements 3.2     Augmented ISI Requirements 3.3     ASME Section XI 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-30                                            ~Page WCRE-30 2 ofl                                            Revision 0 Reiio1

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE OF CONTENTS (Cont'd)
Effective Number Section                                        Description                                   of Pages in Section 4.0     WCGS SYSTEM INSERVICE INSPECTION PROGRAM PLANS...................................... 1 4.1     WCGS Systems Subject To Section XI NDE or Augmented NDE ............................... 1 4.1.1  Main Steam System (AB)................................................................... 7 4.1.2  Feedwater System (AE)..................................................................... 7 4.1.3  Auxiliary Feedwater System (AL) ......................................................... 6 4.1.4  Reactor Coolant System (BB)............................................................. 46 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) ..................................................... 14 4.1.11 High Pressure Coolant Injection System (EM)........................................... 11 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 TWA-S5110(c)................ 1 Tables Table 4.2-1    System Pressure Testing Procedures Attachments Attachment A Assessment of the Surface Condition of Dissimilar Metal Welds ....................... 3 WCRE-30                                          ~~Page WCRE-30 3 ofl                                                Revision 0 Reiio1

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN

==1.0   INTRODUCTION==
AN]) BACKGROUND

==1.1      INTRODUCTION==

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 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.
The 1S1 Program Plan was developed and is controlled by Wolf Creek Administrative Procedure AP 29A-002. This 1S1 Program Plan is effective from September 3, 2015 through September 2, 2025, which represents Wolf Creek's Fourth 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 the Containment Inservice Inspection Program Plan which is in accordance with Wolf Creek Administrative Procedure AP 29A-005.

==1.2     BACKGROUND==

A Construction Pernit 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, NPF-42, was issued on June 4, 1985 anid 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 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 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 10OCFR 50.55a in effect at that time referenced ASME Section XI, 1980 Edition with Addenda through the Winter 1981 Addenda (Section XI 80/W81) in paragraph (b)(2). The extent of the application of Section XI 80/W8 1 was limited by paragraph (2)(iv)(A) such that Section XI, 1974 Edition with Addenda through Summer 1975 Addenda (Section X1 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 X1 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.
Based on these 10 CFR 50.55a mandatory and optional requirements, the WCGS Section XI ISI Program Plan for the initial ten year interval was developed and documented in WCRE-07, Wolf Creek Generating Station ISI Program Plan Document.
WCRE-30                                1.0 Introduction and Background                             Revision 0 Page 4of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 1.2.2    Second Interval 1SI Program Pursuant to the Code of Federal Regulations, Title 10, Part 50, Section 55a, Codes and standards, (10CFR 50.55a), WCGS 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 XI, 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 XI174/S75 to examine ASIME Code Class 1 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 and documented in WCRE-1 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 1 and 2 piping welds. The RM-SI 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 1 and 2 piping welds (i.e., Examination Categories B-F, B-J, C-F-l and C-F-2 only). The RI-SI 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 was addressed in WCGS Basis Document No. WCRE-12.
1.2.3    Third Interval ISI Program Pursuant to the Code of Federal Regulations, Title 10, Part 50, Section 55a, Codes and standards,(10CFR 50.55a), WCGS 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, 2004 referenced ASME Section XI, 1998 Edition with Addenda through 2000 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 1 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 third ten year interval was developed and documented in WCRE-l16, Wolf Creek Generating Station Third Interval ISI Program Plan.
During the third interval, WCGS continued the implementation of a Risk Informed ISI (RI-ISI) Program Plan for ASME Code Class 1 and 2 piping welds.
WCRE-30                        1.0 Introduction and Background                             Revision 0 Page 5 of4l

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN The RI-ISI template submittal was approved by the NRC in the safety evaluation contained in a letter dated February 21, 2007 from the USNRC to Rick Muench (incoming correspondence 07-00115).
The scope of the RI-ISI program is limited to ASME Code Class 1 and 2 piping welds (i.e., Examination Categories B-F, B-J, C-F-i and C-F-2 only). The RM-SI program was developed in accordance with the methodology contained in the Electric Power Research Institute (EPRI) Topical Report (TR) EPRI TR-l112657, Revision B-A. Application of the R1-IS1 methodology was addressed in the WCGS Risk Informed Inservice Inspection Basis Document, WCRE-12.
1.2.4    References To The ISI Program Plan In Other WCGS Programs The examinations and tests performed in accordance with this 1S1 Program Plan and previous interval ISI program Plans support other WCGS Programs as follows:
1.2.4.1 USAR Section 18.3.4, Integrity of Systems Outside of Containment This USAR Section addresses the WCNOC Response to the NRC's Guidance Per NUREG-0737. The WCNOC response is included in Section 18.3.4.2, which references the ASME Section XI Inservice Inspection Program in Item 3.
1.2.4.2 USAR Chapter 18 Appendix A, License Renewal Commitments This USAR Appendix includes references to the ASME Section XI Inservice Inspection Program in Sections AI.l, A1.3, A1.7, A1.19, and A1.29.
1.2.4.3 Technical Requirements Manual The Technical Requirements Manual includes a reference to the Inservice Inspection Program in Section 5.5.6.
WCRE-30                         1.0 Introduction and Background                        Revision 0 Page 6 of 41

WOLF CREEK GENERATING STATION FOURTH 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 Fourth 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 Fourth Interval 1SI Program Update include the 10CFR50.55aFinal Rules published November 5, 2014 (79FR65776), and December 11, 2014 (7973461). The Final Rule published November 5, 2014 was effective December 5, 2014 and incorporated by reference ASME Section XI, 2007 Edition with the 2008 Addenda in paragraph (b)(2); this Final Rule included a maj or reformatting of 10CFR50.55a and also incorporated by reference Regulatory Guide 1.147, Revision 17. The Final Rule published December 11, 2014 was effective December 11, 2014 and included minor technical corrections.
Twenty nine (29) conditions are included in 10OCFR50.55a(b)(2) and are numbered (i) to (xxix).
In addition, six (6) conditions are included in 10OCFR50.55a(b)(3)(v). Each of these conditions were 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 XI 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 4", WCRE-32.
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) ISI program for WCGS once every ten year interval. The ISI 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 Fourth ISI Interval is defined to be from September 3, 2015 to September 2, 2025. Accordingly, based on a "lock in" date of September 3, 2014, the 2007 Edition with the 2008 Addenda of ASME Section XI is the version of Section XI that WCGS must meet for Fourth Interval.
Note that on the "lock in" date, September 3, 2014, the Final Rules listed in 2.1 above were not published. Accordingly, the version of 10CFR50.55a published in the Code of Federal Regulations on January 1, 2014 was utilized to determine the Fourth Interval Code of Record for WCGS, the 2007 Edition with the 2008 Addenda of ASME Section XI. This version of the Code of Federal Regulations included all Final Rules published up to and including September 3, 2014.
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WOLF CREEK GENERATING STATION FOURTH IThfERVAL ISI PROGRAM PLAN 2.1.3     ASME Section XI Code Cases Per 10 CFR 50.5 5a(g), ASME Section XI 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 "inser-vice Inspection Code Case Acceptability-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(z). The ASME Section XI Code Cases incorporated into the WCGS IST Program Plan are listed and discussed in Section 3.3.
2.1.4     Requests For Relief and Requests For Alternatives In cases where WCNOC has determined that ASMiE Section XI requirements are impractical to implement or has determined an altemnative 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(z)(l) or 10 CFR 50.55a(z)(2), as applicable.
Guidance for the preparation of 10 CFR 50.55a Requests was taken from Nuclear Energy Institute (NEI) White Paper "StandardFormatfor Requests from CommercialReactor Licensees Pursuantto J0 CFR 50.55a", Revision 1 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 CER 50.55a(g)(5)(iii). The submittal of this information will be referred to in this document as a Request for Relief.
The NET 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 altemnatives 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(z)(1) and 10 CFR 50.55a(z)(2), respectively. The submittal of this information will be referred to in this document as a Request for Alternative.
Per 10 CER 50.55a paragraphs and (g)(6)(i) and (z), the Director of the Office of Nuclear Reactor Regulation will evaluate Requests for Relief and Requests for Altemnatives per Paragraph (g)(5) and "..may grant such relief and may impose such altemnative 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 4 Requests for Relief and Requests for Altemnatives are included in Section 3.4.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 2.2      Augmented ISI Requirements In accordance with 10 CFR 50.55a(g)(6)(ii), the NRC may require a licensee to follow an augmented inservice inspection program for systems and components for which they deem an added assurance of structural reliability is necessary.
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 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 Condition Report (CR) 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 The following text provides 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 4 is addressed by Request for Alternative No.
I4R-0 1. The 4 th Interval Risk-Informed Program Plan is presented in WCRE-3 1.
2.3.1    Initial RI-ISI Application ASME Section XI Examination Categories B-F, B-J, C-F-1, and C-F-2 originally contained the requirements for the nondestructive examination (NDE) of Class 1 and 2 piping welds. In 2001, a risk-informed methodology for the inservice inspection of Class 1 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."
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 Decision making Inservice Inspection of Piping".
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WOLF CREEK GENERATING STATION FOURTH TINTERVAL ISI PROGRAM PLAN The original RI-ISI template, "Risk-Informed Inservice Inspection Program Plan - Wolf Creek Generating Station (Revision 0)" was submitted to the NRC for approval per 10CFR50.55a(a)(3)(i) in Letter No. ET 01-0009, dated February 15, 2001. 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 in Letter No. 01-00965, dated December 13, 2001 (TAC No. MB 1206). 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- 112657 provides the requirements for defining the relationship between the RI-ISI program and the remaining unaffected portions of ASME Section XI.
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 I tasks are provided in the following paragraphs.
Task 1: Scope and Exemption Determination Per EPRI TR-l112657 and ASME Code Case N-578, the EPRI risk-informed 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 and 2 systems. This corresponded to ASME Section XI Examination Categories B-F, B-J, C-F-l, 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 addressed in 1WB-1220 and IWC-1220, were not affected. Therefore, piping that was previously exempted per ASME Section XI remained exempt in the RI-ISI application.
Task 2: Conseqiuence 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).
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Results of the consequence evaluation were ultimately summarized in the risk ranking tables that are discussed in Task 5.
Task 3: Deuradation 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- 112657. Once the degradation mechanisms were assigned to each piping segment in accordance with the EPRJ 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 checklist 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.
TABLE 2.3-1 DEGRAIDATION MECHANISM CATEGORIES Flow Accelerated Corrosion (FAG)
HIGHargeWater                                Hammer<'&deg; Thermal Fatigue (TASCS, Thermal Transients)
Stress Corrosion Cracking (IGSCC, TGSCC, MEDIUMSmallPWSCC,                                 ECSCC)
Localized Corrosion (MIC, Crevice Corrosion and Pitting)
Erosion-Cavitation No Degradation Mechanisms LOW                 None                                  Present (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 hanmmer events. Various plant documents were reviewed as part of this effort including Outage Summary Reports, Licensee Event Reports (LERs), and corrective action documents.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 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.
TABLE 2.3-2 RI-ISI RISK MATRIX Consequence Assessment                                    CONSEQUENCE CATEGORY
                                          ~CCDP                     and CLERP Potential Failure Potential                                  NONE          LOW        MEDIUM         HIGH Assessment                             f r* *HGH             LOW        MEDIUM           *.i'     _____"G.".
o           IH           (Cat. 7)      (Cat. 5)     ,          ___
uJ                       _    _     _  _     _    _ _        _ _  _
z    2       EDU            LOW           LOW        MEDIUM         HG OEDIU                (Cat. 7)      (Cat. 6)     (Cat. 5)    *.L2
                                      ,ow2           ,ow           Low            Low     MEDIUM O    ..      LO            (Cat. 7)      (Cat. 7)     (Cat. 6)    (Cat. 4) w*
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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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Task 7: Risk Impact Evaluation Once the element selection under Task 6 was completed, the new set of locations that will be inspected under the RI-ISI program were compared to the locations that were inspected per ASME Section XI prior to the application of the RI-S I methodology. A 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 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 inspection program result in either negligible increases in Core Damage Frequency and Large Early Release Frequency or actual decreases in the risk measurements. The risk impact evaluation was performed using a simplified risk quantification method as described in EPRI TR-l112657, 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: Program Submittal/Risk-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 recomimendations as determined by the RI-ISI application, and was prepared in accordance with a template for risk-informed inservice 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- 112657. 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-S I examinations in accordance with the Topical Report for Class 1 and 2 piping welds.
2.3.3    Examination Categories and Code Item Numbers As previously discussed, the requirements of EPRI Topical Report No. TR-1 12657 supersedes those of ASIME Section XI for Class 1 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-I1, and C-F-2) have been superseded. Since TR-1 12657 does not provide new Examination Category and Code Item Numbers, the format from ASME Section XI Code Case N-578-1 (now incorporated into ASME Section XI, Nonmandatory Appendix R) is utilized for the assignment of these new numbers. As such, Class 1 and 2 piping welds have been reassigned to Examination Category R-A and Code Item Nos. R1 .10 through R1 .20, as applicable.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 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 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" was developed. As part of the ISI Program Update for Interval 4, a RI-ISI Living Program Evaluation was performed.
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 WCRE-30                     2.0 Basis For Inservice Inspection Program Plan                       Revision 0 Page 14 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN During the update of the Wolf Creek 1S1 program in preparation for the fourth 151 interval, changes to the PRA, as documented in PSA-15-001, were identified. A number of these changes were in the conservative direction (i.e., Medium Consequence to Low Consequence), the rest of the changes involved moving from Low Consequence to Medium Consequence and from Medium Consequence to High Consequence.
Welds within Risk Segments which changed from Low to Medium Consequence went from a 0% required selection regime to a 10% required selection regime. Similarly, welds within Risk Segments which changed from Medium to High Consequence went from a 10% required selection regime to a 25% required selection regime. Finally, Risk Segments which changed from Medium to Low Consequence went from a 10%
required selection regime to a 0% required selection regime.
As a result of these identified changes, an Element Selection was held to select additional welds for examination as required. More information about these required changes can be obtained in WCRE-3 1.
No other programmatic changes were identified which resulted in the need to change the examination selection.
2.3.4.1 RI-ISI Program Ongoing Commitment In the response to an RAI to the initial RM-SI application, Wolf Creek conmmitted 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 RM-SI 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.
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WOLF CREEK GENERATING STATION FOURTH 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 pennitted. 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 the different methods of: VT-l, VT-2, VT-3, and VE.
The VT-1 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 affect operability or functional adequacy of constant load and spring type supports.
The VE examination is conducted per the augmented requirements of Code Cases N-722-1, N-729-1 and N-770-1, with the conditions of 10 CFR 50.55a(g)(6)(ii)(D), (E) and (F).
All Visual examinations are conducted per Article 9 of ASME Section V and the additional requirements of 1WA-22 10, or as required by the augmented program.
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 1S1 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 XI, paragraph IWA-2221. The examination of coated materials is conducted in accordance with Appendix I of Article 7 of ASME Section V.
Liquid penetrant examinations are conducted per Article 6 of ASME Section V, as required by ASME Section XI, paragraph 1WA-2222.
Eddy current examinations are conducted per Appendix lV, as required by ASME Section XI, paragraph IWA-2223, or as required by the augmented program.
Volumetric 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, or as required by the augmented program.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN For welds in the RI-ISI program, the volume inspected shall be per the recommendations of EPRI TR-l112657 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.
Examination 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 VIII. 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 (Note 1 and Note 2)
Procedure Number          J          Procedure Title QCP 20-50 1                    Solvent Removable Visible Dye Liquid Penetrant Examination QCP 20-502                     Magnetic Particle Examination AC/DC Yoke and AC Coil Techniques 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 QCP 20-541                     VT-3 Visual Examination PDI-UT-1                      PDI Generic Procedure for the Ultrasonic Examination of Ferritic Pipe Welds PDI-UT-2                      PDI Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds PDI-UT-3                      PDI Generic Procedure for Ultrasonic Through Wall Sizing in Pipe Welds PDI-UT-4                      PDI Generic Procedure for Ultrasonic Examination of Studs and Bolts From the Bore PDI-UT-5                      PDI Generic Procedure for Straight Beam Ultrasonic Examination of Bolts and Studs PDI-UT-6                      PDI Generic Procedure for the Ultrasonic Examination of Reactor Pressure Vessel Welds PDI-UT-7                      PDI Generic Procedure for the Manual Ultrasonic Through Wall and Length Sizing of Ultrasonic Indications in Reactor Pressure Vessel Welds WCRE-30                      2.0 Basis For Inservice Inspection Program Plan                         Revision 0 Page 17 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL IS1 PROGRAM PLAN TABLE 2.4-1 (Continued)
EXAMINATION PROCEDIJRES
[Procedure   Number                 Procedure Title PDI-UT-8                     PDI Generic Procedure for the Ultrasonic Examination of Weld Overlaid Similar and Dissimilar Metal Welds PDI-UT-l10                    PDI Generic Procedure for the Ultrasonic Examination of Dissimilar Metal Welds PDI-UT-1 1                    PDI Generic Procedure for the Ultrasonic Detection and Sizing of Reactor Pressure Vessel Nozzle to Shell Welds and Nozzle Inner Radius MT-7                      Magnetic Particle Examination PT-li                      Liquid Penetrant Examination UT-3                      Ultrasonic Examination of Nozzle Inner Radius Areas UT-il                      Ultrasonic Examination of Reactor Vessel Stud Hole Threads UT-92                      Ultrasonic Examination of Weld Overlaid Austenitic Pipe Welds UT-94                      Ultrasonic Examination of Ferritic Pipe Welds UT-95                      Ultrasonic Examination of Austenitic Piping Welds UT-96                      Ultrasonic Through Wall Sizing in Piping Welds UT-97                      Straight Beam Ultrasonic Examination of Bolts and Studs UT-98                      Ultrasonic Examination of Reactor Pressure Vessel Closure Head Welds and Adjacent Base Metal UT-99                      Manual Through Wall and Length Sizing of Ultrasonic Indications in Reactor Pressure Vessel Welds UT-100                     Ultrasonic Thickness Measurements and Surface Contouring UT-101                     Ultrasonic Examination of Reactor Coolant Pump Flywheels UT-103                     Ultrasonic Examination of Dissimilar Metal Piping Welds UT-105                     Ultrasonic Examination of Nuclear Coolant System Cast Austenitic Piping UT-i110                    Ultrasonic Examination of Vessel Welds and Adjacent Base Metal >
2.0" in Thickness UT-i1i2                    Ultrasonic Examination of Vessels Less Than 2" in Thickness PDI-ISI-254-SE-NB                Remote Inservice Examination of Reactor Vessel Nozzle to Safe End, Nozzle to Pipe, and Safe End to Pipe Using the Nozzle Scanner WDI-STD-101                    Head Vent J-Weld Eddy Current Inspection Procedure WDI-STD-1 14                   Head Vent ID Eddy Current Inspection Procedure WDI-STD-1 040                   Procedure for Ultrasonic Examination of Reactor Vessel Head Penetrations WDI-STD- 1041                   Reactor Vessel Head Penetration Ultrasonic Analysis Guidelines WCRE-30                    2.0 Basis For Inservice Inspection Program Plan                        Revision 0 Page 18 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE 2.4-1 (Continued)
EXAMINATION PROCEDURES
[Procedure Number         [Pr       ocedure Title WDI-STD-1042                     Procedure for Eddy Current Examination of Reactor Vessel Head Penetrations WDI-STD-146                     ET Examination of Reactor Vessel Pipe Welds Inside Surface WCAL-002                       Pulser / Receiver Linearity Procedure WDI-CAL-102                     Calibration Procedure for PCI Eddy Current Card LMT-07-PAUT-005                    Performance of Phased Array Instrument Screen Height and Amplitude Control Linearity Checks LMT-10-PAUT-002                    Manual Phased Array Ultrasonic Examination of Austenitic and Ferritic Piping Welds Notes:
: 1. The above Table is a list of currently approved procedures utilized for 1S1 examinations at WCGS. Each examination data record has the procedure and revision documented on that record.
In addition, the vaulted surveillance procedures (i.e. STS PE-300, STS PE-040-H) have a list of the examination procedures attached. These vaulted records and previous revisions of this document may be referenced to obtain historical information on examination procedures utilized.
: 2. The 1SI Engineer shall verify that the procedures utilized are the current revision.
2.5      Personnel Qualification Requirements Personnel performing nondestructive (NDE) examinations shall be qualified and certified using a written practice prepared in accordance with ANSI!ASNT CP-l189, dated 1995, as required by IWA-2300 of Section XI and as modified by 10 CFR50.55a(b)(2)(xviii).
Personnel performing Appendix VIII ultrasonic examinations shall meet the qualification requirements of Appendix VIII as modified by 10CFRS0.55a(b)(2)(xiv).
Personnel performing visual examinations or using other NDE methods not addressed in ANSI/ASNT CP-1 89, shall be qualified as defined in ANSI/ASNT CP-1 89 or the ASNT Central Certification Program (ACCP) and the Employer's written practice.
2.6      Inspection Intervals and Inspection Scheduling Inspection Intervals Per IWA-2430(a) of ASME Section XI, the inservice examinations and system pressure tests required by IWB, ]IWC, IWD and the inservice examinations and tests of LWF shall be completed during each of the inspection intervals for the service lifetime of the plant. The inspections shall be performed in accordance with the schedule of the Inspection Program of IWA-243 1.
Per IWA-2430(b), the inspection interval shall be determined by calendar years following placement of the plant into commercial service.
WCRE-30                      2.0 Basis For Inservice Inspection Program Plan                      Revision 0 Page 19 of4l

WOLF CREEK GENERATING STATION FOURTH INTERVAL IST PROGRAM PLAN Per IWA-2430(c), for components inspected under the Inspection Program of LWA-243 1, the following shall apply:
(1) Each inspection interval may be reduced or extended by as much as 1 year. Adjustments shall not cause successive intervals to be altered by more than one year from the original pattern of intervals. If an inspection interval is extended, neither the start and end dates nor the inservice inspection program for the successive interval need be revised.
(2) Examinations may be performed to satisfy the requirements of the extended period or interval in conjunction with examinations performed to satisfy the requirements of the successive period or interval. However, an examination performed to satisfy requirements of either the extended period or interval or the successive period or interval shall not be credited to both periods or intervals.
(3) That portion of an inspection interval described as an inspection period may be reduced or extended by as much as 1 year. This adjustment shall not alter the requirements for scheduling inspection intervals.
(4) The inspection interval for which an examination was performed shall be identified on examination records. Adjustments shall not cause successive intervals to be altered by more than one year from the original pattern of intervals.
Per IWA-2430(d), in addition to the interval adjustment allowed per IWA-2430(c), 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 IWA-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 1 components, Class 2 components, Class 3 components, and Class 1, 2, and 3 component supports, respectively.
Per IWB-24 10, inservice examinations and system pressure tests of Class 1 components may be performed during plant outages such as refueling shutdowns or maintenance shutdowns.
The term"ma" allows the examinations and system pressure tests to be performed during system operation. Per IWC-24 10, IWD-24 10, and IWF-24 10, 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-24 11, IWC-24 11, IWD-24 11, and IWF-2410. These paragraphs reference Tables IWB-241 1-1, IWC-241 1-1, IWD-241 1-1, and IWF-24 10-1, which include minimum and maximum percentages of examinations required to be completed by inspection period. Table 2.6-1 summarizes this information for Interval 4 at Wolf Creek.
Per IWB-241 1, examinations listed in IWB-241 1(a)(1) to IWB-241 1(5) as specified in Table TWB-2500-1 are not required to meet the criteria in Table IWB-241 1-1.
Per IWC-241 1, examinations listed in IWC-241 1(a) as specified in Table 1WC-2500-1 are not required to meet the criteria in Table IWC-24 11-1.
Per IWD-24 11, examinations listed in IWD-24 11(a) as specified in Table IWD-2500-1 are not required to meet the criteria in Table IWD-24 11-1.
WCRE-30                       2.0 Basis For Inservice Inspection Program Plan                      Revision 0 Page 20 of41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Per IWB-241 1, 1WC-24 11 and IWD-24 11, 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 in any one period if there is only one item or component, in lieu of the requirements of Tables IWB-24 11-1, Tables IWC-24 11-1 and Tables 1WD-24 11-1, respectively.
TABLE 2.6-1 INSPECTION PROGRAM COMPONENT/COMPONENT SUPPORT SCHEDULING INSPECTION          INSPECTION PERIOD,           I       MINIMUM           I      MAXIMUM INTERVAL            CALENDAR YEARS OF IEXAMINATIONS                           EXAMINATIONS PLANT SERVICE             jCOMPLETED, % [COMPLETED, %1 4             316                                                 50 4                        37                           501                      75 4                        40                           100                      100 1If 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 2007 Edition with the 2008 Addenda of Section XI, Tables IWB-2500-1, IWC-2500-1, IWD-2500-l and IWF-2500-1, respectively, except for Categories B-F, B-J, C-F-l1, and C-F-2 welds which were selected in accordance with the RI-ISI Program requirements. The basis for selection of RM-SI welds is documented in 10 CFR 50.55a Request Number I4R-0 1.
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, 2007 Edition with the 2008 Addenda of Section XI. 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 IWA-4000 of ASMvE Section XI, 2007 Edition with the 2008 Addenda. XI and are implemented by WCGS Procedure AP 16A-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, repairs and replacements will be in accordance with Article IWA-6000 of ASME Section XI, 2007 Edition with the 2008 Addenda as modified by Code Case N-532-5.
WCRE-30                       2.0 Basis For Inservice Inspection Program Plan                       Revision 0 Page 21 of41

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 3.0     INSERVICE INSPECTION PROGRAM DESCRIPTION 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.
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 sunmnary of the IS1 Program Plan. Sections 3.3 and 3.4 include supporting details for ASME Section XI Code Cases and Requests for Relief and Requests for Alternatives Requests From ASME Section XI Requirements, respectively. Sections 3.5 through 3.11 provide additional information that describe and support this 181 Program Plan.
3.1       ASME Section XI Requirements Based on an ASME Section XI Code of Record "lock-in" date of September 3, 2014 (one year prior to the 4th Interval start date) and 10CFR50.55arequirements in effect at that time, this 1S1 Program Plan was developed in accordance with the requirements in the 2007 Edition with the 2008 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Subsections IWA, IWB, IWC, IWD, IWE, Mandatory Appendices, and the Inspection Program of IWA-243 1, except as follows:
NOTE: As delineated in AP 29A-002, the requirements for implementation of ASME Section XI, 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, that is governed by administrative procedure AP 29A-005.
3.1.1    Code of Federal Regulations Conditions The following mandatory and optional Code of Federal Regulations Conditions were included in 10CFR50.55a as of September 3, 2015. Only those 10CFR50.55a Conditions applicable to the 2007 Edition with the 2008 Addenda of Section XI are listed. These Conditions were reviewed for inclusion in the 1S1 Program and dispositioned as follows:
3.1.1.1     WCGS will not utilize the option in 10CFR50.55a(b)(2)(ii) to examine Class 1 piping per ASME Section XI, 1974 Edition with the Summer 1975 Addenda.
3.1.1.2     As required by 10CFR50.55a(b)(2)(x), WCGS will apply the station 10OCFR50 Appendix B Quality Assurance Program to Section XI activities.
3.1.1.3     As allowed by 10CFR50.55a(b)(2)(xiv), WCGS will use the annual practice requirements in VII-4240 of Appendix VII of Section XI in place of the 8 hours of annual hands-on training discussed in the first sentence of 10OCFR50.55a(b)(2)(xiv). As required by 10OCFR50.55a(b)(2)(xiv), if implementing the option in the first sentence, the annual practice requirements at WCGS will be performed on material or welds 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.
3.1.1.4     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-23 14(a) and IWA-23 14(b) of the 2007 Edition with the 2008 Addenda of Section XI WCRE-30                                    3.0 - 1S1 Program Description                             Revision 0 Page 22 of 4l

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 3.1.1.5      As required by 10CFR50.55a(b)(2)(xix), the provisions in LWA-4520(b)(2) and IWA-4521of the 2008 Addenda will not be used by WCGS.
3.1.1.6      As required by 10CFR50.55a(b)(2)(xx)(B), WCGS will apply the rules in IWA-4540(a)(2) of the 2002 Addenda of Section XI when performing system leakage tests after repair and replacement activities performed by welding or brazing on a pressure retaining boundary 3.1.1.7      As required by 10CFR50.55a(b)(2)(xxi)(A), the provisions of Table 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, Steam Generator Nozzle Inside Radius Section, of Inspection Program B in the 1998 Edition will be applied by WCGS. As allowed by 10CFR50.55a(b)(2)(xxi)(A), a visual examination with magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria in Table IWB-35 12-1, 2007 Edition with the 2008 Addenda, with a limiting assumption on the flaw aspect ratio (i.e., a/l=0.5), may be performed in place of an ultrasonic examination.
3.1.1.8      As required by 10CFR50.55a(b)(2)(xxii), WCGS will not apply the rules in IWA-2220, "Surface Examination," of Section XI, 2007 Edition with the 2008 Addenda that allow use of an ultrasonic examination method.
3.1.1.9      As required by 10CFR50.55a(b)(2)(xxvii), When performing visual examination in accordance with 1WA-5241 of Section XI of the ASME B&PV Code, 2007 Edition with the 2008 Addenda WCGS will remove insulation from 17-4 PH or 410 stainless steel studs or bolts aged at a temperature below 1100 0F or having a Rockwell Method C hardness value above 30, and from A-286 stainless steel studs or bolts preloaded to 100,000 pounds per square inch or higher.
3.1.1.10 As required by 10CFR50.55a(b)(2)(xxviii) WCGS will implement the following conditions when implementing Equation (2) of A-4300(b)(l) of Appendix A:
For R < 0, AKI depends on the crack depth (a), and the flow stress (of). The flow stress is defined by of= 1/2(o-ys + oult), where o-ys is the yield strength and oult is the ultimate tensile strength in units ksi (MPa) and a is in units in. (mam). For -2
        < R <0and Kmax -Kmin <0.8 x 1.12 of'1(xa), S~ l1and AKI =Kmax. For R<
        -2 and Kmax -Kmin < 0.8 x 1.12 of4*(na), S = 1 and AKI = (1 - R) Kmax/3.
For R< 0 and Kmax -Kmin > 0.8 x 1.12 of4l(2a), S5 1 and AKIl=Kmax -
Kmin.
3.1.1.11 As required by 10CFR50.55a(b)(2)(xxix), when implementing Nonmandatory Appendix R, "Risk-Informed Inspection Requirements for Piping," of Section XI, 2007 Edition with the 2008 Addenda, WCGS will request and receive prior NRC authorization of this proposed altemnative in accordance with paragraph 10CFR50.55a(z)(1).
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 3.1.2    ASMIE Section XI Code Cases Incorporated In The ISI Program Alternatives to ASME Section XI that are provided in Code Cases may be incorporated into the 1S1 Program as described below.
3.1.2.1 Section XI Code Cases Approved and Conditionally Approved in 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 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 10 CFR 50.55a(z). Code Cases being incorporated by WCGS during the fourth 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 1SI Program via a Request for Alternative or Request for Relief submitted to the NRC in accordance with 10 CFR 50.55a(z) or 10CFR50.55a(g)(5), respectively. Those alternatives being incorporated by WCGS during the fourth interval by a 10CFR50.55a Request are addressed in Section 3.4.
3.2     Augmented 1SI Requirements Augmented inservice inspection programs address examinations that go beyond what is required by ASME Section XI. 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 XI. Described below are the augmented ISI commitments at WCGS for the fourth 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.
3.2.1.1 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 These USAR Sections describe that WCGS complies with either USNRC Branch Technical Position MEB 3-1, or as required per the Risk-Informed 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. 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.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN The applicable welds are shown on the Main Steam (AB), Feedwater (AE),
Reactor Coolant (BB), Chemical and Volume Control (BG), Steam Generator Blowdown (BM), and Auxiliary Feedwater Pump Turbine (FC) System Isometrics listed in Sections 4.1.1, 4.l.2, 4.l.4, 4.1.5, 4.1.6, and 4.l.14, respectively, within the "No Break Zone" and included in the respective Component and Component Support Selected/Scheduled for Examination Tables.
Wolf Creek has implemented a Risk-Informed High Energy Line Break Program.
This program is maintained in WCRE-33, 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 Inteigrity 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 Item 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 0-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 XI or an approved alternative (e.g., approved Code Case or Request for Alternative). For the fourth interval, examinations on the Reactor Vessel Closure Studs will be conducted in accordance with Examination Category B-G-l, 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-l, BB-2 and BB-3.
3.2.1.4 USNRC Regulatory Guide 1.137, Revision 0 - Fuel-Oil Systems for 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 implementation of the testing and VT-2 examinations required by Articles 1WD-2000 and IWD-5 000 of ASME Section XI, 2007 Edition with the 2008 Addenda.
3.2.1.5 USNRC Regulatory Guide 1.150, Revision 1-Ultrasonic Testin2 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. 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 XI for those reactor vessel components that are examined in accordance with Article 4 of Section V.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN However; 10OCFR50.55a requires that, with the exception of the shell-to-flange weld and the head-to-flange weld, that the examination of the Reactor Vessel Welds be conducted in accordance with Appendix VIII. Although this Regulatory Guide was withdrawn by the NRC on February 11, 2008 based on full implementation of Appendix VIII (see Federal Register Volume 73, No. 28, Page 7766), this withdrawal does not, in and of itself, alter any prior or existing licensing commitment based on its use. Since the prescriptive guidance in Regulatory Guide 1.150 is not in total agreement with the Appendix VIII requirements, Regulatory Guide 1.150 remains applicable for the examination of the reactor vessel components that are not examined in accordance with Appendix VIII.
3.2.2    WCGS Augmented ISI Requirements The following augmented inservice inspection requirements are those resulting from WCGS commitments other than 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 Pressurizer Nozzle Weld Overlays In Interval 3, a full structural weld overlay was performed on the pressurizer nozzles-to-safe end dissimilar metal (DM) welds and the adjacent stainless steel (SS) safe end-to-piping welds. WCNOC revised the original commitment made in I3 R-05 as follows: Subsequent inservice examination of full structural repair weld overlays on the Pressurizer nozzle welds will be in accordance with the 2004 Edition with 2005 Addenda of ASME Section XI, Appendix Q, Q-4300 as prescribed in WCNOC Request I3R-05, Rev. 1 Table 5, page 27 of 28, attached to WCNOC letter ET 06-0044 dated October 2, 2006. Subsequent inservice examinations of preemptive full structural weld overlays on the Pressurizer nozzle welds will be as prescribed in WCNOC Request I3R-05, Rev. 1 Table 5, page 27 of 28, attached to WCNOC letter ET 06-0044 dated October 2, 2006.
Regulation 10 CFR 50.55 a requires that Class 1 DM welds be examined in accordance with Code Case N-770-
: 1. This includes welds mitigated by WOL. The examinations performed in accordance with I3R-05 also meet the examination requirements of Code Case N-770-l, Items C and F, as applicable.
Table 3.2.2.3-1 provides a listing of the location and designation of each of the overlaid welds. Table 3.2.2.3-2 lists the welds broken out into "Repair" or "Preemptive" categories. The Notes below are applicable to both tables.
Notes:
: 1. Full structural REPAIR weld overlay due to indications found.
: 2. Full structural REPAIR weld overlay due to <90% of required examination volume coverage.
: 3. PREEMPTIVE full structural weld overlay.
Table 3.2.2.3-1 Pzr location                          DM Weld!                          Associated Stainless weld!
Overlay Weld#                              Overlay weld#
Surge nozzle                       TBB03-1-W (1)                             BB-01-F004B (3)
_________                       MW7090-WOL-DM                             MW7090-WOL -SS Spray nozzle                       TBB03-2-W (3)                              BB-04-F001 (3)
MW7089-WOL-DM                              MW7089-WOL-SS "A" Safety nozzle                     TBB03-3-A-W (3)                            BB-02-F001A (2)
__________                      MW7086-WOL-DM                              MW7086-WOL-SS "B" Safety nozzle                     TBB03-3-B-W (3)                            BB-02-F005A (2)
MW7087-WOL-DM                              MW7087-WOL-SS "C" Safety nozzle                     TBB03-3-C-W (1)                            BB-02-F006A (2)
_________                      MW7088-WOL -DM                             MW7088-WOL -SS Relief nozzle                       TBB03-4-W (1)                              BB-02-F008 (2)
_________                       MW7085-WOL-DM                              MW7085-WOL-SS WCRE-30                                     3.0 - ISI Program Description                                 Revision 0 Page 26 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Table 3.2.2.3-2 Repair locations                                          Pre-emptive locations Examine 25% sampling                                         Examine 25% sampling TBB03-l-W (1)                                               TBB03-2-W (3)
MW7090-WOL-DM                                               MW7089-WOL-DM TBB03-3-C-W (1)                                             TBB03-3-A-W (3)
MW7088-WOL-DM                                               MW7086-WOL-DM TBB03-4-W (1)                                             TBB03-3-B-W (3)
MW7085-WOL-DM                                                MW7087-WOL-DM BB-02-F00 1A (2)                                             BB-01-F004B (3)
MW7086-WOE- SS                                              MW7090 -WOE- SS BB-02-F005A (2)                                               BB-04-F001 (3)
MW7087-WOL-SS                                               MW7089-WOL-SS BB-02-F006A (2)
MW7088-WOL-SS                           ______________________
BB-02-F008 (2)
MW7085-WOL-SS                           _______________________
As noted in Table 3.2.2.3-2, there are 3 "Repair" category locations for the DM welds, 4 "Repair" category locations for the SS welds, 3 "Preemptive" category locations for the DM welds, and 2 "Preemptive" category locations for the SS welds. Table 3.2.2.3-3 contains the information from Table 5 of letter ET 06-0044 as discussed above.
Table 3.2.2.3-3: Weld Overlay Inservice Examination Requirements Examination Description*                   Method          Technique         Reference         Acceptance Standards Full Structural Repair WOL: Weld             Volumetric       UT angle beam     ASME Section         Q-4300 overlay and outer 25% of the original DM                              per PDI       XI and Q-4300 weld thickness at least 0.5 inches beyond                           procedure the toes of the original DM weld and butter, and at least 0.5 inches beyond any as-found flaw, will be examined within the next two refueling outages. Re-examination will be on a sampling basis in accordance with Q-4300(b) through (f) and Q-43 10. These examination will be added to the ISI Program Plan in accordance with IWB-2412(b)(l).
Full Structural Repair WOL: Weld             Volumetric       UT angle beam     ASME Section         Q-4300 overlay and outer 25% of the original SS                              per PDI       XI and Q-4300 weld thickness at least 0.5 inches beyond                           procedure the toes of the original SS weld, and at least 0.5 inches beyond any as-found flaw, will be examined within the next two refueling outages. Re-examination will be on a sampling basis in accordance with Q-4300(b) through (f) and Q-431 0.
These examination will be added to the ISI Program Plan in accordance with IWB-2412(b)(1).
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Preemptive Full Structural WOL: If             Volumetric       UT angle beam   ASME Section       Q-4300 greater than or equal to 90% coverage of                              per PDI      XI and Q-4300 the original DM weld is achieved with                               procedure PDI qualified procedures and no service related indications are identified the weld overlay and outer 25% of the original DM weld thickness at least 0.5 inches beyond the toes of the original DM weld and butter will be examined on a sampling basis in accordance with Q-4300(b) through (f) and Q-43 10. These examination will be added to the ISI Program Plan in accordance with IWB-2412(b)( 1).
                                               +                 +                F               I Preemptive Full Structural WOL: If              Volumetric      UT angle beam   ASME Section       Q-4300 greater than or equal to 90% coverage of                              per PDI      XI and Q-4300 the original SS weld is achieved with PDI                             procedure qualified procedures and no service related indications are identified the weld overlay and outer 25% of the original SS weld thickness at least 0.5 inches beyond the toes of the original SS weld will be examined on a sampling basis in accordance with Q-4300(b) through (t) and Q-43 10. These examination will be added to the ISI Program Plan in accordance with IWB-2412(b)(I).
*This is a general examination description to be performed; it does not identify all requirements for performing the examinations. As noted on page 6 of 28 of 10 CFR 50.55a Request I3R-05, Revision 1, submitted by letter ET 06-0031, the examination requirements comply with non-mandatory Appendix Q except as noted.
3.2.2.2 MR!P-192 The MRP issued letter MRP 2007-04 1, which contains document MRP-192, "Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants". This document contains recommendations classified as "good practice" as defined by NEI 03-08 Implementation Protocol. The recommendations of this document were evaluated and documented in Condition Report 2007-000979. The initial examinations were performed in RE-i16, and re-performed on a 6 year frequency.
In 2015, the MIRP issued letter 2015-019 that contains a good practice per NEI 03-08. This good practice is to include the welds of the mixing tee to the upstream piping. The evaluation of this recommendation is documented in CR 96696. The following criteria apply for performing the examinations:
* The inspection zone of the RH-R mixing tees should include all welds within at least four intemnal pipe diameters downstream from the mixing tee junction point, including the mixing tee downstream weld.
* The inspection zone should also include the welds of the mixing tee to the upstream piping.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL 1ST PROGRAM PLAN
           *Personnel performing the examination should receive training on the EPRI-developed thermal fatigue detection technology using the computer-based training module for thermal fatigue cracking and crazing inspection, as referenced in MRP- 192.
3.2.2.3 Code Case N-729-1 In accordance with 10 CFR 50.55a(g)(6)(ii)(D), all PWR licensees shall augment their inservice inspection program with ASME Code Case N-729- 1 and the conditions specified in (g)(6)(ii)(D)(2) through (6) of 10 CFR 50.55 a by December 31, 2008. These requirements were initially implemented during Interval 3.
3.2.2.4 Code Case N-722-1 In accordance with 10 CFR 50.55a(g)(6)(ii)(E), all PWR licensees shall augment their inservice inspection program with ASME Code Case N-722 and the conditions specified in (g)(6)(ii)(E)(2) through (4) of 10 CFR 50.55a. It is required that for inspections to be conducted every refueling outage and inspections conducted every other refueling outage, the initial inspection shall be performed at the next refueling outage after January 1, 2009.
These requirements were initially implemented during Interval 3.
3.2.2.5 MVRP-146 The evaluation for Report MRP-146, Thermal Fatigue in Normally Stagnant Non-Isolable RCS Branch Lines is documented in WCRE-25, Program Plan for Management of Thermal Fatigue. There are four locations did not screen out for thermal fatigue degradation. These locations were required to be examined prior to the end of the next refueling outage beginning after January 31, 2009 (RF 17) per the original guidance of MRP-146. Revision 1 of MRP-146 gives the option of performing periodic inspections on locations that do not screen out per the MRP-146 guidance. Lines with the UH/H configuration that are screened as susceptible to thermal fatigue are to be inspected every refueling outage (RFO) beginning with the first RFO after January 31, 2012 (RF 19). Lines with the DH configuration that are screened as susceptible to thermal fatigue are to be inspected every other RFO beginning with the first REO after January 31, 2012 (RF 19). In 2015, the IvRP issued letter 2015-019 that contains a "Needed" requirement per NEI 03-08. This needed requirement is to perform a "One time" examination of UK configured piping greater than 2 NPS and not larger than 4 NPS and having the potential of previous cold in-leakage. This examination shall be performed not later than the first refueling outage commencing after June 1, 2016 (RF2 1). The evaluation of this "Needed" action is documented in CR 96696.
3.2.2.6 Dissimilar Metal Weld Surface Assessment Incoming correspondence 09-00324 documents the letter that provides notice that EPRI report 1018181, "Guideline for Conducting Ultrasonic Examinations of Dissimilar Metal Welds," has been issued. The purpose of this document is to provide guidance for nuclear power plant (NPP) owners in planning and executing welds examinations in a manner that will minimize the occurrence of significant human errors and to assure completion of the planned examination scope. This guideline is applicable to welds that are scheduled for examination WCRE-30                 3.0 - ISI Program Description                             Revision 0 Page 29 of 4l

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN The NPP owner is responsible for compliance with the one "Needed" requirement in the report that is in accordance with NEL 03-08. The "Needed" requirement is described as follows:
* Needed: The utility shallprepare, maintain, and execute a surface condition assessment and improvementprocess, as part of itsprogramfor dissimilar metal weld examinations.
Condition Report 18089 documents this requirement. Attachment A of this program plan provides the documentation of the required process.
3.2.2.7 Code Case N-770-1 In accordance with 10 CFR 50.55a(g)(6)(ii)(F), all PWR licensees shall augment their inservice inspection program with ASME Code Case N-770-l and the conditions specified in (g)(6)(ii)(F)(2) through (10) of 10 CFR 50.55a. Per the regulation, the Code Case and the applicable conditions shall be implemented by the first refueling outage after August 22, 2011, which for Wolf Creek was Refueling Outage RF 19.
The baseline examinations were required to be completed by the end of the next refueling outage after January 20, 2012; however, previous exams could be credited for baseline examinations if they were performed within the re-inspection period specified in Table 1 of the Code Case using Appendix VIII requirements and met the Code required examination of essentially 100 percent, or had NRC approval of alternative inspection requirements.
The previous exams performed under MIRP-1 39, along with the NRC approved Relief Request I3R-06, met the baseline requirements.
As noted in Section 3.2.2.1, the overlaid nozzle-to-safe end dissimilar metal welds on the pressurizer were examined in accordance with approved Relief Request I3R-05 during Interval 3. The examinations performed in accordance with I3R-05 also meet the requirements of Code Case N-770- 1, Items C and F, as applicable.
          *Note that the VE examinations required by this Code Case are encompassed by the VE examinations of Code Case N-722-1, 3.2.2.8 PWR Owners Group Operating Guidance OG-09-139              - Inspection of Pressurizer Heater Sleeves Based on guidance in PWR Owners Group Operating Guidance OG-09-1 39 and WCAIP-l1691 3-P, visual examinations of the Pressurizer Heater Sleeves for leakage are being performed during each refueling outage in accordance with Reactor Coolant System Pressure Test, STS-PE-040A.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 3.3      ASME Section XI Code Cases Incorporated Into The 1SI Program The use of ASME Section XI Code Cases is in accordance with 10CFR50.55a. ASME Code Cases that have been determined to be suitable for use in 1S1 Program Plans by the NRC are listed in Regulatory Guide 1.147, "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 1SI 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.
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 50.5 5a(z) via acceptance of the associated Request for Alternative.
Note that Code Cases N-729-l, N-722-1 and N-770-1 are not listed in Table 3.3-1, as they are implemented as augmented requirements as described in Section 3.2.
TABLE 3.3-1 CODE CASES INCORPORATED INTO THE ISI PROGRAM Code                       Title                        Regulatory           Extent of Use Case                                                    Guide 1.147 Status/Request for Alternative N-Si13-3     Evaluation Criteria For Temporary             Acceptable   To be used as needed for Acceptance of Flaws in Moderate                            temporary acceptance of Energy Class 2 or 3 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 1 and                      to the re-examination 2 Vessels                                                  requirements of IWB-2420(b) and IWC-2420(b) for vessel volumes containing subsurface flaws N-532-5      Alternative Requirements to Repair            Acceptable   Extent defined within the and Replacement Documentation                              Program Plan Requirements and Inservice Sunmnary Report Preparation and Submission N-586-1      Alternative Additional Examination            Acceptable   To be used as an alternative Requirements for Class 1, 2, and 3                         to the requirements of IWB-Piping, Components, and Supports                           2430(a), IWC-2430(a),
IWD-2430(a), IWF-2430(a)
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WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE 3.3-1 CODE CASES INCORPORATED INTO THE ISI PROGRAM Code                     Title                      Regulatory    1        Extent of Use Case                                               Guide 1.147 Status/Request for Alternative{
N-613-1   Ultrasonic Examination of Full              Acceptable     Extent defined within the Penetration Nozzles in Vessels,                            Program Plan Examination Category B-D, Item No's B3.l0 and B3.90, Reactor Nozzle-to-Vessel Welds, Figures IWB-2500-7(a), (b), and (c)_____________
N-639     Alternative Calibration Block              Conditionally   To be used if needed as an Material                                     Acceptable    alternative to the requirements of Appendix I, Supplement 1 and Section
________V,                                               Article 4 N-648-l  Alternative Requirements for Inner         Conditionally   Extent defined within the Radius Examinations of Class 1               Acceptable    Program Plan Reactor Vessel Nozzles N-705    Evaluation Criteria for Temporary            Acceptable    For use in temporary Acceptance of Degradation in                               evaluation of degradation in Moderate Energy Class 2 or 3                               moderate energy Class 2 or Vessels and Tanks                                          3 vessels and tanks N-706- 1 Alternative Examination                      Acceptable    These alternative Requirements of Table IWB-2500-1                           examination requirements and Table IWC-2500-1 for PWR                               will be applied to the Stainless Steel Residual and                               Residual Heat Removal heat Regenerative Heat Exchangers                               exchangers. The extent is defined in Section 4.1.10.
N-73 1   Alternative Class 1 System Leakage           Acceptable     To be used as an alternative Test Pressure Requirements                                  to the requirements of JWB-5221 (a).
N-735     Successive Inspections of Class 1 and       Acceptable     To be used as an alternative 2 Piping Welds                                              to the requirements of IWB-2420 or JWC-2420.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 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 accordance with I10CFRS0.55a(a)(3) and (g)(5) when specific ASME Section XI 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 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 10OCFR50.55a(z) and (g)(5). The status of each Request For Alternative and Request For Relief (Submitted, Granted, or Denied) is also included in Table 3.4-1.
TABLE 3.4-1 REQUESTS FOR RELIEF AIND REQUESTS FOR ALTERNATIVES FROM ASME SECTION XI REQUIREMENTS Relief Request                              Summary                                      Status 14R-0 1       Request to Continue Implementation of the Risk-                   Pending Informed Inservice Inspection Application on Class 1 and 2 Piping Welds I4R-02        Request to Perform a Limited VT-3 Examination                     Pending of the Reactor Vessel Supports                        ___________
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 4".
3.6       WCGS Nonexempt ASMIE Class Components and Component Supports The WCGS ASME Class 1, 2, and 3 components which are not exempt from the examination per Section XI, 1WB-1220, IWC-1220, and IWD-1220 are listed in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4,WCRE-3 2". This document provides a cross-reference to the applicable ISI Isometric or 1S1 Equipment Drawing.
An index of the WCGS ISI Isometrics and Equipment Drawings is included in Section 3.11. A list of applicable Isometrics and Equipment Drawings is also included in each of the System Program Plans of Section 4.1.
The supports of nonexempt components are subject to examination per Section XI, IWF-1200.
Nonexempt component supports are shown on the ISI Isometrics and ISI Equipment Drawings listed in Section 3.11.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL 1ST PROGRAM PLAN 3.7       ISI Isometrics and Equipment Drawings 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 XI. An index of these isometrics and equipment drawings is included on Inservice Inspection Drawing Cross Reference, ISI-REF, Sheets 1 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 1SI Isometrics and Equipment Drawings is included in the ISI Database. The ISI-REF Sheets, Isometrics and Equipment Drawings are stand alone drawings. They are listed as M-1 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, sub-sub articles IWB-1220, IWC-1220, and IWD-1220.
Component supports which meet the criteria of IWF-l1230 are also exempt from examination.
Exempt components are listed in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4". This document details the specific exemption criteria applicable to each component.
3.9       System Pressure Testing System Pressure 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, IWB-5000, IWC-5000, and IWD-5000, as modified by Code Case N-73 1 (applicable to IWB-5 000 only), and 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.
3.10      Calibration Blocks Table 3.10-1 lists the calibration blocks required for the ultrasonic (UT) examinations scheduled in this program plan. The calibration block design and material selection is in accordance with ASME Section XI.
WCRE-30                                   3.0 - ISI Program Description                             Revision 0 Page 34 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE 3.10-1 WCGS CALIBRATION BLOCKS
[BLOCK   [DESCRIPTION/TITLE                           DRAWING   [APPLICABLE
[NUMBER                                              jNUMBER     [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-             80C41 92       BB 2-CSCL-1 01 102     WC-03-SG-03 .000-SA533-GR.A-                80C41 93        BB CL-2-CS-102 104     WC-5.0-SG-05 .035-SA21 6-WCCA-              80C41 95       BB CSCL-104 105     WC-29-XXX-02.33-SA351-CF8A-                 80D4896        BB CCSS-105 106     WC-27 1/2-XXX-02.21-SA351-                  80D4895        BB CF8A-CCSS-106 112     WC-03-1 60-00.438-SA3 12-TP304-             80D4894        BG SS-112 114     WC-04-1 60-00.531 -SA3 12-TP304-            80C4891        BB SS-114 117     WC-06-160-00.719-SA312-TP304-               80C4891   EJ, EP, EM, BB SS5-117 122     WC-1 0-140-01 .000-SA358-TP304-             80C4891       EJ, EP CL.1-SS-122 126     WC-12-140-01.125-SA376-TP304-               80D4892         EJ SS-126 127     WC-14-120-01 .094-SA508-CL. 1-CS-           80D4892        AE 127 128     WC-1 2-80S-00.500-SA3 12-TP304-             80C4891         EJ SS-128 130     WC-14-1 60-01 .406-SA376-TP3 16-            80D4892         BB SS-130 131     WC- 16-080-00.844-SA106-GR.B-               80C4891        AE CS-131 132     WC-28-01.500-SA106-GR.C-CS-132              80D4892        AB 140     WC-N-7.0-7.99-SA540-GR.B24-                 80D4903        BB CL.3-CS-140 WCRE-30                       3.0 - ISI Program Description                         Revision 0 Page 35 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE 3.10-1 (Continued)
WCGS CALIBRATION STANDARDS
[BLOCK NUMBER I _
DESCRIPTION/TITLE IDRAWING       1APPLICABLE NUMBER] SYSTEM(S) 144         WC-2.0-HPCI-02.000-SA240-TP304-             80D4915            EM SS-144 156         WC-02-1 60-00.344-SA3 12-TP304-             80D4897            BB SS-156 159         WC-04-080-00.337-SA106-GR.B-                80D4893        AB, AE, FC CS-i159 169         WC-NSE-04-1 60-SA508-CL.2                80E491 8          BB 160-SAl182-F3 16L-BI- 169 170         WC-NSE-06-160-SA508-CL.2                 80E4922           BB 160-SAl182-F3 16L-BI-170 171         WC-NSE-14-1 60-SA508-CL.2                80E4923           BB 160-SA1 82-F3 16L-BI- 171 172         WC-00.875-RHR-00.750-SA240-                  80D491 7           EJ TP304-SS-172 175         WC-1 1-RPV-1 1-SA533-GR.B-CL. 1-             80D8410           BB ASCL-175 176         WC-9-RPV-9-SA533-GR.B-CL. 1-                 80D841 1          BB ASCL-176 177         WC-7-RPV-7-SA533-GR.B-CL. 1-                 80D841 2          BB ASCL-177 178        WC-F-XX-33-SA533-GR.B-CL.1-                  80D8413           BB ASCL-178 179        WC-NSE-XXX-3-SA182-GR316-                    5D64166           BB (Note 1)     CL.XX-XXX-3-SA508-GR.XX-CL2-BI-179 183       WC-12-STD-00.375-SA3 12-TP304-               80C4891            EJ SS-183 192       WC-14-40S-00.438-SA358-TP304-                80C4891         BN, EN CL. 1-192 193       WC-S-2.5- 14-SAl193-GR.B7-CS-1 93             80C84 15           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-SA540-GR.B24-CL.3-               Jiiture use         BB CS-195                                         Note 3 WCRE-30                            3.0 - ISI Program Description                           Revision 0 Page 36 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE 3.10-1 (Continued)
WCGS CALIBRATION STANDARDS
[BLOCK
[NUMBER IJ      _
DESCRIPTION/TITLE TDRAWING IAPPLICABLE NUMBER         JSYSTEM(S) 203             WC-08-40S-00.322-SA3 12-TP304-                       M-1 89-               EJ SS-203                                                10203 204             WC-10O-40S-00.365-SA3 12-TP304-                      M- 189-               EJ SS-204                                                10204 8747             Alternate ASME Calibration Block                     Note 4              Note 5 A5 16-70 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 ASMVE Calibration Block                    Note 4              Note 5 A5 16-70 Steel 8751             Alternate ASME Calibration Type                      Note 4              Note 6 316 Stainless Steel 8752            Alternate ASMIE Calibration Type                     Note 4              Note 7 304 Stainless Steel Ax 6-01            6" Axial Reference Block                           100 155C87          BB, Note 8 Circ 6-01          6" Circumferential Reference Block                 100155C88          BB, Note 8 Ax 8-01           8" Axial Reference Block                           100 155C89         BB, Note 8 Circ 8-01          8" Circumferential Reference Block                 100 155C90          BB, Note 8 Axial/Flat         16" Axial/Flat Reference Block                     1001 55C91          BB, Note 8 16-01 Circ 16-01          16" Circumferential Reference Block                100 155C92          BB, Note 8 NOTES:
Note 1: Block 179 was modified by Westinghouse in 1996. The drawing number referenced is the 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, if the block is modified to comply with Appendix VIII, or an equivalent RCP stud cal block meeting Section XI requirements (such as Callaway Block 93).
Note 3: Previous examinations were conducted utilizing either block 155 or Callaway block 95. The Interval 3 examinations will utilize block 195, if the block is modified to comply with Appendix VIII, or an equivalent RV stud cal block meeting Section XI requirements (such as Callaway Block 95).
WCRE-30                                   3.0 - ISI Program Description                                     Revision 0 Page 37 of4l

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN NOTES (Continued):
Note 4: The Alternate ASME Calibration Block is depicted on Figure 4 of PDI-UT-I and PDI-UT-2.
Note 5: The Alternate Calibration Blocks numbered 8747 and 8750 may be utilized in lieu of carbon steel calibration blocks after approval by WCNOC Level III QC, 1S1 Engineering, and review by the ANII.
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 Ill QC, 1SI Engineering, and review by the ANII.
Note 7: The Alternate Calibration Blocks numbered 8749 and 8752 may be utilized in lieu of Type 304 stainless steel calibration blocks after approval by WCNOC Level III QC, 1S1 Engineering, and review by the ANII.
Note 8: These are reference blocks to be utilized for the examination of the overlays installed on the pressurizer nozzles piping welds. Reference P0 733795 and Receipt Inspection Report 06-052193.
3.11      Inservice Inspection Drawing Index M-189-50 Series List Reference Drawings             M-189-50ISI-REF        SHEET 1 of 4 M-189-50ISI-REF        SHEET 2 of 4 M-189-50ISI-REF        SHEET 3 of 4 M-189-50ISI-REF        SHEET 4 of 4 AB System                      M-189-50AB-01-01         SHEET    1 of 1 M-189-50AB-02-01         SHEET    1 of 1 M-189-50AB-03-01         SHEET    1 of 1 M-189-50AB-04-01         SHEET    1 of 1 AE System                      M-189-50AE-01-04         SHEET    1 of 1 M-189-50AE-02-04         SHEET    1 of 1 M-189-50AE-03-05         SHEET    1 of 1 M-189-50AE-04-05         SHEET    1 of 1 AL System                      M-189-50AL-01-01         SHEET 1 of 2 M-189-50AL-01-01         SHEET 2 of 2 M-189-50AL-01-02         SHEET 1 of 1 M-189-50AL-02-03         SHEET 1 of 1 M-189-50AL-03-04         SHEET 1 of 1 M- 189-50AL-04-02        SHEET 1 of 1 M-189-50AL-05-03         SHEET 1 of 1 M-189-50AL-06-04         SHEET 1 of 1 M-1 89-50AL-07-06 SHEET 1 of 1 WCRE-30                                       3.0 - 1S1 Program Description                                    Revision 0 Page 38 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN BB System    M-189-50BB-00-01      SHEET 1 of 1 M-189-50BB-01-01      SHEET 1 of 1 M-189-50BB-01-02      SHEET 1 of 1 M-189-50BB-01-04      SHEET 1 of 2 M-189-50BB-01-04      SHEET 2 of 2 M-189-50BB-01-08      SHEET 1 of 1 M-189-50BB-02-01      SHEET 1 of 1 M-189-50BB-02-02      SHEET 1 of 1 M-189-50BB-02-11      SHEET 1 of 1 M-189-50BB-03-01      SHEET 1 of 1 M-189-50BB-03-09      SHEET 1 of 1 M-189-50BB-04-01      SHEET 1 of 1 M-189-50BB-04-07      SHEET 1 of 1 M-189-5OBB-05-01      SHEET 1 of 1 M-189-50BB-06-01      SHEET 1 of 1 BG System    M-189-50BG-01-01      SHEET   1 of 1 M-189-50BG-01-21      SHEET   1 of 1 M-1 89-50BG-02-22     SHEET   1 of 2 M-1 89-50BG-02-22     SHEET   2 of 2 M-189-50BG-03-23      SHEET   1 of 1 M-189-50BG-04-09      SHEET   1 of 1 M-189-50BG-05-24      SHEET   1 of 1 M-189-50BG-06-02      SHEET   1 of 2 M-189-50BG-06-02      SHEET   2 of 2 M-189-50BG-06-10      SHEET   1 of 1 BM System    M-189-50BM-01-01 SHEET 1 of 1 M-189-50BM-01-02 SHEET 1 of 1 BN System    M-189-50BN-01-01 SHEET 1 of 3 M-189-50BN-01-01 SHEET 2 of 3 M-189-50BN-01-01 SHEET 3 of 3 EF System    M-189-50EF-01-01      SHEET 1 of 2 M-189-50EF-01-01      SHEET 2 of 2 M-189-50EF-01-02      SHEET 1 of 2 M-189-50EF-01-02      SHEET 2 of 2 M-189-50EF-01-03      SHEET 1 of 2 M-189-50EF-01-03      SHEET 2 of 2 M-189-50EF-01-07      SHEET 1 of 1 M-189-50EF-01-08      SHEET 1 of 1 M-189-50EF-01-09      SHEET 1 of 1 M-189-50EF-01-10      SHEET 1 of 1 M-189-50EF-02-01      SHEET 1 of 3 M-189-50EF-02-01      SHEET 2 of 3 M-189-50EF-02-01      SHEET 3 of 3 M-189-50EF-02-04      SHEET 1 of 1 M-189-50EF-02-05      SHEET 1 of 2 M-189-50EF-02-05      SHEET 2 of 2 M-189-50EF-02-06      SHEET 1 of 1 M-189-50EF-02-08      SHEET 1 of 2 WCRE-30                  3.0 - ISI Program Description  Revision 0 Page 39 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN M-189-50EF-02-08      SHEET 2 of 2 M-189-50EF-02-09      SHEET 1 of 1 M-189-50EF-02-10      SHEET 1 of 1 M-189-50EF-03-01      SHEET 1 of 1 EG System    M-189-50EG-01-01       SHEET 1 of 1 M-189-50EG-01-02       SHEET 1 of 2 M-189-50EG-01-02       SHEET 2 of 2 M-189-50EG-02-03       SHEET 1 of 2 M-189-50EG-02-03       SHEET 2 of 2 M-189-50EG-02-05       SHEET 1 of 2 M- 189-50EG-02-05      SHEET 2 of 2 M-189-50EG-03-06       SHEET 1 of 1 M-189-5OEG-03-07       SHEET 1 of 1 M-1 89-50EG-04-01      SHEET 1 of 2 M-189-50EG-04-01       SHEET 2 of 2 M-189-5OEG-05-06       SHEET 1 of 2 M-189-50EG-05-06       SHEET 2 of 2 EJ System    M-189-50EJ-01-01      SHEET 1 of 5 M-189-50EJ-01-01      SHEET 2 of 5 M-189-50EJ-01-01      SHEET 3 of 5 M-189-50EJ-01-O1      SHEET 4 of 5 M-189-50EJ-01-01      SHEET 5 of 5 M-189-5OEJ-01-04      SHEET 1 of 1 M-189-50EJ-02-02      SHEET 1 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-1 89-50EJ-02-02     SHEET 5 of 5 M-1 89-50EJ-02-04     SHEET 1 of 3 M-1 89-50EJ-02-04     SHEET 2 of 3 M-189-50EJ-02-04      SHEET 3 of 3 EM System    M-189-50EM-01-01        SHEET  1 of 1 M-189-50EM-02-01        SHEET  1 of 1 M-189-50EM-03-05        SHEET  1 of 1 M-1 89-50EM-04-03       SHEET  1 of 1 M-189-50EM-05-01        SHEET  1 of 2 M-189-50EM-05-01        SHEET  2 of 2 M-189-50EM-06-02        SHEET   1 of 2 M-189-50EM-06-02        SHEET  2 of 2 M-189-50EM-06-03        SHEET   1 of 1 WCRE-30                   3.0 - 1ST Program Description   Revision 0 Page 40 of 4l

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN M-189-50EN-01-01      SHEET 1 of 3 EN System M-189-50EN-01-01      SHEET 2 of 3 M-189-50EN-01-01      SHEET 3 of 3 M-189-5OEN-02-02      SHEET 1 of 3 M-189-50EN-02-02      SHEET 2 of 3 M-189-50EN-02-02      SHEET 3 of 3 EP System           M-189-50EP-01-01     SHEET   1 of 1 M-1 89-50EP-02-02    SHEET   1 of 1 M-189-50EP-03-02     SHEET   1 of 1 M-189-50EP-04-01     SHEET   1 of 1 FC System           M-189-50FC-01-01 SHEET 1 of 1 GN System           M-189-50GN-01-01      SHEET   1 of 4 M-189-50GN-01-01      SHEET   2 of 4 M-189-50GN-01-01      SHEET   3 of 4 M-189-50GN-01-01      SHEET   4 of 4 M-189-50GN-02-02      SHEET   1 of 4 M-189-50GN-02-02      SHEET   2 of 4 M- 189-5OGN-02-02     SHEET   3 of 4 M-189-50GN-02-02      SHEET   4 of 4 KJ System           M-189-50KJ-01-01     SHEET 1 of 4 M-189-50KJ-01-01     SHEET 4 of 4 M-189-50KJ-02-04     SHEET 1 of 4 M-189-50KJ-02-04     SHEET 4 of 4 Equipment Drawings  M-189-50ISI-RBB01 SHEET 1 of 3 M-189-50ISI-RBB01 SHEET 2 of 3 M-189-50ISI-RBB01 SHEET 3 of 3 M-189-50ISI-TBB03 SHEET 1 of 2 M-189-50ISI-TBB03 SHEET 2 of 2 M-189-50IS1-EBB01A SHEET 1 of 1 M-189-50ISI-EBB01B SHEET 1 of 1 M-189-50ISI-EBB01C SHEET 1 of 1 M-189-501S1-EBB01D SHEET 1 of 1 M-189-50IS1-EEJ01A SHEET 1 of 1 M-189-501SI-EEJ01B SHEET 1 of 1 M-189-50ISI-PUMPS SHEET 1 of 1 M-189-50ISI-CRDMPL SHEET 1 of 1 WCRE-30                         3.0 - ISI Program Description  Revision 0 Page 41 of 41

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.0     WCGS SYSTEM INSERVICE INSPECTION PROGRAM PLANS This Section includes system specific 1S1 Program Plans which detail the examinations and tests scheduled for each WCGS system included in the ISI Program. Section 4.0 has been subdivided into three subsections:
Subsection 4.1 includes systems which are subject to Section XI 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.
Subsection 4.2 includes systems which are subject to ASME Section XI System Pressure Testing only.
These systems or portions of these systems include exempt Class 1, Class 2, and Class 3 components (per IWB-1220, IWC-1220, or IWD-1220) only.
Subsection 4.3 includes Class 2 components which are exempt Section XI NDE and Augmented NDE and are also excluded from periodic system pressure testing per TWA-5 110(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 4", this line cannot be exempted per the criteria of IWC-1 222. 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 4, and the GS System is not included in Section 4.1.
WCRE-30                         4.0 System Inservice Inspection Program Plans                   Revision 0 Page 1 of 1

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1 WCGS SYSTEMS SUBJECT TO SECTION XI NDE OR AUGMENTED NDE 4.1 WCGS Systems Subject To Section XI NDE WCRE-30                          or Augmented NDE                   Revision 0 Page 1 of 1

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.1 Main Steam System (AB)
A. Applicable System Piping and Instrument Drawings
: 1. M-12AB01-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 4".
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 4".
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 1  Main Steam Loop 1
: 2.        M-189-50AB-02-01             Sheet 1  Main Steam Loop 2
: 3.        M-189-50AB-03-01             Sheet 1  Main Steam Loop 3
: 4.        M-189-50AB-04-01             Sheet 1  Main Steam Loop 4 4.1.1 Main Steam System (AB)                                           Revision 0 WCRE-30                                        Page 1 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.1 Main Steam System (AR)
E.      Summary of 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 ASMvIE Section XI or per Augmented requirements. A detailed listing of these components and items is maintained in the 1SI 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         P1. P__2      P_.3        INTERVAL PIPING WELDED                  C-C            C3.20               --                         2           0       1        0                 1 ATTACHMENTS PRESSURE RETAINING                 C-D            C4.40--                                        4                            0110 BOLTING                                                                                                                               Note 2 PIPING COMPONENT                  F-A            F1.20               --                         28          2       2        26 SUPPORTS PIPING WELDS NOT                  R-A           R1.20.6               --                       155          5       6        516 SUBJECT TO A DAMAGE               Note I           Note 1 MECHANISM PIPING WELDS                     --                            USAR           3.6.2         203          2       1        14 SUBJECT TO HELB REQUIREMENTS Note 1: See Section H for an explanation of Category R-A and Item R1.XX nomenclature.
Note 2: Examination of Pressure Retaining Bolting is performed in accordance with Category C-D. See Note 2 in Paragraph I for selection and scheduling criteria.
WCRE-30                                                           4.1.1 Main Steam System (AB)                                                          Revision 0 Page 2 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI 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 Pipine 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-33 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-1, 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-1 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 through 4-4 of TR-1 12657 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 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 1 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-578-1.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table AB-1 (Period 1 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 and RI-ISI Programs. The requirements for examn~ation of these welds are discussed in Paragraphs F and H above, respectively.
: 2. Examination of Pressure Retaining Bolting is performed in accordance with Category C-D.
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 Category C-D, Notes 1 and 2.
: 3. The valves with this bolting were replaced in Interval 3. The preservice exam was performed with the surface exam method. The configuration of the bolting in the new valves will require a new calibration stud and demonstration of a specific procedure. Alternatively, the studs may be removed and a surface examination meeting the acceptance standards of IWB-35 15 may be substituted for the volumetric examination per Note 5 of Category C-D.
WCRE-30                         4.1.1 Main Steam System (AB)                                           Revision 0 Page 3 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN
: 4. These welds have been selected per the RI-ISI Program only. The requirements for examination of these welds are discussed in Paragraph H above.
WCRE-30                4.1.1 Main Steam System (AB)                                         Revision 0 Page 4 of7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AB-1 IIPeriod1Examinations I
[System: ABJ Relief Request or Size Thickness NDE Method           Item    Cal Block          Notes Component Name  Drawing Number Component Description                                                            Category AB-0 I-HV- 14-b AB-01-01       VALVE HV- 14 BONNET BOLTING                            2.5        NA      UT     C-D      C4.40                         2,3 AB-01-C002      AB-01-01       PIPING SUPPORT                                        28                 VT-3    F-A      F1.20 AB-01-H010      AB-02-01       PIPING SUPPORT                                        28                 VT-3    F-A      F1.20 AB-01-F007      AB-01-0I       28' MAIN STEAM HEADER TO FLUED HEAD (P-2)             28        1.5       UT     R-A      Ri1.20.6     132              1 AB-0 I-FO07     AB-01-01                                                             28        1.5       UT     USAR     3.6.2        132 28" MAIN STEAM HEADER TO FLUED HEAD (P-2)
AB-0i-F074      AB-04-01       28" MAIN STEAM HEADER TO FLUED HEAD (P-i)             28        1.5       UT     R-A      Ri1.20.6     1321 AB-01 -F074     AB-04-01                                                             28        1.5       UT     USAR     3.6.2        132 28' MAIN STEAM HEADER TO FLUED HEAD (P-i)
AB-01-S008-B    AB-01-01       10" PIPE TO 10" ELBOW                                  10       .594      UIT    R-A      Ri1.20.6     123              4 AB-0 1-F052-A   AB-03-01       28" PIPE TO TORSIONAL RESTRAINT                       28        1.5       UT     R-A      RI .20.6     168              4 AB-01-S032-W    AB-03-01       12" PIPE TO 12" PIPE CAP                               12       .688      UT     R-A      RI .20.6     129              4 WCRE-30                                                 4.1.1 Main Steam System (AR)                                                              Revision 0 Page 5 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AB-2
[Period 2 Examinations
[System:   AB Relief Request Component Name Drawing Number Component Description                                    Size Thickness NDE Method Category Item     Cal Block      or Notes AB-01l-R0Oi0   AB-02-0I       PIPING INTEGRAL ATTACHMENTS                             28                  MT     C-C      C3.20 AB-0Ol-R001    AB-04-0 l      PIPING SUPPORT                                          28                 VT-3    F-A      F1.20 AB-0I-R003     AB-03-0i       PIPING SUPPORT                                          28                 VT-3    F-A      FI.20 AB-01-F026     AB-02-01       28" MAIN STEAM HEADER TO FLUED HEAD (IP-3)              28         1.5      UT     R-A      Ri1.20.6     132 28" MAIN STEAM HEADER TO FLUED HEAD (P-3)                                                                132 AB-01-F026     AB-02-01                                                               28         1.5      UT     USAR     3.6.2 AB-01-F02 8-A  AB-02-01       28" PIPE TO TORSIONAL RESTRAINT                         28          1.5     U      R-A      Ri1.20.6     168 AB-01-S020-B   AB-02-01       10' PIPE TO 10" ELBOW                                    10        .594     UIT    R-A      R1 .20.6    123              4 AB-01-S018-L   AB-02-01       6" OUTLET ON MAIN STEAM HEADER TO 6" FLANGE             6          .432     UT     R-A      RI1.20.6     180             4 AB-01-S049-D   AB-04-01       10" ELBOW TO 10" X 8" REDUCER10                          10       .594      UT     R-A      Ri1.20.6     165             4 AB-01-S046-L   AB-04-01       6' OUTLET ON MAIN STEAM HEADER TO 6" FLANGE             6          .432     UT     R-A      R1 .20.6     180             4 WCRE-3 0                                              4.1.1 Main Steam System (AB)                                                               Revision 0 Page 6 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AB-3 SPeriod 3 Examinations1 lsystem: AB Relief Request or Size Thickness  NDE Method           Item     Cal Block    Notes Component Name Drawing Number  Component Description                                                             Category AB-0 1-CO011   AB-03-01        PIPING SUPPORT                                        10                 VT-3     F-A      F1.20 AB-01-H-005    AB-03-01        PIPING SUPPORT                                        28                 VT-3     F-A      F1.20 AB-0I-F050     AB-03-0OI       28" MAIN STEAM HEADER TO FLUED HEAD (P-4)             28         1.5      UT     R-A       RI .20.6     132 AB-01-F050                     28" MAIN STEAM HEADER TO FLUED HEAD (P-4)                                        USAR      3.6.2        132 AB-03-01                                                              28         1.5      UT AB-01-F006     AB-01-01        28' PIPE TO 28" ELBOW                                 28       .934       UT     R-A       R1 .20.6     135            4 AB-01-F097     AB-01-O1       FLUED HEAD (P-2) TO 28" PIPE                           28         .934     UT     R-A       Ri1.20.6     135            4 AB-01-S034-D   AB-03-01       10" ELBOW TO 10" PIPE                                  10        .594      UT     R-A       R1 .20.6     123            4 AB-01 -F076-A  AB-04-01       28" PIPE TO TORSIONAL RESTRAINT                        28         1.5      UT     R-A       Ri1.20.6     168            4 WCRE-30                                                   4.1.1Main tRevision                                                                   Revision 0AB 0
Page 7 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.2 Feedwater System (AE)
A. Applicable System Piping and Instrument Drawings
: 1. M- 12AE02-Feedwater System B. Classification of Components Details of the classification of the Feedwater System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Feedwater System. These drawings are included in the M-189-50 series.
: 1.       M-189-50AE-01-04            Sheet  1         Main Feedwater Loop   1
: 2.       M-189-50AE-02-04            Sheet  1         Main Feedwater Loop   2
: 3.       M-189-50AE-03-05            Sheet  1         Main Feedwater Loop   3
: 4.       M-189-50AE-04-05            Sheet  1        Main  Feedwater Loop   4 4.1.2 Feedwater System (AE)                                             Revision 0 WCRE-30                                       Page 1 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.2 Feedwater System (AE)
E.       Summary of 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 1SI 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     P1_     P_.2  P_.3       INTERVAL PIPING INTEGRAL                C-C              C3.20                --                           12       1      1     0                 2 ATTACHMENTS PIPING WELDS SUBJECT               R-A              R1.11                --                           33      5       3     4                12 TO THERMAL FATIGUE                Note I            Note 1 PIPING WELDS NOT                R-A              R1.20                                            108      6       5     2                13 SUBJECT TO A DAMAGE               Note 1            Note 1 MECHANISM PIPING COMPONENT                F-A              F1.20                --                          44       3       3     3 *9 SUPPORTS PIPING WELDS SUBJECT                                                 USAR              3.6.2          17      3       3     2                  8 TO HELB REQUIREMENTS WITH THERMAL FATIGUE             __  _   _  _    __   _    _   _   __    _    _  _  _   _   _  _ _   _   _ _ _ _   __                  _  _    _    _  _  _   _
PIPING WELDS                                     -USAR                          3.6.2           62      3       0     0                 3 SUBJECT TO HELB REQUIREMENTS NOT                                                                                                                        Note 2 SUBJECT TO A DAMAGE MECHANISM Note 1: See Section H for an explanation of Category R-A and Item R1 .XX nomenclature.
Note 2: Two of these welds were optionally selected for examination.
WCRE-30                                                            4.1.2 Feedwater System (AE)                                                   Revision 0 Page 2 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.2 Feedwater System (AE)
F. Augmented ISI Requirements The following Augmented 1SI requirements apply to the Feedwater 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-33 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 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 1 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-1 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 through 4-4 of TR-1 12657 Rev. B-A.
Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table AE-1 (Period 1 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.
: 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-30                       4.1.2 Feedwater System (AE)                                    Revision 0 Page 3 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AE-1 IPeriod 1 Examinations tSystem: AE Relief Request or Size                                       Cal Block          Notes Component Name Drawing Number  Component Description                                        Thickness NDE Method Category  Item 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       F 1.20 AE-05-R011I    AE-03-05       PIPING SUPPORT                                           14                VT-3    F-A       F1.20 AE-04-F015     AE-01-04        16" PIPE TO S.G.A. INLET NOZZLE                         16      0.844      UT     R-A       RI.11      131          1,3 AE-04-S010-C   AE-01-04       16"X14" REDUCER TO 16" PIPE                              16      0.844      UT     R-A       RI~ll      131          1,3 AE-04-S025-A   AE-01-04       4" PIPE TO 4" ELBOW                                     4        0.337      UIT    R-A       RI 1l      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       RI 11      159          1,2,3 AE-04-S025-B   AE-01-04       4" ELBOW TO 4" PIPE                                     4        0.337      UIT    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       RI ll      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 AE-04-FW3 14   AE-02-04       14" PIPE TO 14" PIPE                                     14      0.750      UT     R-A       RI.20      173          1,2 AE-04-FW3 14   AE-02-04       14" P/PE TO 14" PIPE                                     14      0.750      UT     USAR      3.6.2      173 AE-04-FW3 15   AE-02-04       14" PIPE TO FLUED HEAD (P-7)                             14      0.750      UT     R-A      R1.20       173          1,2 AE-04-FW3 15   AE-02-04       14" PIPE TO FLUED HEAD (P-7)                             14      0.750      UT     USAR     3.6.2       173 WCRE-30                                                       4.1.2 Feedwater System (A.E)                                                      Revision 0 Page 4 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL IS1 PROGRAM PLAN TABLE AE-1 IPeriod 1 Examinations
[System: AE Relief Request or Size Thickness NDE Method          Item   Cal Block          Notes Component Name Drawing Number Component Description                                                         Category AE-05-F006     AE-04-05       14" PIPE TO 14" PIPE                                 14     0.750      UT     R-A      Ri1.20     124           1 AE-05-EW3 19   AE-04-05       14" PIPE TO 14" PIPE                                 14     0.750      UT     R-A      Rl.20      124           1 AE-05-F008     AE-04-05       14" PIPE TO 14" PIPE                                 14     0.750      UT     R-A      RI.20      173           1 WCRE-30                                                    4.1.2 Feedwater System (AE)                                                    Revision 0 Page 5 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AE-2
[Period 2 Examinations
[System: AE Relief Request or Cal Block          Notes Component Name Drawing Number Component Description                                   Size Thickness NDE Method Category  Item AE-05-R028     AE-04-05       PIPING INTEGRAL ATTACHMENTS                             14                 MT     C-C      C3.20 AE-05-C001     AE-03-05       PIPING SUPPORT                                          14                VT-3    F-A      FI.20 AE-05-R028     AE-04-05       PIPING SUPPORT                                          14                VT-3    F-A      F1.20 AE-04-C002     AE-01-04       PIPING SUPPORT                                          14                VT-3    F-A      F1.20 AE-04-S026-A   AE-02-04       4" PIPE TO 4" ELBOW                                     4       0.337      UT     R-A      RI ll     159          1,2,3 AE-04-S026-A   AE-02-04                                                               4                         USAR     3.6.2     159          1,2,3 4" PIPE TO 4" ELBOW                                            0.337       UT AE-04-F040     AE-02-04       4" WELDOLET TO 4" PIPE                                  4      0.337       UIT    R-A      RI ll     159          1,2,3 AE-04-F040     AE-02-04                                                               4                         USAR     3.6.2     159          1,2,3 4" WELDOLET TO 4" PIPE                                         0.337       UT AE-02-04                                                               4                         R-A      RI.I1     159          1,2,3 AE-04-S026-B                  4" ELBOW TO 4" PIPE                                             0.337      UT AE-04-S026-B   AE-02-04                                                               4                         USAR     3.6.2     159          1,2,3 4" ELBOW TO 4" PIPE                                             0.337      UT AE-04-F002     AE-01-04       14" TORSIONAL RESTRAINT TO FE-5 10                      14      1.094      UT     R-A      R1.20     127 AE-04-F006     AE-01-04       14" PIPE TO 14" PIPE                                    14      1.094      UT     R-A      R1.20     124 AE-05-F021     AE-03-05       14" PIPE TO 14" PIPE                                    14      1.094      UIT    R-A      RI.20     124 AE-05-MW7147   AE-03-05       14" PIPE TO 14" PIPE                                    14      1.094      UT     R-A      R1.20     124 AE-04-S0 19-B  AE-01-04       14" PIPE TO 14" PIPE                                    14      0.750      UIT    R-A      R1.20     116 WCRE-30                                                      4.1.2 Feedwater System (AE)                                                     Revision 0 Page 6 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AE-3 ISystem: AE Relief Request or Size                               Item     Cal Block          Notes Component Name Drawing Number  Component Description                                     Thickness NDE Method Category AE-04-R016     AE-02-04       PIPING SUPPORT                                        14                VT-3    F-A      FI.20 AE-04-H001     AE-02-04       PIPING SUPPORT                                        14                VT-3    F-A      F1.20 AE-05-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      RI ll 159           1,2,3 AE-05-F033     AE-03-05       4' PIPE TO VALVE V127                                 4                                  3.6.2        159           1,2,3 0.337      UT     USAR 4" ELBOW TO 4" PIPE                                   4       0.337      UT     R-A      RI~ll        159           1,2,3 AE-05-FW900    AE-03-05 AE-05-FW900    AE-03-05       4" ELBOW TO 4" PIPE                                   4                                  3.6.2        159           1,2, 3 0.337      UT     USAR AE-04-S02 1-C  AE-02-04       16'"X 14' REDUCER TO 16" PIPE                          16     0.844      UT     R-A      Rl.ll.5      131           1,3 AE-04-F035A    AE-02-04       16" PIPE TO S.G.B. INLET NOZZLE                        16     0.844      UT1    R-A      R.1.11.5     131           1,3 AE-04-F071     AE-01-04       14" PIPE TO 14" ELBOW                                  14     0.750      UT     R-A      R1.20        116 AE-04-S008-A   AE-01-04       14" ELBOW TO 14" PIPE                                  14     0.750      UT     R-A      RI.20        116 WCRE-30                                                      4.1.2 Feedwater System (AE)                                                      Revision 0 Page 7 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.3 Auxiliary Feedwater System (AL)
A. Applicable System Piping and Instrument Drawings
: 1. M-12AL01-Auxiliary Feedwater System B. Classification of Components Details of the classification of the Auxiliary Feedwater System Components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics detail the nonexempt 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-01-01           Sheet 1     Auxiliary Feedwater Turbine Driven Pump Suction Piping
: 2.       M-189-50AL-01-01           Sheet 2     Auxiliary Feedwater Pump Motor Driven Pump Suction Piping
: 3.       M- 189-50AL-01-02          Sheet 1     Motor Driven Auxiliary Feedwater Pump "A" Discharge Piping
: 4.       M-1 89-50AL-02-03          Sheet 1     Motor Driven Auxiliary Feedwater Pump "B" Discharge Piping Feedwater
: 5.       M- 1 89-50AL-03-04         Sheet 1     Turbine Driven Auxiliary Feedwater Pump Suction Piping
: 6.       M-189-50AL-04-02           Sheet 1     Motor Driven Auxiliary Feedwater Pump "A" Discharge Piping
: 7.       M-1 89-50AL-05-03          Sheet 1     Motor Driven Auxiliary Feedwater Pump "B" Discharge Piping
: 8.       M-1 89-50AL-06-04          Sheet 1     Turbine Driven Auxiliary Feedwater Pump Discharge Piping
: 9.       M-1 89-50AL-07-06          Sheet 1     Turbine Driven Aux. Feedwater Standby Tanks & Piping WCRE-30                                4.1.3 Auxiliary Feedwater (AL)                          Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.3 Auxiliary Feedwater (AL)
E.        Summary of Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table 1 is a sunmmary 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      P1_l  P..2    P_3        INTERVAL PIPING WELDED                   C-C             C3.20              --                           9          1       0    01 ATTACHMENTS Pressure Vessel Welded            D-A             D 1.10             --                           3          0       0    1                  1 Attachments PIPING WELDED                   D-A             D 1.20--7                                                 0        0    11 ATTACHMENTS PIPING COMPONENT                  F-A             F1.20              --                           32        2        1    2                 5 SUPPORTS PIPING COMPONENT                  F-A             F1.30              --                          45          3       2    3                 8 SUPPORTS EQUIPMENT SUPPORTS                 F-A             F1.40               --                          11         0       4    15 (Other Than Piping)
PIPING WELDS NOT                  R-A             R1.20                                          126         0       0    00 SUBJECT TO A DAMAGE                Note 1           Note 1 MECHANISM Note 1: See Section H for an explanation of Category R-A and Item R1.XX nomenclature.
WCRE-30                                                          4.1.3 Auxiliary Feedwater (AL)                                                  Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.3 Auxiliary Feedwater (AL)
F. Augmented 1S1 Requirements No Augmented ISI requirements apply to the Auxiliary Feedwater System.
G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining components within the Auxiliary Feedwater System will receive a system leakage test per IWC-5220 each inspection period.
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 IWD-5220 every period.
Procedures used to perform System Pressure Testing are listed in Table 4.2.1 H. Risk Informed 1SI Progrnm A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class 1 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, guidance was taken from Code Case N-578-1 for the assignment of these designators. No welds in the Auxiliary Feedwater System were selected for examination in the RI-ISI program.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table AL-i (Period 1 Examinations), Table AL-2 (Period 2 Examinations),
and Table AL-3 (Period 3 Examinations).
WCRE-30                        4.1.3 Auxiliary Feedwater (AL)                               Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE AL-I IPeriod 1 Examinations
[System:  AL Component Name Drawing Number  Component                                            Size Thickness NDE Method Category Item   Relief Request    Notes AL-04-C013     AL-06-04        PIPING INTEGRAL ATTACHMENT                                              PT     C-C      C3.20 4
AL-03-R0L11    AL-05-03        PIPING SUPPORT                                                         VT-3    F-A      F 1.20 4
AL-04-C013     AL-06-04        PIPING SUPPORT                                                         VT-3    F-A      F 1.20 4
AL-03-R010     AL-02-03        PIPING SUPPORT                                                         VT-3    F-A      F1.30 6
AL-06-R001     AL-07-06        PIPING SUPPORT                                                         VT-3    F-A      F1.30 AL-01-H008     AL-01-01 SHT. 2 PIPING SUPPORT                                       8                 VT-3    F-A      FI.30 WCRE-30                                               4.1.3 Auxiliary Feedwater (AL)                                                        Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AL-2 I eid2Examinations LSystem: AL 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      F 1.30 AL-04-C002     AL-03-04        PIPING SUPPORT                                                    VT-3    F-A      F 1.30 PAL02-SUP- 1   AL-01-01 SHT. I 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 PAL0 1A-SUP-2  AL-01-01 SHT. 2 PUMP SUPPORT                                   8                  VT-3    F-A      F1.40 WCRE-30                                          4.1.3 Auxiliary Feedwater (AL)                                                        Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE AL-3 SSystem:  AL Component Name Drawing Number Component                                          Size Thickness NDE Method Category Item   Relief Request    Notes AL-03-A001     AL-02-03       PIPING INTEGRAL ATTACHMENTS                                          VT-i    D-A      D1.20 AL-04-R014     AL-06-04       PIPING SUPPORT                                                       VT-3    F-A      F 1.20 4
AL-02-R011I    AL-04-02       PIPING SUPPORT                                                       VT-3    F-A      F1.20 AL-02-C003     AL-0 1-02      PIPING SUPPORT                                                       VT-3    F-A      F 1.30 6
AL-03-A001     AL-02-03       PIPING SUPPORT                                                       VT-3    F-A      F1.30 6
AL-06-C001     AL-07-06       PIPING SUPPORT                                                       VT-3    F-A      F 1.30 TAL01A-SUP-1   AL-07-06       TANK SUPPORT                                                         VT-3    F-A      F1.40 TAL0 IA-SUP-I  AL-07-06       TANK INTEGRAL AYIACHMENT                                             VT-I    D-A      DI.10 WCRE-30                                             4.1.3 Auxiliary Feedwater (AL)                                                       Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.4 Reactor Coolant System (BB)
A. Applicable System Piping and Instrument Drawings
: 1. M-12BB0 1-Reactor Coolant System
: 2. M-12BB02-Reactor Coolant System*
: 3. M-12BB03-Reactor Coolant System
* Except for ASME Class 2 components listed in Section 4.3 B. Classification of Components Details of the classification of the Reactor Coolant System components for I SI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
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-189-50 series.
: 1.        M-189-50BB-00-01           Sheet 1   Reactor Coolant System Primary Loop General Layout
: 2.        M-189-50BB-01-01           Sheet 1   Reactor Coolant Loop 1
: 3.        M-189-50BB-01-02           Sheet 1   Reactor Coolant Pressurizer Relief Header
: 4.        M- 189-50B B-01-04         Sheet 1   Reactor Coolant Pressurizer Spray Line
: 5.        M- 189-5OBB-01-04          Sheet 2   Reactor Coolant Pressurizer Spray Line
: 6.        M-189-5OBB-01-08           Sheet 1   Reactor Coolant Pump "A" Seal Water Injection Line
: 7.        M-189-50BB-02-01           Sheet 1   Reactor Coolant Loop 2
: 8.        M-1 89-50BB-02-02          Sheet 1   Reactor Coolant Pressurizer Safety Valve Lines
: 9.        M-189-50BB-02-1 1          Sheet 1   Reactor Coolant Pump "B" Seal Water Injection Line
: 10.      M-1 89-5OBB-03-0 1        Sheet  1   Reactor Coolant Loop 3
: 11.      M-189-50BB-03-09          Sheet  1   Reactor Coolant Pump "C" Seal Water Injection Line
: 12.      M-189-50BB-04-01          Sheet  1   Reactor Coolant Loop 4
: 13.      M-1 89-50BB-04-07         Sheet  1   Reactor Coolant Pump "D" Seal Water Injection Line
: 14.      M-189-50BB-05-01          Sheet  1   Reactor Coolant Pressurizer Surge Line
: 15.      M-189-5OBB-06-0l           Sheet 1   Reactor Coolant Loop Drain To Reactor Coolant Drain Tank
: 16.      M- 189-50ISI-RBB0 1        Sheet 1   Reactor Vessel
: 17.      M- 189-501SI-RBB0 1        Sheet 2   Reactor Vessel
: 18.      M- 189-50ISI-RBB01         Sheet 3   Reactor Vessel
: 19.      M- 189-50ISI-TBB01         Sheet 1   Pressurizer Vessel
: 20.       M-1 89-50ISI-TBB0 1        Sheet 2   Pressurizer Vessel
: 21.       M-1 89-50ISI-EBB01lA       Sheet 1   Steam Generator EBB01lA
: 22.       M-1 89-50ISI-EBB01 B       Sheet 1   Steam Generator EBB01B
: 23.       M-1 89-50ISI-EBB01lC       Sheet 1   Steam Generator EBB01iC
: 24.       M-1 89-50ISI-EBB01iD       Sheet 1   Steam Generator EBB0 1D
: 25.       M-1 89-50ISI-PUMPS         Sheet 1   IS1 Pumps
: 26.       M-189-50ISI-CRDMPL         Sheet 1   CRDM Platform WCRE-30                                4.1.4 Reactor Coolant System (BB)                                      Revision 0 Page 1 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.4 Reactor Coolant (BR)
E.       Summary of 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 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        P1_. P.22     P.33       INTERVAL Circumferential Shell         B-A             Bi 1.11                                          2           0      0      22 Welds, Reactor Vessel Longitudinal Shell Welds,        B-A             B 1.12-                                          90                 0      99 Reactor Vessel Circumferential Head           B-A             B 1.21--30                                                          0      33 Welds, Reactor Vessel Meridional Head Welds,          B-A             B 1.22--81                                                          2      58 Reactor Vessel Shell-to-Flange Weld,          B-A             B 1.30                                                                                         1 Reactor Vessel                                                                                                                        Note 4 Head-to-Flange Weld,           B-A             B 1.40               --                          10                 0      11 Reactor Vessel                                                                                                                        Note 4 Circumferential Shell-To-        B-B             B2. 11--21                                                          1      02 Head Welds, Pressurizer Longitudinal Shell-To-         B-B             B2.12--20                                                           1      12 Head Welds, Pressurizer Tube Sheet-To-Head            B-B             B2.40--4                                                     0      0      1 Weld, Steam Generator Nozzle-to-Vessel Welds,         B-D             B3.90--80                                                           0      88 Reactor Vessel Nozzle Inside Radius          B-D             B3.100--80                                                          0      88 Section, Reactor Vessel WCRE-30                                                      4.1.4 Reactor Coolant System (BB)                                                  Revision 0 Page 2 of 46

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

==SUMMARY==
AND SCHEDULE Nozzle-to-Vessel Welds,   B-D        B3.ll160           --                            2  26 Pressurizer Nozzle Inside Radius    B-D        B3.120             --                       62   2  2     6 Section, Pressurizer                                                                      Note 1 Nozzle Inside Radius    B-D        B3.140             --                       83   3  2     8 Section, Steam Generator                                                                    Note 1 Reactor Vessel Closure  B-G-1        B6.10                                     54  0 0 54     5 Head Nuts                                                                           Note 2 Reactor Vessel Closure  B-G-1        B6.20             --                      54  0 0 54     5 Studs                                                                             Note 2 Threads in Reactor Vessel B-G-1        B6.40             --                      54  0 0 54    5 Flange                                                                            Note 2 Reactor Vessel Closure  B-G-1        B6.50             --                      54  0 0 54    5 Washers                                                                            Note 2 Bolts &Studs in Pumps    B-G-1       B6.180            --                        4  0 0  1     1 Note 2 Flange Surface, When    B-G-1       B6.190            --                        4  0 0  11 Connection Disassembled,                                                                     Note 2 in Pumps Nuts, Bushings, &     B-G-1       B6.200            --                        40   0  11 Washers in Pumps                                                                         Note 2 Bolts, Studs, & Nuts in B-G-2        B7.20            --                        1*   *
* Note 2 Pressurizer Bolts, Studs & Nuts in  B-G-2        B7.30            --                        8*   *
* Note 2 Steam Generator Bolts, Studs & Nuts in  B-G-2        B7.50            --                        7*   *
* Note 2 Piping WCRE-30                                         4.1.4 Reactor Coolant System (BB)                Revision 0 Page 3 of 46

PLMAANDSHUL CSOMPROGRAM FOURTHN IUMNTERDA SECTI TABLE 1 SECTION XI AND AUGMENTED COMPONENT 

==SUMMARY==
AND SCHEDULE Bolts, Studs & Nuts in   B-G-2          B7.60           --                          4    *     *
* Note 2 Pumps Bolts, Studs & Nuts in   B-G-2          B7.70            --                         3    *     *
* Note 2 Valves Welded Attachments For      B-K          Bl10.10           --                         21         0    01 Vessels, Piping, Pumps and ValvesSee                                                                    Paragraph I, Note 11 Pump Casings        B-L-2         B 12.20           --                         4*         *
* 0
                                                                                                           **See Paragraph I, Note 7 Valve Bodies       B-M-2         B12.50            --                         3*         *
* 1 Exceeding NPS 4                                                                                     *See Paragraph I, Note 8 Vessel Interior     B-N-i         B13.10            --                         1    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           --                         10         0    1 Reactor Vessel Welds in Peripheral     B-O          B 14.20           --                        26    0     0    3                3 CRD Housings                                                                                                 Note 5 Welds in Peripheral ICI    B-O          B14.21            --                         50         0    11 Housings                                                                                                  Note 5 Steam Generator Tubing      B-Q          B 16.20          ----                                 -       - See Paragraph I, Note 10 Piping Component       F-A           FI. 10           --                        77    5   10     7               22 Supports Equipment Supports       F-A           F1.40            --                        79    8   12  11                 31 (Other Than Piping)
WCRE-30                                            4.1.4 Reactor Coolant System (BB)                                     Revision 0 Page 4 of 46

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

==SUMMARY==
AND SCHEDULE Piping Welds Subject to    R-A           R1.1 1              --                      36  3  5  3                11 Thermal Fatigue       Note 6         Note 6 Piping Welds Not Subject    R-A            R1,20               --                      287 8 10 10               28 to a Damage Mechanism      Note 6         Note 6 Piping Welds Subject       --                            USAR               3.6.2   89  0  0  00                            /
To HELB Requirements Reactor Coolant Pump       --             -AUG.l1                        AUG.FW      9*
* 44 Flywheel
* See Paragraph. I, Note 9 Shell Circumferential   C-A           Ci1.10                                       122    1 03 Welds Head Circumferential    C-A           C1 .20--40                                          1 01 Welds Tubesheet-to-Shell Weld   C-A           CI1.30               --                      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-C22 Section in Vessels Without  C-C22                                                -41          0 0 Reinforcing Plate, Greater than 1/2" Nominal Thickness RC Hot Leg SE         R-A           R1.20               --                      41    0   01 UT Exam Note 3 RC Cold Leg SE         R-A           R1.20               --                      42    0   03 UT Exam Note 3 WCRE-30                                               4.1.4 Reactor Coolant System (BB)                            Revision 0 Page 5 of 46

X              COMPROGENSUMARPLANDSHUL FO URTHENTERVA SECIO 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  P_1  P__2  P__3        INTERVAL Pressurizer Nozzle Piping         --                        Code Case       F (DM-R)          3     0     0    1                     1 Overlaid DM Welds Repaired                                     N-770-1                                                            Notes 7, 8 Pressurizer Nozzle Piping         -I3R-05                                     (SS-R)          4     0     1    0                     1 Overlaid SS Welds RepairedNoe7, Pressurizer Nozzle Piping         --                        Code Case        C (DM-P)         3     0     1    0                     1 Overlaid DM WeldsN-71 Preemptive                                             -701Notes                                                               7, 8 Pressurizer Nozzle Piping         -I3R-05                                      (SS-P)         2     0     0    1                     1 Overlaid SS Welds Preemptive                                                                                                              Notes 7, 8 Reactor Vessel Upper Head                        -Code             Case         B4.10         79     0    79   79                   158 Nozzles and Partial                                      N-291 Penetration Welds, Visual                                      Note                                                                  9 Exam_____________
Reactor Vessel Upper Head                       -Code              Case         B4.20         79     0    79    0                    79 Nozzles and Partial                                      N-729-1Noe1 Penetration Welds,                                                                                                           Nt Volumetric/Surface Exam                                                                                            ____________
Reactor Vessel, Alloy                                     Cd ae             B58              85          8  5                      7 600/82/182 bottom-mounted                                      N-od7as2B2-15                         5     5     8                     7 instrument penetrations,                                                                                                        Note 11 Visual Exam Reactor Vessel, Alloy                        -Code              Case        B 15.90         48          8   12                    12 600/82/182 Hot leg nozzle-to-                                  N-722-1Noe1 pipe connections, VisualNoe1 Exam                                           ______                                                    ____________
Reactor Vessel, Alloy            --                       Code Case         B 15.95         40          2    2                     4 600/82/182 Cold leg nozzle-                                   N-722-1                                                              oe1 to-pipe connections, VisualNoe1 Exam Piping, Alloy 600/82/1 82          --                       Code Case         B 15.200        12    24   24   36                    72 Hot leg instrument                                       N-722-1Noe1 connectionsNoe1 WCRE-30                                                   4.1.4 Reactor Coolant System (BB)                                            Revision 0 Page 6 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN COMPONENT OR ITEM                 CODE           CODE                AUG.                   AUG                TOTAL IN    EXAMS BY PERIOD & INTERVAL DESCRIPTION           CATEGORY          ITEM NO.        CATEGORY                ITEM NO.                 SYSTEM P1   P_22 P..3      INTERVAL Piping, Alloy 600/82/1 82                           -Code                Case             B 15.205                   4  0    2    2                4 Cold leg instrument                                             N-722-1Noe1 connectionsNoe1 Locations in Normally                                           MVRP-146                 UH/H                      12      2    3                 6 Stagnant Non-Isolable RCS Branch Lines Subject toNoe1 Thermal Fatigue_______
Locations in Normally                             -MRP-146                                 DH                      33      3    6                9 Stagnant Non-Isolable RCS Branch Lines Subject toNoe1 ThermalFatigue______________
Locations in Normally                                           MRP-146                    UH                      1 Stagnant Non-Isolable RCS Branch Lines Subject toNoe1 Thermal Fatigue______________                                                   ________                  ______
Unmitigated Butt Weld at Hot                                         Code Case                  A-2                     44      4    4                12 Leg Operating Temperature <                                           N-770-1 625&deg;F________
Unmitigated Butt Weld at                                         Code Case                    B44                            4    4                12 Cold Leg Operating                                              N-770-I Temperature > 525&deg;F and <
580&deg;F                                                _______________________________________________
Note 1: This Code Item Number is not included in Section XI12007 Edition with the 2008 Addenda, examination is required per 10CFR50.55a(b)(2)(xxi).
Note 2: Examination of Pressure Retaining Bolting is performed in accordance with Categories B-G-1 and B-G-2. See Notes 1-6 and 30 in Paragraph I for selection and scheduling criteria.
Note 3: Three dissimilar metal welds were selected under RI-ISI requirements. All of the welds subject to PWSCC have additional augmented examinations performed per Code Case N-770-1. The RI-ISI exam may be conducted at the same time as the N-770-1 exam.
Note 4: Examination of Reactor Vessel Shell-to-Flange and Head-to Flange welds are performed in accordance with Category B-A, Note 5.
Note 5: Welds in Peripheral CRD Housings (Category B-O, Item No. B14.20) are shown on drawing M-189-501SI-RBB01 in Section A-A and include 26 locations as discussed in Note 6 of this drawing. Welds in Peripheral ICI Housings (Category B-O, Item No. B 14.21) are also shown on drawing M-189-501S1-RBB01 in Section A-A and include 5 locations, Penetrations 74-78.
Note 6: See Section H for an explanation of Category R-A and Item R1.XX nomenclature.
Note 7: The Pressurizer nozzle-to-safe end welds and safe end-to-piping welds were overlaid in Interval 3 during P.115. Per 13R-05, and Code Case N-770-1, 25% of these overlaid welds are now included in the ISI Program and examined once each inspection interval.
Note 8: See Section F for an explanation of the Category and Item designations.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Note 9: The VE exams are extended to once every     3 rd refueling outage per Note 4 of Code Case N-729-1. The acceptability of this frequency (EDY calculation) is documented in procedure STS PE-040E.
Note 10: The volumetric/surface exams are performed once every 8 calendar years. The acceptability of this frequency (MIY calculation) is documented in procedure STS PE-040E.
Note 11: The BMI~s are examined every other refueling outage beginning in RF17.
Note 12: The RPV Hot leg nozzle-to-pipe connections are required to be examined each refueling outage; however, per Note 5 of Table 1 of Code Case N-722-1, an ultrasonic examination is acceptable in lieu of the VE exam. Ultrasonic examinations (that meet the requirements of Note 5 of the subject Code Case) are tentatively scheduled for RF23 and RF26. These UT exams will be credited in lieu of the VE exams.
Note 13: The examination frequency requirement of these components is once per Interval.
Note 14: The examination frequency requirement of these components is each refueling outage.
Note 15: The initial examination of the MRP-146 locations was required in RF17. The MRP-146 locations have been seperated into 2 items: UK/H and DH. The UH-H item requires examination each refueling outage beginning with RFl9; and the DH items require examination every other refueling outage beginning in RF 19.
Note 16: This is a "One time" exam to be performed the first refueling outage after June 1, 2016 (RLF21).
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WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.4 Reactor Coolant (BB)
F. Augmented ISI Requirements The following Augmented IST 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, 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-33 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 Regulatory Guide 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 "AUG. 1" and Item No. "AUG.FW" but may be performed at anytime during the inspection interval. Approved Amendment 106 of the Technical Specifications allows examinations to be completed on each flywheel at an interval not to exceed 20 years
: 3. USNRC Regulatory Guide 1.65. Revision 0. Materials and Inspections 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 Examination Category B-G-1 of the 2007 Edition with the 2008 Addenda are understood to satisfy the WCNOC commitment to Regulatory Guide 1.65. These examinations are 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 1. 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.
: 7. Pressurizer Nozzle Weld Overlays-In Interval 3, a mitigation strategy was performed on the Pressurizer nozzle-to-safe end dissimilar metal (DM) piping welds by installation of a full structural weld overlay (WOL). Due to the configuration, this modification also encompassed the adjacent SS piping welds. These WOL configurations are tracked under Code Case N-770-l Inspection Items of Table 1, and under I3R-05. Examinations are on a 25% sampling basis each inspection interval. The components tracked under Code Case N-770-l are Item F (DM-R) for DM repaired welds, and Item C (DM-P) for DM preemptive welds,. The components tracked under I3R-05 are Item (SS-R) for SS repaired welds and Item (SS-P) for SS preemptive welds.
: 8. Code Case N-729-1-The NRC has mandated that ISI programs shall be augmented by the implementation of Code Case N-729- 1, with the conditions stated in 10 CFR 50.55a(g)(6)(ii)(D) by December 31, 2008.
: 9. Code Case N-722-l- The NRC has mandated that ISI programs shall be augmented by the implementation of Code Case N-722-l, with the conditions stated in 10 CFR 50.55a(g)(6)(ii)(E). The inspections required by this Code Case are required to begin the refueling outage after January 1, 2009.
: 10. MRP-146, Material Reliability Program: Management of Thermal Fatigne in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines-The evaluation for this program is documented in WCRE-25, Program Plan for Thermal Fatigue: The initial inspection of locations that did not pass the screening criteria in the applicable 2.1 sections of MRP-146 to be performed prior to the end of the next refueling outage that is initiated after January 31, 2009 (RFl17). Revision 1 of MRP-146 provides the option of performing periodic inspections in lieu of monitoring. Locations with UH/H configuration are WCRE-30                              4.1.4 Reactor Coolant System (BB)                                       Revision 0 Page 9 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN to be inspected every refueling outage (RFO) beginning with the first RFO after January 31, 2012 (RF 19).
Locations with the DR configuration are to be inspected every other RFO beginning with the first RFO after January 31, 2012 (RF 19). Such inspections shall be conducted in accordance with the requirements of section 2.4 of MRP-146, volumetric examination (UT or RT). Per letter MRP 2015-019, applicable section 2.3.2, a "One time examination of UH configured piping greater than 2-inches NPS and not larger than 4-inches NPS and having the potential of previous cold in-leakage" shall be performed no later that the first refueling outage commencing after June 1, 2016.
: 11. Code Case N-770 The NRC has mandated that ISI programs shall be augmented by the implementation of Code Case N-770-1, with the conditions stated in 10 CFR 50.55a(g)(6)(ii)(F). The inspections required by this Code Case are required to begin the refueling outage after August 22, 2011.
An additional notation is that the visual examination requirements of this Code Case are encompassed by the requirements of Code Case N-722- 1.
G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWB-5000, the Class 1 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 XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining components within the Reactor Coolant 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 lSI A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class 1 and 2 piping welds at WCGS. This program is described in detail in Section 2.3. Reactor Coolant System welds selected for examination per the RI-ISI program are listed in Tables BB-1, BB-2 and BB-3. Since the EPRI methodology used for the RI-ISI Program does not prescribe Code Examination Category and Item Numbers, guidance was taken fr-om 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-112657 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 through 4-4 of TR-1 12657 Rev. B-A.
Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table BB-1 (Period 1 Examinations), Table BB-2 (Period 2 Examinations), and Table BB-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 Category B-G-2, Notes 1 and 3.
: 2. Bolting is required to be examined only when a connection is disassembled or bolting is removed. For components other than piping, examination of bolting is required only when the component is examined under Examination Category B-B, B-L-2 and B-M-2. Examination of bolted connection is required only once during the interval. See Category B-G-2, Notes 1 and 2.
: 3. Examination may be alternatively performed on the bolts or studs in pump PBB01 B, PBB01 C, or PBB01D. See Category B-G-I, Note 3.
: 4. Examination of the pump flange will be pefformed when connection is disassembled for maintenance.
Examination may be alternatively performed on the pump flange of PBB01B, PBB01C, or PBB01D. See Category B-G-l, Notes 3 and 4.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN
: 5. Examination of the pump nuts, bushings and washers may be alternatively performed on the pump nuts, bushings and washers of PBB01B, PBB01C, or PBB01D. See Category B-G-l, Notes 3 and 4.
: 6. Examination of the steam generator hotleg and coldieg manway bolting may be alternatively performed on the bolting ofEBB01A, EBB01B, or EBB01D. See Category B-G-l, Notes 3 and 4.
: 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 or repair. The 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 that perform 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 to 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 fr'equency of examination of a 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 Generator Management," provides details of SG tubing inspection activities.
: 11. The 4 Pressurizer Seismic Supports (Code Item F1 .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
: 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. An enhanced VT-i examination may be performed in lieu of the UT examination per I1OCFR50.55a(b)(2)(xxi)(A).
: 15. Examination of the Reactor Nozzle-to-Vessel welds is performed in accordance with Code Case N-6 13-1, which allows an alternative examination volume to be utilized.
: 16. Examination of the Reactor Nozzle-to-Vessel inner radius area is performed in accordance with Code Case N-648-1, and the conditions specified in Revision 17 of Regulatory Guide 1.147.
: 17. These locations are subject to PWSCC. This examination may be performed at the same time as the Code Case N-770-1 exam.
: 18. Calibration of the instruments for this location will utilize reference blocks Axial/Flat 16-0 1 and Circ 16-01.
: 19. Calibration of the instruments for this location will utilize reference blocks Ax 6-01 and Circ 6-01.
: 20. Calibration of the instruments for this location will utilize reference blocks Ax 8-01 and Circ 8-01.
: 21. See CCP 11977 and WO 05-277921-000 for the modified thickness of these components.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN
: 22. These components have been selected in accordance with the Augmented ISI requirements of Code Case N-729-1 and conditions of 10 CFR 50.55a(g)(6)(ii)(D). The non-visual examination of these components shall utilize approved calibration blocks as required by the demonstrated procedure. The Item 4.10 components are to be examined every third refueling outage (an IWA-2212 VT-2 exam is performed under the insulation through multiple access ports in outages that the VE is not performed). The Item 4.20 components are to be examined every fifth refueling outage. The exams performed in RF15 under NRC Order EA-03-009 are credited for the baseline examinations.
: 23. These components have been selected in accordance with the Augmented 1S1 requirements of Code Case N-722-1 and conditions of 10 CFR 50.55a(g)(6)(ii)(E). These components to be examined every other refueling outage beginning in RF17.
: 24. These components have been selected in accordance with the Augmented 151 requirements of Code Case N-722-1 and conditions of 10 CFR 50.55a(g)(6)(ii)(E). These components to be examined every refueling outage beginning in RF17. Per Note 5 of Table 1 of the Code Case, an ultrasonic examination is acceptable in lieu of the VE examination. Ultrasonic examinations of these components are scheduled in RF17 and in RF20.
: 25. These components have been selected in accordance with the Augmented 1S1 requirements of Code Case N-722-1 and conditions of 10 CFR 50.55a(g)(6)(ii)(E). These components to be examined once per Interval.
: 26. These components have been selected in accordance with the Augmented ISI requirements of Code Case N-722-1 and conditions of 10 CFR 50.55a(g)(6)(ii)(E). These components to be examined every refueling outage beginning in RF17.
: 27. These locations have been selected per MRP- 146 guidance. See Paragraph F.10 above. The examination of these locations are to be in accordance with Section 2.4 of MRP-146. The initial exams were performed in RF17. The periodic examinations began in RF19. Locations designated as Item UH/H shall be examined each refueling outage. Locations designated as Item DH shall be examined every other refueling outage.
: 28. These components have been selected in accordance with the Augmented 1S1 requirements of Code Case N-770-l and conditions of 10 CFR 50.55a(g)(6)(ii)(F).
: 29. This location selected per MRP letter 2015-0 19. This is a "one time" examination to be performed in accordance with Section 2.3.2 of MRP 2015-019. This examination shall be performed in the first refueling outage commencing after June 1, 2016 (RF2 1). This examination is a supplement to the MRP-146 exams..
: 30. WCNOC procedures require that the 1S1 Coordinator be informed whenever a Class 1 component is disassembled for repair or maintenance and that the ISI Coordinator specify if a VT-i and/or VT-3 exam is required. Whenever a component is required to have a B-G-2 or B-M-2 exam performed, the ISI Coordinator shall revise the applicable Table BB-l, BB-2, or BB-3 and Table i to reflect the component being examined. Reference procedures AP 16A-003, ASME Section XI Repair and Replacement Program; and Al i6C-007, Work Order Planning.
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WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB.1
[Period 1 Examinations
[System: BB Relief Request or Component Name    Drawing Number     Component Description                                     Size Thickness NDE Method Category Item    Cal Block         Notes CH-I 01-1 04-A    ISJ-RBB01 SHIT I   RV CLOSURE HEAD MERIDIONAL WELD                           NA        8.25     UT     B-A      B 1.22      177 TBB03-CIRCUJM-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 SHlT. 1  SAFETY NOZZLE A TO TOP HEAD WELD                         NA         1.90     UIT    B-D      B3.110      101 TBB03-10B-B-W     ISI-TBB03 SHT. 1   SAFETY NOZZLE B TO TOP HEAD WELD                         NA         1.90     UT     B-D      B3.110      101 TBB03-10B-A-IR    IS1-TBB03 SHIT. 1  SAFETY NOZZLE A INNER RADIUS                             NA         1.90     UT     B-D      B3. 120     101                14 TBB03-I 0B-B-IR   ISI-TBB03 SI-IT. 1 SAFETY NOZZLE B INNER RADIUS                              NA        1.90     UT     B-D      B3.120      101                14 EBB01C-IB-IR      ISI-EBB01C SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                        NA         5.00     UIT    B-D      B3.140      104                14 EBB01D-1A-IR      ISI-EBB01D SI-T. 1 PRIMARY INLET NOZZLE INNER RADIUS                        NA         5.00     UT     B-D      B3. 140     104                14 EBB01D-1B-IR      ISI-EBB01D SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                        NA         5.00     UT     B-D      B3. 140     104                14 TBB03-SKIRT-W     ISI-TBB03 SHT. 1   SUPPORT SKIRT INTEGRAL ATTACHMENT                                            PT     B-K      B10.1 RV-INTER1OR       ISI-RBB01 SHT. 1   REACTOR VESSEL INTERIOR                                                     VT-3    B-N-1    B13. 10 EBB01A-SEAM-3-W   ISI-EBB01A SilT. I STUB BARREL TO SHELL SECTION A                           NA         3.0      UT     C-A      CI.10       102 EBB01A-SEAM-6-W   ISI-EBB01A SHT. 1 TRANSITION CONE TO SHELL SECTION C                        NA         3.76     UT     C-A      CI.10       102 EBB01A-SEAM-2-W   ISI-EBB01A SI-T. 1 TUBESHEET TO STUB BARREL                                 NA         3.0      UT     C-A      C 1.30      102 EBB01A-1 1-W      ISI-EBB01A SHT. 1 FEED WATER NOZZLE WELD                                    NA         3.76   UT/MT    C-B      C2.21       102 EBB01 A- I 1-IR   ISI-EBB01A SHT. I FEED WATER NOZZLE INNER RADIUS                            NA         3.76     UT     C-B      C2.22       102 BB-02-R01 1       BB-01-02           PIPING SUPPORT                                                              VT-3    F-A      FI.1 BB-02-R015        BB-01-02           PIPING SUPPORT                                                              VT-3    F-A      FI.1 BB-04-R009        BB-01-04 SHT. 1    PIPING SUPPORT                                           4                  VT-3    F-A      Fl 10 BB-04-H009        BB-01-04 SILT. 2   PIPING SUPPORT                                           4                  VT-3    F-A      FI.10 WCRE-30                                                    4.1.4 Reactor Coolant System (BB)                                                           Revision 0 Page 13 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-1 IPeriod 1 ExaminationsI
[System: BB Relief Request or Cal Block         Notes Component Name Drawing Number   Component Description                                      Size Thickness NDE Method Category Item BB-04-R033     BB-01-04 SHT. 2  PIPING SUPPORT                                             4                 VT-3    F-A      Fl.10 CRDMPL-SUP- 1  ISI-CRDMPL       CRDM Upper Seismic Support                                                   VT-3    F-A      F1.40 CRDMPL-SUP-2   ISI-CRDMPL       CRDM Upper Seismic Support                                                   VT-3    F-A      F1.40 EBB01A-01 231  M-717-00002      SG A LOWER COLUMN SUPPORT                                                    VT-3    F-A      F1.40 EBB01A-05 231  M-717-00009      SG A LOWER LATERAL SUPPORT                                                   VT-3    F-A      F1.40 PBB01lA-SUP-1  ISI-PUMPS        RCP A TIE ROD SUPPORT                                                        VT-3    F-A      F 1.40 PBB01lA-SUP-lA ISI-PUMPS        RCP A COLUMN SUPPORT                                                         VT-3    F-A      F 1.40 RBB-01-01      ISI-RBB01 SHT. 1 RV SUPPORT PAD 1                                                             VT-3    F-A      F1.40                     14R-02 TBB03-SKIRT-W  ISI-TBB03 SHT. 1 SUPPORT SKIRT SUPPORT                                                        VT-3    F-A      F1.40 BB-0 l-F001    BB-05-01         14" NOZZLE ON 60-BCA-29" TO 14" PIPE                       14                 UT     R-A      RI ll      130                 12 1.25 BB-02-F019     BB-01-02         3" PIPE TO VALVE PCV-456A                                  3       0.438      UT     R-A      RI.ll      112             12, 13 BB-04-FW3 14   BB-01-04 SHT. 1  4" PIPE TO 4" ELBOW                                        4       0.531      UT     R-A      RI.1l      114             12, 13 BB-04-F010     BB-01-04 SHT. 2  4" PIPE TO 4" ELBOW                                        4       0.53 1     UT     R-A      RI.20      114                 12 BB-04-S007-D   BB-01-04 SPIT. 2 4" PIPE TO 4" ELBOW                                        4       0.531      UT     R-A      R1.20      114                 12 BB-04-S007-E   BB-01-04 SHT. 2  4" ELBOW TO 4" PIPE                                        4       0.53 1     UIT    R-A      R1.20      114                 12 BB-08-FW308    BB-01-08         2"'PUP PIECE TO 2" PIPE                                    2       0.344      UT     R-A      R1.20      156                 12 BB-08-FW309    BB-01-08         2" PIPE TO 2"X2"X3/4" TEE                                  2       0.344      UT     R-A      R1.20      156                 12 BB-08-FW3 11   BB-01-08         2"X2"X3/4" TEE TO 2" PIPE                                  2       0.344      UT     R-A      R1.20      156                 12 BB-08-FW3 12   BB-01-08         2" PIPE TO 2" ELBOW                                        2       0.344      UIT    R-A      R1.20      156                 12 BB-02-FW900    BB-01-02         6" ELBOW TO 6" PIPE                                        6       0.7 19     UT     R-A      R1.20      117                 12 RV-30 1-121-A  ISI-RBB01 SHT. 1 LOOP # 1 RPV OUTLET NOZZLE TO SAFE-END                     29       2.92      UT     R-A      R1.20      179                  12 WCRE-30                                                  4.1.4 Reactor Coolant System (BB)                                                         Revision 0 Page 14 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE    BB-1 I~rodT    Eaminations  I
[System: BB Relief Request or Component Name  Drawing Number    Component Description                                     Size Thickness NDE Method Category Item     Cal Block          Notes RV-302-12 1-A   ISI-RBBO1 SHT. 1  SAFE-END TO LOOP #1 RPV INLET NOZZLE                      27.5     2.79      UT     R-A      R1.20        179                12 RV-302-12 1-Dl  ISI-RBB01 SHT. 1  SAFE-END TO LOOP #4 RPV INLET NOZZLE                      27.5     2.79      UT     K-A      RI.20        179                12 RV-201-151-1   ISI-RBB01 SHT. 1 RV BMI PENETRATION     I                                                     VE     N-722-1  B15.80 RV-201-151-2   ISI-RBB01 SHT. 1 RV BMI PENETRATION    2                                                      VE     N-722-1  B 15.80 RV-201-151-3   ISI-RBBO1 SHT. 1 RV BM1 PENETRATION    3                                                      VE     N-722-1  B 15. 80 RV-201-151-4   ISI-RBB01 SHT. I RV BM1 PENETRATION    4                                                      VE     N-722-1  B 15.80 RV-201-151-5   ISI-RBB01 SHT. 1 RV BM1 PENETRATION    5                                                      VE     N-722-1  B 15.80 RV-201-151-6   ISI-RBBO1 SHT. I RV BMI PENETRATION    6                                                      VE     N-722-1  B 15.80 RV-201-151-7   ISI-RBB01 SHT. I RV BMI PENETRATION    7                                                      VE     N-722-1  B 15.80 RV-201-151-8   ISI-RBBO1 SHT. 1 RV BM1 PENETRATION    8                                                      VE     N-722-1  B15.80 RV-201-151-9   ISI-RBBOI SHT. I RV BMI PENETRATION    9                                                      VE     N-722-1  B15.80 RV-201-151-10  ISI-RBB01 SHT. I RV BM1 PENETRATION    10                                                     VE     N-722-1  B 15.80 RV-201-151-11I ISI-RBB01 SHT. 1 RV BM1 PENETRATION    11                                                     VE     N-722-I  B 15.80 RV-201-151-12  ISI-RBB01 SHT. 1 RV BMI PENETRATION     12                                                    VE     N-722-1  B15.80 RV-201-15l-13  ISI-RBB0 1 SHlT. 1 RV DM1 PENETRATION    13                                                     VE     N-722-1  B 15.80 RV-201-151-14  ISI-RBB01 SLIT. 1 RV BMI PENETRATION    14                                                     VE     N-722-1  B 15.80 RV-201-151-15  ISI-RBBO1 SHT. I RV BM1 PENETRATION    15                                                     VE     N-722-1  B 15.80 RV-201-151-16  ISI-RBB01I SHlT. 1 RV BMI PENETRATION    16                                                     VE     N-722-1  B 15.80 RV-201-151-17  ISI-RBB01 SHT. 1 RV BMI PENETRATION    17                                                     VE     N-722- I B15.80 RV-201-151-18  ISI-RBB01 SHT. 1 RV BMI PENETRATION    18                                                     VE     N-722-I  B15.80 RV-201-151-19  ISI-RBBO1 SHT. I RV BM1 PENETRATION    19                                                     VE     N-722-1  B 15.80 RV-201 -151-20 ISI-R.BB01 SHT. 1 RV BM1 PENETRATION    20                                                     VE     N-722-1  B 15.80 RV-201-151-21  ISI-RBB01 SilT. 1 RV BMI PENETRATION    21                                                     YE     N-722-1  B 15.80 RV-201 -151-22 ISI-RBBO01 SHT. 1 RV BMI PENETRATION    22                                                     VE     N-722-1  B 15.80 RV-201-151-23  ISI-RBB01 SHT. 1 RV BMI PENETRATION    23                                                     VE     N-722-1  B15.80 RV-201-151-24  ISI-RBB01 SHT. I RV BMI PENETRATION    24                                                     YE     N-722-1  B 15.80 RV-201-151-25  ISI-RBB0 1 SHT. 1 RV BMI PENETRATION    25                                                     VE     N-722-1  B 15.80 23 RV-201-151-26  ISI-RBBO01 SHT. 1 RV BMI PENETRATION    26                                                     VE     N-722-1  B15.80 RV-201-151-27  ISI-RDBB1 SHlT. I RV BMI PENETRATION    27                                                     YE     N-722-1  BI5.80 RV-201-151-28  ISI-RBB01 SHT. 1 RV DM1 PENETRATION    28                                                     YE     N-722-1  B15.80 RV-20l- 151-29 ISI-RBB01 SHT. I RV BM1 PENETRATION    29                                                     VE     N-722-1  B 15.80 RV-201-151-30  ISI-RBB01 SHIT. I RV BM1 PENETRATION    30                                                     VE     N-722-1  B 15.80 RV-201-151-31  ISI-RBB01 SHlT. 1 RV BMI PENETRATION    31                                                     VE     N-722-1  B15.80 RV-201-151-32  ISI-RBB01 SHlT. 1 RV BMI PENETRATION    32                                                     VE     N-722-1  B 15.80 RV-201-151-33  ISI-RBB01 SHT. I RV BM1 PENETRATION    33                                                     VE     N-722-1  B 15.80 RV-201-I51-34  ISI-RBB01 SHT. 1 RV BM1 PENETRATION    34                                                     VE     N-722-1  B 15.80 RV-201-151-35  ISI-RBB01 SHT. I RV BMI PENETRATION    35                                                     YE     N-722-1  B 15.80 RV-201-151-36  ISI-RBB01 SHT. 1 RV DMI PENETRATION    36                                                     YE     N-722-1  B15.80 RV-20 1-151-37 ISI-RBB01 SIHT. I RV BM1 PENETRATION    37                                                     VE     N-722-1  B 15.80 WCRE-30                                                    4.1.4 Reactor Coolant System (BB)                                                          Revision 0 Page 15 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE    BB-1 Ieo  Examinations Isystem: BB Relief Request or Component Name     Drawing Number       Component Description                                     Size Thickness NDE Method Category Item     Cal Block         Notes RV-201-151-38     ISI-RBB01   SHT. 1  RY  BMI   PENETRATION 38                                                     VE     N-722-1  B 15.80                         23 RV-201-151-39     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 39                                                     VE     N-722-1  B 15.80                         23 RV-201-151--40    ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 40                                                     VE     N-722-1  B15.80                          23 RV-201-151-41     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 41                                                     VE     N-722-1  B 15.80                         23 RV-201-151-42     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 42                                                     VE     N-722-1  B15.80                          23 RV-201-151-43     ISI-RBB01   SHT. I  RV  BMI   PENETRATION 43                                                     VE     N-722-1  815.80                          23 RV-201-1 51--44   ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 44                                                     VE     N-722-1  B 15.80                         23 RV-201-151-45     ISI-R.BB01  SHT. 1  RV  BMiI  PENETRATION 45                                                     VE     N-722-1  B 15.80                         23 RV-201-1 51--46   ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 46                                                     VE     N-722-1  B 15.80                         23 RV-201-151-47     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 47                                                     YE     N-722-1  B 15.80                         23 RV-201-151-48     ISI-RBB01   SI-T. 1  RV  BMI   PENETRATION 48                                                     YE     N-722-1  B 15.80                         23 RV-201-151-49     ISI-RBB01   SI-IT. I  RV  BMI   PENETRATION 49                                                     YE     N-722-1  B 15.80                         23 RV-201 -151-50    ISI-RBB01   SHT. I  RV  BMI   PENETRATION 50                                                     VE     N-722-1  B15.80                          23 RV-201-151-51     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 51                                                     YE     N-722-1  B 15.80                         23 RV-201-151-52     ISI-RBB01   SHT. I  RV  BMI   PENETRATION 52                                                     YE     N-722-1  B 15.80                         23 RV-201-151-53     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 53                                                     VE     N-722-1  B 15.80                         23 RV-201-151-54     ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 54                                                     YE     N-722-1  B 15.80                         23 RV-201-151-55     ISI-RBB01   SHT. I  RV  BMI   PENETRATION 55                                                     YE     N-722-1  B15.80                          23 RV-201-151-56     ISI-RBB01   SHIT. I  RV  BMI   PENETRATION 56                                                     YE     N-722-I  815.80                          23 RV-201- 151-57    ISI-RBB01   SHT. 1  RV  BMI   PENETRATION 57                                                     YE     N-722-1  B15.80                          23 RV-201-151-58     ISI-RBB01   SHT. 1  RV  BMIT  PENETRATION 58                                                     YE     N-722-1  815.80                          23 RV-301 -121 -A     ISI-RBB01   SHT. 1 LOOP   #1 RPV OUTLET NOZZLE   TO SAFE-END                29       2.92       VE     N-722-1  815.90                       24 RV-30 1-12 1-B     ISI-RBB01   SHT. 1 LOOP   #2 RPV OUTLET NOZZLE   TO SAFE-END                29       2.92       YE     N-722-1  B15.90                       24 RV-301-121-C       ISI-RBB01I  SHT. I LOOP   #3 RPV OUTLET NOZZLE   TO SAFE-END                29       2.92       YE     N-722-1  B 15.90                      24 RV-301-121-D       ISI-RBB01   SHT. I LOOP   #4 RPV OUTLET NOZZLE   TO SAFE-END                29       2.92       YE     N-722-1  815.90                       24 BB-01-S 102-TW-T   BB-01-01             LOOP   #1 NARROW   RANGE THERMOWELL,    TOP                                  YE     N-722-1  B 15.200                     26 BB-0 1-S 102-TW-I  BB-01-01             LOOP   #1 NARROW   RANGE THERMOWELL,    INSIDE                               YE     N-722-1  B15.200                      26 BB-01-S102-TW-O    BB-01-01             LOOP   # 1 NARROW  RANGE THERMOWELL,    OUTSIDE                              YE     N-722-1  815.200                      26 BB-01 -S202-TW-T   BB-02-01             LOOP   #2 NARROW   RANGE TH-ERMOWELL,   TOP                                  YE     N-722- I B 15.200                     26 BB-01-S202-TW-I    BB-02-01             LOOP   #2 NARROW   RANGE THERMOWELL,    INSIDE                               YE     N-722-1  B 15.200                     26 BB-01-S202-TW-O    BB-02--01            LOOP   #2 NARROW   RANGE THERMO WELL,   OUTSIDE                              VE     N-722-1  B 15.200                     26 BB-01-S302-TW-T    BB-03-01             LOOP   #3 NARROW   RANGE THERMOWELL,    TOP                                  YE     N-722-1  B815,200                     26 BB-01-S302-TW-I    BB-03-01             LOOP   #3 NARROW   RANGE TH-ERMO WELL,  INSIDE                               YE     N-722-1  B 15.200                     26 BB-01 -S302-TW-O   BB-03-01             LOOP   #3 NARROW   RANGE THERMO WELL,   OUTSIDE                              VE     N-722-1  B 15.200                     26 BB-01 -S402-TW-T   BB-04-01             LOOP   #4 NARROW   RANGE THERMOWELL,    TOP                                  YE     N-722-1  B 15.200                     26 BB-01-S402-TW-I    BB-04-01             LOOP   #4 NARROW   RANGE THERMO WELL,   INSIDE                               YE     N-722-1  815.200                      26 BB-01-S402-TW-O    BB-04-01             LOOP   #4 NARROW   RANGE THERMOWELL,    OUTSIDE                              YE     N-722-1  B15.200                      26 HB-24-W502         BB-06-01             2' ELBOW TO2" PIPE                                        2       0.344      UT     MRP-146  DH           156             27 WCRE-30                                                         4.1.4 Reactor Coolant System (BB)                                                           Revision 0 Page 16 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-1
[Period 1 Examinations SSystem: BB Relief Request or Component Name  Drawing Number    Component Description                                     Size Thickness NDE Method  Category Item Cal Block          Notes HB-24-W5 12     BB-06-0 1         2' ELBOW TO2" PIPE                                                0.344      UT     MRF-146   DHI      156              27 BG-23-W596A     BG-03-23          2" ELBOW TO2" PIPE                                                0.344      UT     MRP-1 46  DH       156              27 BG-21 -F027A BG-01-21                                                                                       UT     MRP-146   UH/H     112              27 3" PIPE TO 3" NOZZLE ON BB-56-BCA-27 1/2"                 3       0.438 BG-21 -F014A    BG-01-21          3" PIPE TO 3" NOZZLE ON BB-01-BCA-27 1/2"                 3       0.438      UIT    MRP-146   UH       112              29 RV-301-121-A    ISI-RBB0 1 SHT. 1 LOOP #1 RPV OUTLET NOZZLE TO SAFE-END                     29       2.92    UT/VE    N-770-1   A-2      179              28 RV-301-121-B    ISI-RBB01I SHT. l LOOP #2 RPV OUTLET NOZZLE TO SAFE-END                     29       2.92    UT/VE    N-770-1   A-2      179              28 RV-30 1-12 1-C  ISI-RBB01 SLIT. 1 LOOP #3 RPV OUTLET NOZZLE TO SAFE-END                     29       2.92    UT/VE    N-770-1   A-2      179              28 RV-301 -121 -D  ISI-RBB01 SHT. 1  LOOP #4 RPV OUTLET NOZZLE TO SAFE-END                     29       2.92    UT/VE    N-770-1   A-2      179              28 RV-302-12 1-A  ISI-RBB01 SHT. 1   SAFE-END TO LOOP #1 RPV INLET NOZZLE                      27.5    2.79      UT      N-770-1   B        179             28, RV-302-12 1-B  ISI-RBB01 SHT. 1   SAFE-END TO LOOP #2 RPV INLET NOZZLE                      27.5    2.79      UT      N-770-1   B        179             28, RV-302-121-C   ISI-RBB01 SHT. 1   SAFE-END TO LOOP #3 RPV INLET NOZZLE                      27.5    2.79      UT      N-770-1   B        179             28, RV-302-121-D   ISI-RBB0 1 SHT. I  SAFE-END TO LOOP #4 RPV INLET NOZZLE                      27.5    2.79      UT      N-770-1   B        179             28, WCRE-30                                                 WCRE-304.1.4 Reactor Coolant System (BB)                                                         Revision 0 Page 17 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2 IPeriod 2 Examinations
[System: BB Relief Request or Component Name     Drawing Number     Component Description                                     Size Thickness  NDE Method Category Item     Cal Block         Notes CH-101-104-B       ISI-RBB01 SHlT. 1  RV CLOSURE HEAD MERIDIONAL WELD                           NA        *8.25     UT     B-A      B 1.22       177 CH-10 1-104-C      ISI-RBB0 1 SHT. 1  RV CLOSURE HEAD MERIDIONAL WELD                           NA         8.25     UT     B-A      B 1.22       177 TBB03-CIRCUM- 1 -W ISI-TBB03 SHlT. 1  SHELL TO UPPER HEAD WELD                                  NA         1.90     UT     B-B      B2.11 101 TBB03-SEAM-4-W     ISI-TBB03 SHT. 1   SHELL TO UPPER HEAD LONGITUDINAL WELD                     NA         1.90     UT                           101 B-B      B2.12 TBB03-10B-C-W      ISI-TBB03 SHlT. 1  SAFETY NOZZLE C TO TOP HEAD WELD                          NA         1.90     UT     B-D      B3.1 10      101 TBB03-10B-D-W      ISI-TBB03 SHlT. 1  RELIEF NOZZLE D TO TOP HEAD WELD                          NA         1.90     UT     B-D      B3.110       101 TBB03-10B-C-IR     ISI-TBB03 SHlT. 1  SAFETY NOZZLE C INNER RADIUS                              NA         1.90     UT     B-D      B3. 120      101 14 TBB03-10B-D-IR     ISI-TBB03 SHlT. 1  RELIEF NOZZLE D INNER RADIUS                              NA         1.90     UT     B-D      B3. 120      101             14 EBB01 C-1A-IR      ISI-EBB01C SHlT. 1 PRIMARY INLET NOZZLE INNER RADIUS                         NA         5.00     UT     B-D      B3. 140      104             14 EBB01B-1A-IR.      ISI-EBB01B SHlT. 1 PRIMARY INLET NOZZLE INNER RADIUS                         NA         5.00     UT     B-D      B3. 140      104             14 EBB01B-1B-IR       ISI-EBB01B SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                         NA         5.00     UT     B-D      B3. 140      104             14 RV-INTERIOR        ISI-RBB01 SHlT. 1                                                                               VT-3    B-N-i    B 13. 10 REACTOR VESSEL INTERIOR EBBO1A-SEAM-5-W    ISI-EBB01A SHT. 1 SHELL SECTION B TO TRANSITION CONE                         NA         3.00     UT     C-A      CI.10        102 EBB01A-SEAM-8-W    ISI-EBB01A SHT. 1 SHELL SECTION D TO TOP HEAD                                NA         3.95     UT     C-A      C 1.20       102 BB-04-R012         BB-0 1-04 SHT. 1   PIPING SUPPORT                                            4                  VT-3    F-A      FI.1 BB-04-R017         BB-01-O4 SHT. 1    PIPING SUPPORT                                            6                  VT-3    F-A      FI.1 BB-04-R021l        BB-01-04 SHT. I    PIPING SUPPORT                                            4                  VT-3    F-A      FI.1 BB-04-C006         BB-01-04 SHT. 2    PIPING SUPPORT                                            4                  VT-3    F-A      FI.10 BB-04-C0100        BB-01-04 SHT. 2    PIPING SUPPORT                                            4                  VT-3    F-A      Ft.1 BB-04-H001         BB-01-04 SHT. 2    PIPING SUPPORT                                            4                  VT-3    F-A      FI.1 BB-04-H005         BB-01-04 SHT. 2                                                              4                  VT-3    F-A      FI.1 PIPING SUPPORT WCRE-30                                                      4.1.4 Reactor Coolant System (BB)                                                             Revision 0 Page 18 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BB-2 IPeriod 2 Examinations
[ Systm:BB Relief Request or Component Name Drawing Number   Component Description                                      Size Thickness NDE Method Category Item   Cal Block         Notes BB-02-H001     BB-02-02         PIPING SUPPORT                                             6                 VT-3    F-A BB-01-H001     BB-05-01         PIPING SUPPORT                                              14               VT-3    F-A HB-24-R015     BB-06-0 1        PIPING SUPPORT                                             2                 VT-3    F-A      FlI.10 CRDMPL-SUP-3   ISI-CRDMPL       CRDM Upper Seismfic Support                                                  VT-3    F-A      FI.40 CRDMPL-SUP-4   ISI-CRDMPL       CRDM Upper Seismic Support                                                   VT-3    F-A      Fl1.40 EBB01A-02 231  M-717-00002      SG A LOWER COLUMN SUPPORT                                                    VT-3    F-A      F 1.40 EBBO1A-06 231  M-71 7-00009     SG A LOWER LATERAL SUPPORT                                                   VT-3    F-A      FI.40 EBBO1A-07 231  M-71 7-00009     SG A LOWER LATERAL SUPPORT                                                   VT-3    F-A      F 1.40 EBB01A-08 231  M-717-00010      SG A UPPER LATERAL SUPPORT                                                   VT-3    F-A      Fl1.40 EBB01A-UP-2    M-717-00015      SG A UPPER LATERAL SUPPORT                                                   VT-3    F-A      Fl1.40 EBB01A=UP-3    M-717-00015      SG A UPPER LATERAL SUPPORT                                                   VT-3    F-A      F 1.40 PBB01 A-SUP-2  ISI-PUMPS        RCP A TIE ROD SUPPORT                                                        VT-3    F-A      F1.40 PBB01A-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      F 1.40                    I4R-02 RBB-01-03      ISI-RBB01 SHT. 1 RV SUPPORT PAD 3                                                             VT-3    F-A      F 1.40                    I4R-02 BB-04-FW302    BB-01-04 SHT. I  4" ELBOW TO 4" PIPE                                                           UT     R-A      RI.II      114             12, 13 4       0.53 1 BB-02-FW301    BB-02-02         6' 180 DEGREE RET. TO 6" FLANGE (VALVE 8010A)              6       0.7 19     UT     R-A      RI.11      117             12, 13 BB-01-F002     BB-05-01         14" PIPE TO 14" PIPE                                        14      1.25      UT     R-A      RI ll      130             12, 13 BB-01-S101-13  BB-01-01         3" NOZZLE TO 3" X 1.5" REDUCER                             3       0.438      UIT    R-A      RI.I11     112              12, 13 BB-01-$201-15  BB-02-01         3" NOZZLE TO 3" X 1.5" REDUCER                             3       0.438      UT     R-A      RI lI      112             12, 13 BB-01-F 108    BB-01-01         31" ELBOW TO 31" PIPE                                      31       2.88      UT     R-A      R1.20  SAP-01, 105             12 WCRE-30                                                  4.1.4 Reactor Coolant System (BB)                                                         Revision 0 Page 19 of 4.6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2 IPeriod 2 Examinations
[System: B88 Relief Request or Component Name       Drawing Number    Component Description                                       Size  Thickness     NDE Method Category item   Cal Block           Notes BB-0 1-S 105-04      BB-01-01          31" PIPE TO 31" ELBOW                                       31        2.88          UT     R-A      R1.20  SAP-01, 105              12 BB-04-S01 5-B        BB-01-04 SIT. 2   4" ELBOW TO 4" PIPE                                         4         0.531         UT     R-A      R1.20      114                  12 BB-04-S01 5-D        BB-01-04 SIT. 2   4" PIPE TO 4" ELBOW                                         4         0.531         UT     R-A      R1.20      114                  12 BB-04-S0 15-E        BB-01-04 SHT. 2   4" ELBOW TO 4" PIPE4                                                  0.531         UT     R-A      R1.20      114                  12 BB-02-S001-D         BB-02-02          6" ELBOW TO 6" PIPE6                                                  0.719         UT     R-A      R1.20       117                 12 BB-02-FW304          BB-02-02          6" ELBOW TO 6" PIPE6                                                  0.719         UT     R-A      R1.20      117                  12 BB-01-F103           BB-01-01          SAFE END TO 29" I.D. PIPE                                   29          2.5         UT     R-A      R1.20  SAP-01, 105              12 BB-01-F203           BB-02-01          SAFE END TO 29" ID PIPE                                     29          2.5         UT     R-A      R1.20  SAP-07, 106              12 BB-01-F303           BB-03-01          SAFE END TO 29" ID PIPE                                     29          2.5         UT     R-A      R1.20  SAP-07, 106              12 TBB03-MW7086-WOL-DM  ISI-TBB03 SHT. 1  SAFETY NOZZLE A TO SAFE-END WELD OVERLAY                    6    See I, Note 21     UT     N-770-1  DM-P  See I, Note 20 BB-02-MW7086-WOL-SS  BB-02-02          SAFETY NOZZLE A SAFE-END TO PIPE WELD OVERLAY               6    See I, Note 21     UT     I3R-05   SS-R  See I, Note 20 CH-107-101          ISI-RBB0 1 SHT. I RV  VENT PENETRATION                                                                 VE    N-729-I  B4.10                           22 CH-1 12-201         ISI-RBB0 1 SIHT. I RV  CRDM PENETRATION 1                                                              VE     N-729-1  B4.10                           22 CH-1 12-202-2       ISI-RBB01 SHT. I RV  CRDM PENETRATION 2                                                              VE     N-729-1  B4.10                           22 CH-1 12-202-3       ISI-RBBO1 SHT. 1 RV  CRDM PENETRATION 3                                                              VE     N-729-1  B4.10                           22 CH- 112-202-4       ISI-RBB0 1 SHT. I RV  CRDM PENETRATION 4                                                              VE     N-729-1I B4.10                        22 CH-1 12-202-5       ISI-RBB01 SHT. 1 RV  CRDM PENETRATIONS5                                                              VE     N-729-1  B4.10                        22 CH-1 12-203-6       ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 6                                                              VE     N-729- I B4.10                        22 CH-1 12-203-7       ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 7                                                              VE     N-729-1  B4.10                        22 CH-1 12-203-8       ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 8                                                              VE     N-729-1  B4.10                        22 Cl-1-i12-203-9      ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 9                                                              VE     N-729-1  84.10                        22 CH-I112-204-10      ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 10                                                             VE     N-729-1  B4.10                        22 CH-1 12-204-11      ISI-RBB01 SI-T. I RV  CRDM PENETRATION 11                                                             VE     N-729-1  B4.10                        22 CH-1 12-204-12      ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 12                                                             VE     N-729-1  84.10                        22 CH-1 12-204-13      ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 13                                                             VE     N-729-1  B4.10                        22 CH-1 12-205-14      ISI-RBB0I SI-T. I RV  CRDM PENETRATION 14                                                             VE     N-729-1  84.10                        22 CH-1 12-205-15      ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 15                                                             VE     N-729-1  B4.10                        22 CH-1 12-205-16      ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 16                                                             VE     N-729-1  B4.10                        22 CH-1 12-205-17      ISI-RBB01 SIT. 1 RV  CRDM PENETRATION 17                                                             VE     N-729-1  84.10                        22 Cl-I-i12-206-18     ISI-RBB01 SHT. 1 RV  CRDM PENETRATION 18                                                             VE     N-729-1  84.10                        22 CH-1 12-206-19      ISI-RBB01 SI-T. 1 RV  CRI7M PENETRATION 19                                                            VE     N-729-1  B4.10                        22 WCRE-30                                                        4.1.4 Reactor Coolant System (BB)                                                                 Revision 0 Page 20 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2
[Period 2 Examinations SSystem: BB Relief Request or Component Name    Drawing Number    Component Description                                    Size Thickness NDE Method Category Item   Cal Block          Notes CE-I! 12-206-20  ISI-RIBB01 SET. I  RV CRDM PENETRATION 20                                                      VE     N-729-1  B4.10                      22 CE-i112-206-21   ISI-RBB01 SHT. 1   RV CRDM PENETRATION 21                                                      VE     N-729-1  B4.10                      22 CH-1 12-207-22   ISI-RIBB01 SET. 1  RV CRDM PENETRATION 22                                                      VE     N-729-1  B4.10                      22 CE-i112-207-23   ISI-RIBB01 SHT. 1  RV CRDM PENETRATION 23                                                      VE     N-729-1  B4.10                      22 CE-I 12-207-24   ISI-RBB01I SHT. I  RV CRDM PENETRATION 24                                                      VE     N-729-1  B4.l0                      22 CH-1 12-207-25   ISI-RIBB01 SHT. 1  RV CRDM PENETRATION 25                                                      VE     N-729-1  B4.10                      22 CE-I112-207-26   ISI-RIBB01 SHIT. 1 RV CRDM PENETRATION 26                                                      VE     N-729-1I B4.10                      22 CH-1 12-207-27   ISI-RBB01 SET. I   RV CRDM PENETRATION 27                                                      VE     N-729-1  B4.10                      22 CH- 112-207-28   ISI-RBB01 SET. 1   RV CRDM PENETRATION 28                                                      VE     N-729-1  B4.10                      22 CH-1 12-207-29   ISI-RBBO1 SHT. 1   RV CRDM PENETRATION 29                                                      VE     N-729-1  B4.10                      22 CH-1 12-208-30   ISI-RIBB01 SHIT. 1 RV CRDM PENETRATION 30                                                      VE     N-729-1  B4.10                      22 CH- 112-208-31   ISI-RBB01 SHT. 1   RV CRDM PENETRATION 31l                                                     VE     N-729-1  B4.10                      22 CH-1 12-208-32   ISI-RBB01 SET. 1   RV CRDM PENETRATION 32                                                      VE     N-729-I  B4.10                      22 CH-1 12-208-33   ISI-RBB01 SET. I   RV CRDM PENETRATION 33                                                      VE     N-729-1  B4.10                      22 CH-1 12-208-34   ISI-RBB01 SHT. 1   RV CRDM PENETRATION 34                                                      VE     N-729-1  B4. 10                     22 CH-I 12-208-35   ISI-RIBB01 SET. I  RV CRDM PENETRATION 35                                                      VE     N-729-1  B4.10                      22 CE-i112-208-36   ISI-RIBB01 SELT. 1 RV CRDM PENETRATION 36                                                      VE     N-729-1  B4.10                      22 CU-I112-208-37   ISI-RBB01 SET. 1   RV CRDM PENETRATION 37                                                      VE     N-729-1  B4.10                      22 Cl-I-i12-209-3 8 ISI-RBB01 SET. 1   RV CRDM PENETRATION 38                                                      VE     N-729-1  B4.10                      22 CH-1 12-209-39   ISI-RBB01 SET. I   RV CRDM PENETRATION 39                                                      VE     N-729-I  B4.10                      22 Cl--i12-209-40   ISI-RBB01 SET. 1   RV CRDM PENETRATION 40                                                      VE     N-729- I B4.10                      22 CH-1 12-209-41   ISI-RBB01 SET. 1   RV CRDM PENETRATION 41                                                      VE     N-729-1  B4.10                      22 CE-I112-210-42   ISI-RIBB01 SET. 1  RV CRDM PENETRATION 42                                                      VE     N-729-1  B4.10                      22 CU-I112-210-43   ISI-RIBB01 SEIT. 1 RV CRDM PENETRATION 43                                                      VE     N-729-1  B4. 10                     22 CH-1 12-210-44   ISI-RBB0 1 SET. 1  RV CRDM PENETRATION 44                                                      VE     N-729-1  B4.10                      22 CE-i112-210-45   ISI-RBB01 SET. 1   RV CRDM PENETRATION 45                                                      VE     N-729-i  B4.10                      22 CH-112-21I0.46   ISI-RBB01 SEIT. 1  RV CRDM PENETRATION 46                                                      VE     N-729-1  B4.10                      22 CH-1 12-210-47   ISI-RBB01 SELT. 1  RV CRDM PENETRATION 47                                                      VE     N-729-1  B4. 10                     22 CE-112-210.48    ISI-RBB01 SET. 1   RV CRDM PENETRATION 48                                                      VE     N-729-1  B4.10                      22 CH-1 12-210-49   ISI-RIBB01 SET. I  RV CRDM PENETRATION 49                                                      VE     N-729-1  B4.10                      22 CH-1 12-211-50   ISI-RBB01 SET. I   RV CRDM PENETRATION 50                                                      VE     N-729-1  B4.10                      22 CH-112-211-51    ISI-RBB01 SEIT. I  RV CRDM PENETRATION 51                                                      VE     N-729-1  B4. 10                     22 CH-1 12-211-52   ISI-RBB01 SET. 1   RV CRDM PENETRATION 52                                                      VE     N-729-l  B4.10                      22 CH-1 12-211-53   ISI-R.BB01 SET. I  RV CRDM PENETRATION 53                                                      VE     N-729-1  B4.10                      22 CH-1 12-212-54   IS1-RiBB01 SET. 1  RV CRDM PENETRATION 54                                                      VE     N-729-1  B4.10                      22 CE-I112-212-55   ISI-RIBB01 SELT. 1 RV CRDM PENETRATION 55                                                      VE     N-729-1  B4.10                      22 CH-1 12-212-56   ISI-RBB01 SET. 1   RV CRDM PENETRATION 56                                                      VE     N-729-1  B4.10                      22 CH-1 12-212-57   ISI-RBB01 SET. 1   RV CRDM PENETRATION 57                                                      VE     N-729-1  B4.10                      22 CH-1 12-212-58   1SI-RBB01 SET. 1   RV CRDM PENETRATION 58                                                      VE     N-729-1  B4.10                      22 CH-1 12-212-59   ISI-RBB01 SET. 1   RV CRDM PENETRATION 59                                                      VE     N-729-1  B4.10                      22 CE-I112-212-60   ISI-RBB0 1 SELT. 1 RV CRDM PENETRATION 60                                                      VE     N-729-1  B4.10                      22 CH-112-212-61    ISI-RBB01 SET. 1   RV CRDM PENETRATION 61                                                      VE     N-729-1  B4.10                      22 WCRE-30                                                   4.1.4 Reactor Coolant System (BB)                                                          Revision 0 Page 21 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2 Isystem: BBl Relief Request or Component Name   Drawing Number     Component Description                                 Size Thickness NDE Method Category Item   Cal Block         Notes CR-i112-213-62  ISI-RBB01  SRT. I  RV CRDM PENETRATION    62                                                VE     N-729-1  B4. 10                     22 CH-1 12-213-63  ISI-RBB01  SHT. 1  RV CRDM PENETRATION    63                                                VE     N-729-I  84.10                      22 CR-i112-213-64  ISI-RBB01  SIHT. 1  RV CRDM PENETRATION    64                                                VE     N-729-1  84.10                      22 CH-I112-213-65  ISI-RBB01  SRT. 1  RV CRDM PENETRATION    65                                                VE     N-729-1I 84.10                      22 CH-1 12-214-66  ISI-RBB01  SRT. 1  RV CRDM PENETRATION    66                                                VE     N-729-1  B4.10                      22 CR-1 12-214-67  ISI-RBB01  SHT. I  RV CRDM PENETRATION    67                                                VE     N-729-I  B4.10                      22 CH-1 12-214-68  ISI-RBBO01 SHT. 1  RV CRDM PENETRATION    68                                                VE     N-729-1  B4.10                      22 CR-i112-214-69  ISI-RBB01  SHT. I  RV CRDM PENETRATION    69                                                VE     N-729-1  84.10                      22 CH-1 12-214-70  ISI-RBB01  SILT  I  RV CRDM PENETRATION    70                                                VE     N-729-1  B4. 10                     22 CH-1 12-214-71  ISI-RBB01  SUT. I  RV CRDM PENETRATION    71                                                VE     N-729-1  B4.10                      22 CR-i112-214-72  ISI-RBB01  SHT. 1  RV CRDM PENETRATION    72                                                VE     N-729-1  84.10                      22 CH-1 12-214-73  ISI-RBB01  SRT. 1  RV CRDM PENETRATION    73                                                VE     N-729-I  B4.10                      22 CH-1 12-215-74  ISI-RBB01  SHT. 1  RV CRDM PENETRATION    74                                                VE     N-729-1  84.10                      22 CH-1 12-215-75  ISI-R8B01  SRLT. 1  RV CRDM PENETRATION    75                                                VE     N-729-1  B4.10                      22 CH-1 12-215-76  ISI-RBB01  SRT. 1  RV CRDM PENETRATION    76                                                VE     N-729-1  B4.10                      22 Cl-I1I12-215-77 ISI-RBB01  SRT. 1  RV CRDM PENETRATION    77                                                VE     N-729-1  84.10                      22 CR-I112-215-78  ISI-RBB01  SHT. 1  RV CRDM PENETRATION    78                                                VE     N-729-1  B4.10                      22 CH-107-I01      ISI-RBB01  SHT. 1  RV VENT PENETRATION                                   NA        NA      UT/ET N-729-I  B4.20                      22 CR-112-201      ISI-RBB01  SRT. 1  RV CRDM PENETRATION    1                              NA        NA      UT/ET   N-729-1  84.20                      22 CR-i 112-202-2  ISI-RBB01  SRT. 1  RV CRDM PENETRATION    2                              NA        NA      UT/ET   N-729-1  B4.20                      22 CH- 112-202-3   ISI-RBB01  SHT. I  RV CRDM PENETRATION    3                              NA        NA      UT/ET   N-729-1  84.20                      22 CR-I112-202-4   ISI-RBB01  SHiT. 1  RV CRDM PENETRATION    4                              NA        NA      UT/ET   N-729-1  84.20                      22 CH-1 12-202-5   ISI-RBB01  SRT. 1  RV CRDM PENETRATION    5                              NA        NA      UT/ET   N-729-1  B4.20                      22 Cl-i- 112-203-6 ISI-RBB01  SHT. 1  RV CRDM PENETRATION    6                              NA        NA      UT/ET   N-729-1  B4.20                      22 CR-i112-203-7   ISI-RBB01  SILT. I RV CRDM PENETRATION    7                              NA        NA      UT/ET   N-729-1  84.20                      22 CR-i 112-203-8  ISI-RBB01  SilT. 1  RV CRDM PENETRATION    8                              NA        NA      UT/ET   N-729-I  B4.20                      22 CH-1 12-203-9   ISI-RBB01  SRT. 1  RV CRDM PENETRATION    9                              NA        NA      UT/ET   N-729-1  B4.20                      22 CH-i112-204-10  ISI-RBB801 SRIT. I  RV CRDM PENETRATION     10                            NA        NA      UT/ET   N-729-1  B4.20                      22 CR-i112-204-11  ISI-RIBB01 SHiT. 1  RV CRDM PENETRATION     11                            NA        NA      UT/ET   N-729-1  84.20                      22 CH-1 12-204-12  ISI-RBB01  SRT. 1  RV CRDM PENETRATION     12                            NA        NA      UT/ET   N-729-1  B4.20                      22 CH-I112-204-13  ISI-RBB01  SET. 1  RV CRDM PENETRATION     13                            NA         NA     UT/ET   N-729-I  84.20                      22 CR-1 12-205-14  ISI-RBB01  SHT. 1  RV CRDM PENETRATION     14                            NA         NA     UT/ET   N-729-I  84.20                      22 CR-i112-205-15  ISI-RBB01  SRT. I  RV CRDM PENETRATION     15                            NA         NA     UT/ET   N-729-1  84.20                      22 CR-i112-205-16  ISI-R.BB01 SRT. 1  RV CRDM PENETRATION     16                            NA         NA     UT/ET   N-729-1  84.20                      22 CR-I112-205-17  ISI-RBB01  SHT. 1  RV CRDM PENETRATION     17                            NA         NA     UT/ET   N-729-1  84.20                      22 CH-1 12-206-18  ISI-RBB01  SET. 1  RV CRDM PENETRATION     18                            NA         NA     UT/ET   N-729-1  84.20                      22 CR-I112-206-19  ISI-RBB01  SRT. 1  RN CRDM PENETRATION     19                            NA         NA     UT/ET   N-729-1  84.20                      22 CH- 112-206-20  ISI-RBB01  SRT. 1  RV CRDM PENETRATION    20                             NA         NA     UT/ET   N-729-1  84.20                      22 CR-i112-206-2 1 ISI-RBB01  SRT. 1  RV CRDM PENETRATION    21                             NA         NA     UT/ET   N-729-1  84.20                      22 CR-i112-207-22  ISI-RBB01  SHT. 1 RV CRDM PENETRATION    22                              NA        NA     UT/ET   N-729-1  84.20                      22 CR-i112-207-23  ISI-RBB0!  SRT. 1 RV CRDM PENETRATION    23                              NA        NA     UT/ET   N-729-1  84.20                      22 WCRE-30                                                      1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 22 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BB-2
[Period 2 Examinations ISystem: 8B8 Relief Request or Component Name    Drawing Number    Component Description                                    Size Thickness NDE Method Category Item  Cal Block         Notes CR-i112-207-24   1S1-REDO01 SRT. 1  RV CRDM PENETRATION 24                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-I112-207-25   1SI-RBBO01 SHT. 1  RV CRDM PENETRATION 25                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-I112-207-26   ISI-RB801I SKIT. I RV CROM PENETRATION 26                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR- 112-207-2?   ISI-RBB01 SHT. 1   RV CRDM PENETRATION 27                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i112-207-28   1SI-RBB0 1 SHT. 1  RV CRDM PENETRATION 28                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-I112-207-29   ISI-RBB01 SHT. 1   RV CRDM PENETRATION 29                                   NA        NA     UT/FT    N-729-1  84.20                    22 CR-i112-208-30   ISI-RBB0 1 SRT. 1  RV CRDM PENETRATION 30                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i112-208-3 1  151-REDO01 SRT. I  RV CRDM PENETRATION 31                                   NA        NA     UT/ET    N-729-I  84.20                    22 CR-i112-208-32   1SI-RBB01 SLRT. 1  RV CRDM PENETRATION 32                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i 112-208-33  1S1-RBB0 I SHT. 1  RV CRDM PENETRATION 33                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i1!2-208-34   ISI-RBB01 SHT. I   RY CRDM PENETRATION 34                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i 112-208-35  1SI-RBB0 1 SRT. 1  RV CRDM PENETRATION 35                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR-i112-208-36   1SI-RBB01I SHT!. I RV CRDM PENETRATION 36                                   NA        NA     UT/FT    N-729-I  84.20                    22 CR-i112-208-37   1SI-R8B01 SHT. 1   RV CRDM PENETRATION 37                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i 112-209-38  lSi-RBB01 SILT. 1  RV CRDM PENETRATION 38                                   NA        NA     UT/FT    N-729-I  84.20                    22 CR-i112-209-39   ISI-RBB0 1 SHT. 1  RV CRDM PENETRATION 39                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR- 112-209-40   1SI-RBB0 1 SHT. 1  RV CRDM PENETRATION 40                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i112-209-41   ISI-RBB01 SHT. 1   RV CRDM PENETRATION 41                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i112-210-42  1SI-RBB01 SRT. 1    RV CRDM PENETRATION 42                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i112-210-43   151-REDO01 SRT. 1  RV CRDM PENETRATION 43                                   NA        NA     UT/FT    N-729-1  84.20                    22 CH-i112-210-44  ISI-RBB01 SRT. 1    RV CRDM PENETRATION 44                                  NA         NA     UT/ET    N-729-1  84.20                    22 CH-112-210-45   IST-REDO0I SRT. 1   RV CRDM PENETRATION 45                                  NA         NA     UT/ET    N-729-I  84.20                    22 CR-i112-210-46  ISI-RiBB01 SRT. 1   RV CRDM PENETRATION 46                                  NA         NA     UT/FT    N-729-i  84.20                    22 CR-i112-210-47  1SI-REBO01 SRT. 1   RV CRDM PENETRATION 47                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR-i112-210-48   ISI-RBBO01 SRT. 1  RV CREM PENETRATION 48                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i112-210-49   IS1-RBBO01 SLIT. 1 RV CRDM PENETRATION 49                                  NA         NA     UTT/ET   N-729-1  84.20                    22 CR-i112-211-50   1SI-REDO0I SLRT. 1 RY CRDM PENETRATION 50                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR-112-21il-5i   1SI-REDO0I SRT. I  RV CRDM PENETRATION 51                                   NA        NA     UT/FT    N-729-1  84.20                    22 CR-i112-211-52   ISI-RBBO01 SRT. 1  RV CRDM PENETRATION 52                                   NA        NA     UT/FT    N-729-1  84.20                    22 CR-I112-211-53   1S1-REDO01 SRT. 1  RV CRDM PENETRATION 53                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR-i112-212-54  ISI-RBB01 SHT. 1    RV CRDM PENETRATION 54                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i112-212-55  ISI-REDOI SIIT. 1   RV CRDM PENETRATION 55                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR-i112-212-56   ISI-REDB0I SHT. 1  RV CRDM PENETRATION 56                                  NA         NA     UT/ET    N-729-1  84.20                    22 CR-i112-212-57   1S1-REDO01 SRT. 1  RV CRDM PENETRATIONS?7                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR- 112-212-58   ISI-RBB01 SHIT. I  RV CRDM PENETRATION 58                                   NA        NA     UT/ET    N-729-i  84.20                    22 CR-I112-212-59   ISI-RBB01 SI-T. 1  RV CRDM PENETRATION 59                                  NA         NA     UT/FT    N-729-i  84.20                    22 CR-i1i2-212-60   ISI-RBDOI SIRT. 1  RV CRDM PENETRATION 60                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i112-212-61   ISI-RBBO0I SHT. 1  RV CRDM PENETRATION 61                                   NA        NA     UT/ET    N-729-1  84.20                    22 CR-i112-21.3-62  ISI-RBBO01 SHT. 1  RV CRDM PENETRATION 62                                   NA        NA     UT/FT    N-729- I 84.20                    22 CR-i112-213-63   ISI-REBB0 SHIT. I  RV CRDM PENETRATION 63                                  NA         NA     UT/FT    N-729- I 84.20                    22 CR-i112-213-64   ISI-REDO01 SRT. 1  RV CRDM PENETRATION 64                                  NA         NA     UT/FT    N-729-1  84.20                    22 CR-I112-213-65   ISI-RBD01 SHIT. 1  RV CRDM PENETRATION 65                                  NA         NA     UT/ET    N-729-1  84.20                    22 WCRE-30                                                    1.4 Reactor Coolant System (BB)                                                        Revision 0 Page 23 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2
[Peiod 2Examinations I ISystem: BBI Relief Request or Component Name   Drawing Number     Component Description                                     Size Thickness NDE Method Category Item     Cal Block         Notes CH-1 12-214-66  ISI-RBB01   SI-T. 1 RV CRDM  PENETRATION     66                               NA        NA      UJT/ET  N-729-I  B4.20                        22 CH-1 12-214-67  ISI-RBB01   SHT. I RV CRDM  PENETRATION     67                               NA         NA     UT/ET   N-729-1  B4.20                        22 CH-1 12-214-68  ISI-RBB01   SHT. I RV CRDM  PENETRATION     68                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-214-69  ISI-RBB01   SI-T. I RV CRDM  PENETRATION     69                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-214-70  ISI-RBB01   SHT. 1 RV CRDM  PENETRATION     70                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-214-71  ISI-RBB01   SHlT. 1 RV CRDM  PENETRATION     71                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-214-72  ISI-RBB01   SHT. 1 RV CRDM  PENETRATION     72                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-214-73  ISI-RBB01   SHT. 1 RV CRDM  PENETRATION     73                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-215-74  ISI-RBB01   SHT. 1 RV CRDM  PENETRATION     74                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-112-215-75   1SI-RBB01  SHIT. I RV CRDM  PENETRATION     75                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-112-215-76   ISI-RBB01  SHT. 1 RV CRDM  PENETRATION     76                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-215-77  ISI-RBB01  SI-T. 1 RV CRDM  PENETRATION     77                               NA        NA      UT/ET   N-729-1  B4.20                        22 CH-1 12-215-78  ISI-RBB01   SHT. 1 RV CRDM  PENETRATION      78                              NA        NA      UT/ET   N-729-1  B4.20                        22 RV-201-151-1    ISI-RBB01 SI-IT. 1                                                                               VE    N-722-1  B 15.80                      23 RV BMI PENETRATION    I RV-201-151-2    ISI-RBB01 SHT. 1 RV BMI PENETRATION    2                                                       VE    N-722-1  B 15.80                      23 RV-201-151-3    ISI-RBB01 SHT. 1 RV BMI PENETRATION    3                                                      VE     N-722-1  B 15.80                      23 RV-201-I151-4   ISI-RBB01 SHT. 1 RV BMI PENETRATION    4                                                       VE    N-722-1  B15.80                       23 RV-201-151-5    ISI-RBB01 SHT. 1 RV BMI PENETRATION    5                                                      VE     N-722-1  B1 5.80                      23 RV-201-151-6    ISI-RBB01 SI-T. 1 RV BMI PENETRATION    6                                                      VE     N-722-1  B 15.80                      23 RV-201 - 151-7  ISI-RBB01 SHT. I RV BMI PENETRATION    7                                                       VE    N-722-I  B 15.80                      23 RV-201-151-8    ISI-RBB01 SI-T. 1 RV BMI PENETRATION    8                                                       VE    N-722-I  B 15.80                      23 RV-201-151-9    ISI-RBB01 SI-IT. I RV BMI PENETRATION    9                                                      VE     N-722-1  B 15.80                      23 RV-201-151-10   ISI-RBB01 SHT. I RV BMI PENETRATION    10                                                     VE     N-722-1  B 15.80                      23 R.V-20 1-151-11 ISI-RBB01 SHIT. 1 RV BMI PENETRATION    11                                                     VE     N-722-1  B 15.80                      23 RV-201-151-12   ISI-R.BB01 SHlT. 1 RV BMI PENETRATION    12                                                     VE     N-722-1  B 15.80                      23 RV-201-151-13   ISI-RBB01 SHT. 1 RV BMI PENETRATION    13                                                     VE     N-722-1  B 15.80                      23 RV-201-151-14   ISI-RBB01 SHT. 1 RV BMI PENETRATION    14                                                      VE    N-722-1  B 15.80                      23 RV-201-1 51-15  ISI-R.BB0 1 SI-T. 1 RV BMI PENETRATION    15                                                      VE    N-722-1  B 15.80                      23 RV-201-1 51-16  ISI-RBB01 SHT. I RV BMI PENETRATION     16                                                     VE    N-722-1  B15.80                       23 RV-201-1 51-17  ISI-RBB01 SHT. 1 RV BMI PENETRATION    17                                                      VE    N-722-1  B 15.80                      23 RV-20 1-151-18  ISI-RBB01 SHT. I RV BMI PENETRATION    18                                                      VE    N-722-1  B 15.80                      23 RV-201-1 51-19  1SI-RBB01 SHT. 1 RV BMI PENETRATION    19                                                      VE    N-722-1  B 15 .80                     23 RV-201I-151-20  ISI-RBB01 SI-T. I RV BMI PENETRATION    20                                                      VE    N-722-1  B 15.80                      23 RV-201 - 151-21 ISI-RBB01 SI-T. 1 RV BMI PENETRATION    21                                                      VE    N-722-1  B 15.80                      23 RV-201-151-22   ISI-RBB01 SHT. I RV BMI PENETRATION    22                                                      VE    N-722-1  B 15.80                      23 RV-201-151-23   ISI-RBB01 SHT. I RV BMI PENETRATION    23                                                      VE    N-722-1  B 15.80                      23 RV-201-151-24   ISI-RBB01 SHT. I RV BMI PENETRATION    24                                                      VE    N-722-1  B15.80                       23 RV-201-151-25   ISI-RBB01 SHT. I RV BMI PENETRATION    25                                                      VE    N-722-1  B 15.80                      23 RV-201-151-26   ISI-RBB01 SHT. 1 RV BMI PENETRATION    26                                                      VE    N-722-1  B15.80                       23 RV-201-151-27   ISI-RBB01 SHT. I RV BMI PENETRATION    27                                                      VE    N-722-1  B 15.80                      23 RV-201-151-28   ISI-RBB01 SHT. 1 RV BMI PENETRATION    28                                                      VE    N-722-1  B 15.80                      23 WCRE-30                                                      4.1.4 Reactor Coolant System (BB)                                                         Revision 0 Page 24 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2 IPeriod 2 Examinations
[System: BB Relief Request or Component Name    Drawing Number    Component Description                                      Size Thickness NDE Method Category Item     Cal Block          Notes RV-201-151-29    ISI-RBBOI SHlT. I RV BMI PENETRATION 29                                                         VE     N-722-1  BI15.80                      23 RV-201-151-30    ISI-RBB01 SHT. 1 RV BMI PENETRATION 30                                                         VE     N-722-1  B1 5.80                      23 RV-201-151-31   ISI-RBB01 SHT. 1 RV BMI PENETRATION 31                                                         YE     N-722-1  B 15.80                      23 RV-201-I151-32  ISI-RBB01 SHlT. 1 RV BMI PENETRATION 32                                                         VE     N-722-1  B 15.80                      23 RV-201-151-33   ISI-RBBO1 SHlT. 1 RV BMI PENETRATION 33                                                         VE     N-722-1  B 15.80                      23 RV-201-151-34   ISI-RBB01 SI-T. 1 RV BMI PENETRATION 34                                                         VE     N-722-I  B 15.80                      23 RV-201-1 51-35  ISI-RBB01 SHlT. 1 RV BMI PENETRATION 35                                                         VE     N-722-I  B 15.80                      23 RV-201-151-36   ISI-RBB01 SI-T. I RV BMI PENETRATION 36                                                         VE     N-722-lI B 15.80                      23 RV-201-151-37   ISI-RBB01 SHlT. 1 RY BMI PENETRATION 37                                                         VE     N-722-1  B15.80                       23 RV-201-151-38   ISI-RBB01 SilT. 1 RY BMI PENETRATION 38                                                         VE     N-722-1  B 15.80                      23 RV-201 -151-39  ISI-REBB1 SHlT. 1 RV BMI PENETRATION 39                                                         VE     N-722-1  B 15.80                      23 RV-201-151-40   ISI-RBB01 SilT. 1 RV BMI PENETRATION 40                                                         VE     N-722-1  B 15.80                      23 RV-201-151-41   ISI-RBB01 SHT. 1 RV BMI PENETRATION 41                                                         VE     N-722-1  B 15.80                      23 RV-201 -151-42  ISI-RBB01 SHlT. 1 RV BMI PENETRATION 42                                                         VE     N-722-1  B 15.80                      23 RV-201-151-43   ISI-RBB01 SilT. I RY BMI PENETRATION 43                                                         VE     N-722-1  B 15.80,                     23 RV-201-151-44   ISI-RBB0I SHT. I RV BMI PENETRATION 44                                                         VE     N-722-1  B 15.80                      23 RV-201 -15 1-45 ISI-RBB01 SHlT. 1 RV BMI PENETRATION 45                                                         VE     N-722-1  B 15.80                      23 RV-201-151--46  ISI-RBB01 SHT. 1 RV BMI PENETRATION 46                                                         VE     N-722-1  B 15.80                      23 RV-201-1 51--47 ISI-RBB01 SHlT. 1 RY BMI PENETRATION 47                                                         VE     N-722-1  B 15.80                      23 RV-201-151-48   ISI-RBB01 SHlT. 1 RV BMI PENETRATION 48                                                         VE     N-722-1  B 15.80                      23 RV-201-151-49   ISI-RBB01 SHlT. 1 RV BMI PENETRATION 49                                                         VE     N-722-I  B 15.80                      23 RV-201-151-50   ISI-RBB01 SHT. 1 RV BMI PENETRATION 50                                                         VE     N-722-I  B 15.80                      23 RV-201-151-51   ISI-RBBO1 SHT. 1 RV BMI PENETRATION 51                                                         VE     N-722-1  B 15.80                      23 RV-201-151-52   ISI-RBB01 SHT. 1 RV BMI PENETRATION 52                                                        YE      N-722-1  B 15.80                      23 RY-201-151-53   ISI-RBB01 SHT. 1 RV BMI PENETRATION 53                                                        YE      N-722-1  B15.80                       23 RV-20 I-151-54  ISI-RBB01 SHT. I RV BMI PENETRATION 54                                                        YE      N-722-1  B 15.80                      23 RV-201-151-55   ISI-RBB01 SilT. 1 RV BMI PENETRATION 55                                                         VE     N-722-1  B 15.80                      23 RV-201-151-56   ISI-RBB0 1 SilT. 1 RV BMI PENETRATION 56                                                         VE     N-722-1  B 15.80                      23 RV-201-151-57   ISI-RBBO1 SHT. 1 RY BMI PENETRATION 57                                                         VE     N-722-1I B 15.80                      23 RV-201 -I51-58  ISI-RBB01 SHT. 1 RY BMI PENETRATION 58                                                         VE     N-722-1  BI15.80                      23 RV-30 1-121-A    ISI-RBB01 SHT. 1 LOOP #1 RPY OUTLET    NOZZLE  TO SAFE-END                 29       2.92       VE     N-722-1  B 15.90                      24 RY-301 -121-B    ISI-RBB01 SHT. I LOOP #2 RPY OUTLET    NOZZLE  TO SAFE-END                 29       2.92       VE     N-722-1  B15.90                       24 RV-30 1-12 1-C   ISI-RBB0 1 SHlT. 1 LOOP #3 RPV OUTLET    NOZZLE  TO SAFE-END                 29       2.92       VE     N-722-1  B 15.90                      24 RV-301-121-D     ISI-RBB01 SHLT. I LOOP #4 RPY OUTLET    NOZZLE  TO SAFE-END                 29       2.92       VE     N-722-1  B 15.90                      24 RV-302-12 1-A                                                                                 27.5     2.79      YE      N-722-1  B15.95                       25 ISI-RBB01 SilT. 1  SAFE-END TO LOOP #1 RPV INLET NOZZLE RV-302-121 -D    IS1-RBB01 SHlT. 1  SAFE-END TO LOOP #4 RPV INLET NOZZLE                      27.5     2.79       VE     N-722-1  B15.95                       25 WCRE-30                                                     4.1.4 Reactor Coolant System (BB)                                                            Revision 0 Page 25 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-2
[Period 2 Examinations
[System: BB]
Relief Request or Component Name    Drawing Number     Component Description                                     Size     Thickness NDE Method Category Item     Cal Block         Notes BB-0 I-S 102-TW-T BB-01-01           LOOP  #1 NARROW   RANGE  THERMO WELL,   TOP                                      VE     N-722-I  B 15.200                     26 BB-01 -S 102-TW-I BB-01-01           LOOP  #1 NARROW   RANGE  TIHERMO WELL,  INSIDE                                   VE     N-722-1  B 15.200                     26 BB-0 1-S 102-TW-O BB-01-01           LOOP  #1INARROW   RANGE  THERMO WELL,   OUTSIDE                                  VE     N-722-1  B15.200                      26 BB-01 -S202-TW-T  BB-02-01           LOOP  #2 NARROW   RANGE  TIHERMO WELL,  TOP                                      VE     N-722-1  B15.200                      26 BB-01 -S202-TW-I  BB-02-01           LOOP  #2 NARROW   RANGE  THERMO WELL,   INSIDE                                   VE     N-722-1  B 15.200                     26 BB-0 1-S202-TW-O  BB-02-01           LOOP  #2 NARROW   RANGE  THERMO WELL,   OUTSIDE                                  VE     N-722-1  B 15.200                     26 BB-01l-S302-TW-T  BB-03-01           LOOP  #3 NARROW   RANGE  THERMO WELL,   TOP                                      VE     N-722-1  B 15.200                     26 BB-0 1-S302-TW-I  BB-03-01           LOOP  #3 NARROW   RANGE  THERMOWELL,    INSIDE                                   YE     N-722-1  B 15.200                     26 BB-01-$302-TW-O   BB-03-01           LOOP  #3 NARROW   RANGE  THERMOWELL,    OUTSIDE                                  YE     N-722-1  B 15.200                     26 BB-01-S402-TW-T   BB-04-01           LOOP  #4 NARROW   RANGE  TI{ERMOWELL,   TOP                                      VE     N-722-1  B 15.200                     26 BB-01 -S402-TW-I  BB-04-01           LOOP  #4 NARROW   RANGE  THERMO WELL,   INSIDE                                   YE     N-722-1  B 15.200                     26 BB-0 I-S402-TW-O  BB-04-01           LOOP  #4 NARROW   RANGE  THERMO WELL,   OUTSIDE                                  YE     N-722-1  B 15.200                     26 BB-0l-S 101-TW-T  BB-01-01           LOOP #1 NARROW RANGE THERMO WELL, TOP                                            VE     N-722-1  B 15.205                     25 BB-01-S401-TW-T   BB-04-01           LOOP #4 NARROW RANGE THERMOWELL, TOP                                             VE     N-722-1  B 15.205                     25 HB-24-W502        BB-06-0 1          2' ELBOW TO2" PIPE                                              2     0.344      UT     MRP-146  DH           156             27 HB-24-W512        BB-06-0 1          2" ELBOW TO2" PIPE                                              2     0.344      UT     MRP-146  DH           156             27 BG-23-W596A       BG-03-23           2" ELBOW TO2" PIPE                                              2     0.344      UT     MRP-146  DH           156             27 BG-21-F027A       BG-01-21           3' PIPE TO 3" NOZZLE ON BB-56-BCA-27 1/2"                       3     0.438      UT     MRP-146  UH/H         112             27 RV-301-121-A      ISI-RBB01 SHT. 1   LOOP # 1 RPV OUTLET NOZZLE TO SAFE-END                    29   2.92            UT/YE    N-770-1  A-2          179             28 RV-301-121-B      ISI-RBB01 SHT. 1   LOOP #2 RPV OUTLET NOZZLE TO SAFE-END                     29   2.92            UT/VE    N-770-1  A-2          179             28 RV-301-121-C      ISI-RBB01 S1LIT. I LOOP #3 RPV OUTLET NOZZLE TO SAFE-END                     29   2.92            UT/YE    N-770-1  A-2          179             28 RV-301-121-D      ISI-RBB01 SHT. 1   LOOP #4 RPV OUTLET NOZZLE TO SAFE-END                     29   2.92            UT/YE    N-770-1  A-2          179             28 RV-302-12 1-A     ISI-RBB01 SHT. I   SAFE-END TO LOOP #1 RPV INLET NOZZLE                      27.5         2.79      UT     N-770-1  B            179                28, RV-302-12 1-B     ISI-RBB01 SHT. 1   SAFE-END TO LOOP #2 RPV INLET NOZZLE                      27.5         2.79      UT     N-770-1  B            179                28, RV-302-12 1-C     ISI-RBB01 SHT. 1   SAFE-END TO LOOP #3 RPV INLET NOZZLE                      27.5         2.79      UT     N-770-1  B            179                28, RV-302-121-D      ISI-RBB01 SHT. 1   SAFE-END TO LOOP #4 RPV INLET NOZZLE                      27.5         2.79      UT     N-770-1  B            179                28, WCRE-30                                                     4.1.4 Reactor Coolant System (BB)                                                                Revision 0 Page 26 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BB-3 lsystem: BB Relief Request or Component Name Drawing Number    Component Description                                Size Thickness  NDE Method Category Item   Cal Block          Notes RV-101-171     ISI-RBB01 SHT. I  RV CIRCUMFERENTIAL SHELL WELD                        NA        9.63      UT     B-A      BI~ll      176 RV-103-121     ISI-RBB0O1 SHT. 1 RV CIRCUMFERENTIAL SHELL WELD                        NA        9.63      UT     B-A      BI.I 1   175,176 RV-101-122A    1SI-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      Bl.12      175 RV-101-122C    ISI-RBB01 SET. I  RV LONGITUDINAL SHELL WELD                           NA        11.75     UT     B-A      B1.12      175 RV-101-124A    ISI-RBB0 1 SET. 1 RV LONGITUDINAL SHELL WELD                          "NA        9.63      UT     B-A      Bl.12      176 RV-101-124B    ISI-RBB0 1 SET. I RV LONGITUDINAL SHELL WELD                           NA        9.63      UT     B-A      BI1.12     176 RV-101-124C    ISI-RBB01 SET. 1  RV LONGITUDINAL SHELL WELD                           NA        9.63      UT     B-A      Bl1.12     176 RV-101-142A    ISI-RBB01 SHT. 1  RV LONGITUDINAL SHELL WELD                           NA        9.63      UT     B-A      Bl1.12     176 RV-101-142B    ISI-RBB01 SEIT. 1 RV LONGITUDINAL SHELL WELD                           NA        9.63      UT     B-A      B1.12      176 RV-101-142C    ISI-RBB01 SHT. 1  RV LONGITUDINAL SHELL WELD                           NA        9.63      UT     B-A      B1.12      176 CH-103-101     ISI-RBB01 SHT. 1  RV CLOSURE HEAD CIRCUMFERENTIAL WELD                 NA        8.25      UT     B-A      B1.21      177 RV-10 1-14 1   ISI-RBB01 SET. 1  RV LOWER HEAD TO SHELL WELD                          NA        6.38      UT     B-A      B1.21   176, 177 RV-102-151     ISI-RBB01 SET. 1  RV LOWER HEAD TO DOLLAR PLATE WELD                   NA        6.38      UT     B-A      B 1.21     177 CH-101-104-D   ISI-RBB01 SHT. 1  RV CLOSURE HEAD MERIDIONAL WELD                      NA        8.25      UT     B-A      B 1.22     177 RV-101-1 54A   ISI-RBB01 SHT. 1  RV LOWER HEAD MERIDIONAL WELD                        NA        6.38      UT     B-A      B 1.22     177 RV-101-154B    ISI-RBB01 SHT. 1  RV LOWER HEAD MERIDIONAL WELD                        NA        6.38      UT     B-A      B1.22      177 RV-101-154C    IS1-RBB01 SET. 1  RV LOWER HEAD MERIDIONAL WELD                        NA        6.38      UT     B-A      B 1.22     177 RV-101-154D    ISI-REBB1 SHT. 1  RV LOWER HEAD MERIDIONAL WELD                        NA        6.38      UT     B-A      B1.22      177 RV-I01-121     ISI-RBB01 SET. 1  RV FLANGE TO VESSEL WELD                             NA        11.75     UT     B-A      B 1.30     178 CH-101-101     ISI-RBB01 SHT. 1  RV CLOSURE HEAD TO FLANGE WELD                       NA        8.25    UT/MT    B-A      B1.40      176 WCRE-30                                                4.1.4 Reactor Coolant System (BB)                                                        Revision 0 Page 27 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3 Ieod3Examinations Relief Requesteor Cal Block           Notes Component Name    Drawing Number     Component Description                                    Size Thickness    NDE Method Category Item TBB03-SEAM-I-W    ISI-TBB03 SHT. 1   SHELL TO BOTTOM HEAD LONGITUDINAL WELD                   NA        3.75        UT     B-B      B2.12       101 EBB01ID-SEAM- 1-W ISI-EBB01D SHT. 1 BOTTOM HEAD TO TUBESHEET                                  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-105-12 1-B     ISI-RBB01 SI-IT. 1 INLET NOZZLE C TO VESSEL WELD                            NA         1 1.75     UT     B-D      B3.90     175, 178 RV-105-121-C      ISI-RBB01 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. 1   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-I    B-D      B3. 100 RV-105-121-B-IR   ISI-RBB01 SHT. 1   INLET NOZZLE C INNER RADIUS AND BORE                                          VT-I    B-D      B3.100 RV-105-121-C-IR   ISI-RBB01 SHT. 1   INLET NOZZLE F INNER RADIUS AND BORE                                          VT-I    B-D      B3. 100 RV- 105-121-D-IR  ISI-RBB01 SHT. I   INLET NOZZLE G INNER RADIUS AND BORE                                          VT-I    B-D      B3. 100 RV- 107-121-A     ISI-RBB01 SHT. I   OUTLET NOZZLE A TO VESSEL WELD                           NA         1 1.75     UT     B-D      B3.90     175, 178 RV-107-12 1-B     IS1-RBB01 SHT. 1   OUTLET NOZZLE D TO VESSEL WELD                           NA         11.75      UT     B-D      B3.90     175, 178 RV-107-12 1-C     ISI-RBB01 SI-T. 1  OUTLET NOZZLE E TO VESSEL WELD                           NA         1 1.75     UT     B-D      B3.90     175, 178 RV-107-121-D      ISI-RBB01 SHT. 1   OUTLET NOZZLE H TO VESSEL WELD                           NA         11.75      UT     B-D      B3.90     175, 178 RV-107-121-A-IR   ISI-RBB01 SHT. I   OUTLET NOZZLE A INNER RADIUS AND BORE                                         VT-1    B-D      B3. 100 RV-107-121-B-IR   ISI-RBB01 SI-T. I  OUTLET NOZZLE D INNER RADIUS AND BORE                                         VT-I    B-D      B3. 100 RV-107-121-C-IR. ISI-RBB01 SHT. 1   OUTLET NOZZLE C INNER RADIUS AND BORE                                         VT-i    B-D      B3.100 RV-107-121-D-IR   ISI-RBB01 SHT. 1   OUTLET NOZZLE D INNER RADIUS AND BORE                                         VT-i    B-D      B3. 100 TBB03-10A-W       ISI-TBB03 SHT. 1   SURGE NOZZLE TO BOTTOM HEAD WELD                         NA         2.55       UIT    B-D      B3.1 10     101 TBB03-10C-W       ]SI-TBB03 SHT. 1   SPRAY NOZZLE C TO TOP HEAD WELD                          NA         1.90       UT     B-D      B3.110      101 TBB03-10A-IR      ISI-TBB03 SHT. I   SURGE NOZZLE INNER RADIUS                                NA         2.55       UT     B-D      B3.120      101                  14 4.1.4 Reactor Coolant System (BB)                                                              Revision 0 WCRE-30 Page 28 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3 I~rod3Examin~ations Relief Request or Component Name Drawing Number     Component Description                                  Size Thickness  NDE Method Category Item    Cal Block         Notes TBB303-10C-IR  ISI-TBB03 SHT. 1   SPRAY NOZZLE C INNER. RADIUS                          NA          1.90     UT     B-D      B3. 120     101                14 EBII01A-1A-IR  ISI-EBB01A SHT. 1 PRIMARY INLET NOZZLE INNER RADIUS                      NA         5.00      UT     B-D      B3.140      104                14 EBII01A-1B-IR  ISI-EBB01A SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                     NA         5.00      UIT    B-D      B3.140      104                14 EB}301A-1A-IR  ISI-EBB01A SHT. 1 PRIMARY INLET NOZZLE INNER RADIUS                      NA         5.00     VT-i    B-D      B3. 140 EBII01A-1B-IR  ISI-EBB01A SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                     NA         5.00     VT-1    B-D      B3. 140 EBII01B-IA-IR  ISI-EBB0iB SHT. 1 PRIMARY INLET NOZZLE INNER RADIUS                      NA         5.00     VT-1    B-D      B3. 140 EBII01B-1B-IR  ISI-EBB01B SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                     NA         5.00     VT-I    B-D      B3. 140 EBII01C-1A-IR  ISI-EBB01C SHT. 1 PRIMARY INLET NOZZLE INNER RADIUS                      NA         5.00     VT-I    B-D      B3. 140 EBIB01C-1B-IR  ISI-EBB01C SHT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                     NA         5.00     VT-I    B-D      B3. 140 EBI301D-IA-IR  ISI-EBB01D SHT. 1 PRIMARY INLET NOZZLE INNER RADIUS                      NA         5.00     VT-I    B-D      B3. 140 EBt301D-iB-IR  ISI-EBB01D SHlT. 1 PRIMARY OUTLET NOZZLE INNER RADIUS                    NA         5.00     VT-i    B-D      B3. 140 CH-NUT-01      ISI-RBB01 SHlT. 1  REACTOR VESSEL NUT I                                                      VT-1    B-G-1    B6.10 CH-NUT-02      ISI-RBB0 1 SHT. 1  REACTOR VESSEL NUT 2                                                      VT-1    B-G-1    B6.10 CH-NUT-03      ISI-RBBO1 SHlT. 1  REACTOR VESSEL NUT 3                                                      VT-I    B-G-I    B6.10 CH-NUT-04      ISI-RBB01 SHlT. I  REACTOR VESSEL NUT 4                                                      VT-i    B-G-I    B6.10 CH-NUT-05      ISI-RBB01 SHlT. I  REACTOR VESSEL NUT 5                                                      VT-I    B-G-1    B6.10 CH-NUT-06      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 6                                                      VT-1    B-G-1    B6.10 CH-NUT-07      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 7                                                      VT-I    B-C-I    B6.10 CU-NUT-08      ISI-RBB0OI SilT. I REACTOR VESSEL NUT 8                                                      VT-I    B-C-I    B6.10 CH-NUJT-09     ISI-RBB01 SilT. 1  REACTOR VESSEL NUT 9                                                      VT-i    B-G-i    B6.10 CH-NUT- 10     ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 10                                                     VT-1    B-G-1    B6.10 WCRE-30                                                  4.1.4 Reactor Coolant System (BB)                                                        Revision 0 Page 29 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3
[~eio 3Examinations Relief Request or Component Name Drawing Number                                                            Size Thickness NDE Method Category Item   Cal Block         Notes Component Description CH-NUT-1 11    ISI-RBB0 1 SHT. I  REACTOR VESSEL NUT 11                                                    VT-i    B-G-1    B6.10 CH-NUJT-12     ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 12                                                    VT-i    B-G-1    B6.10 CH-NUT-13      ISI-RBBOL SHT. 1   REACTOR VESSEL NUT 13                                                    VT-i    B-U-i    B6.10 CH-NUT-14      ISI-RBB0I SHT. 1   REACTOR VESSEL NUT 14                                                    VT-I    B-G-1    B6.10 CH-NUT-I 5     ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 15                                                    VT-I    B-G-1    B6.10 CH-NUT-i6      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 16                                                    VT-i    B-U-i    56.10 C H-NULT- 17   ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 17                                                    VT-i    B-G-I    56.10 CH-NUT-1 8     ISI-RBB0 1 SH-T. 1 REACTOR VESSEL NUT 18                                                    VT-i    B-G-1    56.10 CH-NUT- 19     ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 19                                                    VT-i    B-G-I    B6. 10 CH-NUT-20      ISI-RBB0 1 SHT. I  REACTOR VESSEL NUT 20                                                    VT-I    B-G-I    56.10 CH-NUT-21      ISI-RBB01 SI-T. I  REACTOR VESSEL NUT 21                                                    VT-1    B-U-I    56.10 CH-NUT-22      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 22                                                    VT-I    B-G-i    B6.10 CH-NUT-23      ISI-RBB0 1 SHT. 1  REACTOR VESSEL NUT 23                                                    VT-I    B-G-I    B6.10 CH-NUT-24      ISI-RBB0 1 SHT. 1  REACTOR VESSEL NUT 24                                                    VT-i    B-G-l    56.10 CH-NUT-25      ISI-RBB01 SilT. I  REACTOR VESSEL NUT 25                                                    VT-i    B-U-I    B6.10 CH-NUTr-26     ISI-RBB01 SH-T. 1  REACTOR VESSEL NUT 26                                                    VT-i    B-U-i    B6.10 CH-NUT-27      ISI-RBB0 1 SHT. I  REACTOR VESSEL NUT 27                                                    VT-i    B-U-i    56.10 CH-NUT-28      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 28                                                    VT-i    B-U-i    56.10 CH-NUT-29      ISI-RBB0 1 SilT. 1 REACTOR VESSEL NUT 29                                                    VT-i    B-U-I    B6.10 CH-NUT-30      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 30                                                    VT-i    B-U-I    56.10 CH-NUT-3 I     ISI-RBB01 SilT. I  REACTOR VESSEL NUT 31                                                    VT-i    B-U-i    B6. 10 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                       Revision 0 Page 30 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BB-3 F~rod3Examinations ]
[System: BBj Relief Request or Component Name                                                                         Size Thickness NDE Method Category  Item  Cai Block         Notes Drawing Number     Component Description CH-NUT-32      IS1-RBB01 SHT. 1   REACTOR VESSEL NUT 32                                                  VT-I    B-U-i    B6.10 CH-NUT-33      ISI-RBB01 SHT. I   REACTOR VESSEL NUT 33                                                  VT-i    B-G-1    B6.10 CH-NUT-34      ISI-RBB01 SHT. I   REACTOR VESSEL NUT 34                                                  VT-i    B-G-i    B6.10 CH-NUT-35      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 35                                                  VT-i    B-G-1    B6.10 CH-NUT-36      ISI-RBB01 SHT. I   REACTOR VESSEL NUT 36                                                  VT-I    B-U-I    B6.10 CE-NUT-37      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 37                                                  VT-i    B-U-i    B6.10 CH-NUT-38      ISI-RBB01 SET. 1   REACTOR VESSEL NUT 38                                                  VT-I    B-G-i    B6.10 CH-NUT-39      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 39                                                  VT-i    B-U-i    B6.10 CH-NUT-40      ISI-RBB0I SET. 1   REACTOR VESSEL NUT 40                                                  VT-I    B-G-i    B6.1i0 CH-NUT--41     ISI-RBB01 SET. 1   REACTOR VESSEL NUT 41                                                  VT-i    B-G-i    B6. 10 CH-NUT-42      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 42                                                  VT-i    B-G-i    B6.10 CH-NUT--43     ISI-RBB0 1 SHlT. I REACTOR VESSEL NUT 43                                                  VT-i    B-G-i    B6.10 CH-NUT-44      ISI-RBB01 SHT. I   REACTOR VESSEL NUT 44                                                  VT-i    B-U-i    B6.10 CH-NUT-45      ISI-RBB01 SHT. I   REACTOR VESSEL NUT 45                                                  VT-i    B-U-i    B6.10 CH-NUT-46      ISI-RBB01 SilT. I  REACTOR VESSEL NUT 46                                                  VT-i    B-U-i    B6.10 CH-NUT--47     ISI-RBB01 SET. 1   REACTOR VESSEL NUT 47                                                  VT-i    B-U-i    B6.10 CH-NUT-48      ISI-RBB01 SET. 1   REACTOR VESSEL NUT 48                                                  VT-i    B-U-i    B6.10 CH-NUT--49     ISI-RBB01 SET. 1   REACTOR VESSEL NUT 49                                                  VT-i    B-U-i    B6.10 CH-NUT-50      ISI-RBB01 SET. 1   REACTOR VESSEL NUT 50                                                  VT-i    B-U-i    B6.10 CH-NUT-5 1     ISI-RBB01 SET. 1   REACTOR VESSEL NUT 51                                                  VT-i    B-U-i    B6.10 CH-NUT-52      ISI-RBB01 SHT. 1   REACTOR VESSEL NUT 52                                                  VT-i    B-U-i    B6.10 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 31 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE BB-3 Ieid3ExaminationsI
[System: BB    ]Relief                                               Request or Size  Thickness NDE Method Category Item  Cal Block    Notes Component Name Drawing Number    Component Description CH-NUT-53      ISI-RBB01 SHT. 1  REACTOR. VESSEL NUT 53                                                     VT-i    B-U-I    B6.10 CH-NUT-54      ISI-RBB01 SHT. 1  REACTOR VESSEL NUT 54                                                      VT-i    B-G-1    B6.10 CH-STUD-01     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 1                                   NA         NA       UT     B-G-1    B6.20     195 CH-STUD-02     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 2                                   NA          NA      UIT    B-U-i    B6.20     195 CH-STUD-03     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 3                                   NA          NA      UT     B-U-i    B6.20     195 CH-STUD-04     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 4                                   NA          NA      UT     B-U-i    B6.20     195 CH-STUD-05     ISI-RBBOI SHT. 1  REACTOR. VESSEL STUD 5                                  NA          NA      UT     B-G-i    B6.20     195 CH-STUD-06     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 6                                   NA          NA      UT     B-U-I    B6.20     195 CH-STUD-07     ISI-RBB01 SHT. I  REACTOR VESSEL STUD 7                                   NA          NA      UT     B-G-I    B6.20     195 CH-STUD-08     ISI-RBB01 SHT. I  REACTOR. VESSEL STUD 8                                  NA          NA      UT     B-U-I    B6.20     195 CH-STUD-09     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 9                                   NA         NA       UT     B-U-i    B6.20     195 CH-STUD-10     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 10                                  NA          NA      UIT    B-U-I    B6.20     195 CH-STUD-1 1    ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 11                                  NA          NA      UT     B-U-i    B6.20     195 CH-STUD-12     ISI-RBBO1 SHT. I  REACTOR VESSEL STUD 12                                  NA          NA      UT     B-U-i    B6.20     195 CH-STUD-13     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 13                                  NA          NA      UT1    B-U-i    B6.20     195 CH-STUD-14     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 14                                  NA          NA      UT     B-U-i    B6.20     195 CH-STUDJ-15    ISI-RBB01 SHT. I  REACTOR VESSEL STUD 15                                  NA          NA      UT     B-U-i    B6.20     195 CH-STUD- 16    ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 16                                  NA          NA      UT     B-U-i    B6.20     195 CI--STUD- 17   ISI-RBB0 1 SHT. 1 REACTOR VESSEL STUD 17                                  NA          NA      UT     B-U-I    B6.20     195 CH-STUD- 18    ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 18                                  NA          NA      UT     B-U-i    B6.20     195 CH-STUD- 19    ISI-RBB01 SHT. I  REACTOR VESSEL STUD 19                                  NA          NA      UT1    B-U-i    B6.20     195 WCRE-30                                                 . 1.4 Reactor Coolant System (BB)                                                   Revision 0 Page 32 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3 Ieod3ExaminationsI Relief Request or Size Thickness NDE Method Category Item  Cal Block         Notes Component Name Drawing Number    Component Description CH-STtJD-20    ISI-RBB01 SHT.1   REACTOR VESSEL STUD 20                                 NA        NA       UT     B-G-I    B6.20     195 CH-STUD-21     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 21                                 NA        NA       UT     B-U-t    B6.20     195 CH-STUD-22     ISI-RBB01 SEIT. 1 REACTOR VESSEL STUD 22                                 NA        NA       UT     B-G-t1   B6.20     195 CH-STUD-23     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 23                                 NA        NA       UT     B-G-1    B6.20     195 CH-STUD-24     ISI-RBBO01 SET. 1 REACTOR VESSEL STUD 24                                                                              195 NA        NA       UT     B-U-I    B6.20 CH-STUD-25     ISI-RBBO01 SET. 1 REACTOR VESSEL STUD 25                                 NA        NA       UT     B-U-I1   B6.20     195 CH-STUD-26     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 26                                 NA        NA       UT     B-G-t1   B6.20     195 CH-STUD-27     ISI-RBB01 SET. 1  REACTOR VESSEL STUD 27                                 NA        NA       UT     B-U-i    B6.20     195 CH-STUD-28     ISI-RBB01 SET. 1  REACTOR VESSEL STUD 28                                 NA        NA       UT     B-U-i    B6.20     195 CH-STUD-29     ISI-RBB01 SEIT. 1 REACTOR VESSEL STUD 29                                 NA        NA       UT     B-U-i    B6.20     195 CH-STUD-30     ISI-RBB01 SET. 1  REACTOR VESSEL STUD 30                                 NA        NA       liT    B-U-I    B6.20     195 CH-STUD-31I    ISI-RBB01 SET. 1  REACTOR VESSEL STUD 31                                 NA        NA       UT     B-G-t1 B6.20     195 CH-STUD-32     1SI-RBB01 SET. 1  REACTOR VESSEL STUD 32                                 NA        NA       UT     B-U-i1   B6.20     195 CH-STUD-33     ISI-RBB01 SET. 1  REACTOR VESSEL STUD 33                                 NA        NA       UT     B-U-i1   B6.20     195 CH-STUD-34     ISI-RBBOt SHTr. 1 REACTOR VESSEL STUD 34                                 NA        NA       UT     B-U-I    B6.20     195 CH-STUIJ-35    ISI-RBB01 SET. 1  REACTOR VESSEL STUD 35                                 NA        NA       UT     B-U-I1   B6.20     195 CH-STUD-36     ISI-RBB01 SET. 1  REACTOR VESSEL STUD 36                                 NA        NA       UT     B-U-i    B6.20     195 CH-STUD-37     ISI-RBBO1 SEIT. 1 REACTOR VESSEL STUD 37                                 NA        NA       UT     B-U-i1   B6.20     195 CH-STUD-38     ISI-RBB01 SELT. 1 REACTOR VESSEL STUD 38                                 NA        NA       UT     B-U- I   B6.20     195 CHI-STUD-39                                                                             NA        NA       UT     B-U-i    B6.20     195 ISI-RBB0I SET. 1  REACTOR VESSEL STUD 39 CH-STUD-40     ISI-RBB01 SELT. 1 REACTOR VESSEL STUD 40                                 NA        NA       UT     "B-U-i   B6.20     195 WCRE-30                                                4.1.4 Reactor Coolant System (BB)                                                       Revision 0 Page 33 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE    BB-3 I~dd3Examinations
[System: BB Relief Request or Size Thickness NDE Method Category Item  Cal Block          Notes Component Name Drawing Number    Component Description CH-STUD-41     ISI-RHB01 SHlT. 1 REACTOR VESSEL STUD 41                                   NA         NA      UIT    B-G-I    B6.20     195 CH-STUD-42     ISI-RBB01 SHlT. 1 REACTOR VESSEL STUD 42                                   NA         NA      UT     B-G-I    B6.20     i195 CH-STUD-43     ISI-RBB01 SHT. I  REACTOR VESSEL STUD 43                                   NA         NA      UT     B-G-i    B6.20     195 CH-STUD-44     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 44                                                                                195 NA         NA      UIT    B-U-I    B6.20 CH-STUD-45     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 45                                   NA         NA      UIT    B-G-I    B6.20     195 CH-STUD-46     ISI-RBB0i SHlT. 1 REACTOR VESSEL STUD 46                                   NA         NA      UT     B-G-I    B6.20     195 CH-STUD-.47    ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 47                                                                                195 NA         NA      UT     B-G-i    B6.20 CH-STUD-48     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 48                                   NA         NA      UT              B6.20     195 B-U-I CH-STUD-49     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 49                                   NA         NA      UIT    B-U-i    B6.20     195 CH-STUD-50     ISI-RBB01 SHT. 1  REACTOR VESSEL STUD 50                                   NA         NA      UT     B-U-i    B6.20     195 CH-STUD-51I    ISI-RBB0i SHT. I  REACTOR VESSEL STUD 51                                   NA         NA      UIT    B-U-1    B6.20     195 CH-STUD-52     ISI-RBB01 SHT. I  REACTOR VESSEL STUD 52                                   NA         NA      UIT    B-U-i    B6.20     195 CH-STUD-53     ISI-RBB01 SHlT. 1 REACTOR VESSEL STUD 53                                   NA         NA      UT     B-U-i    B6.20     195 CH-STUD-54     ISI-REBB1 SHT. 1  REACTOR VESSEL STUD 54                                   NA         NA      UT     B-U-I    B6.20     195 RV-LIG-01      ISI-RBB01 SHlT. 1 REACTOR VESSEL THREAD IN FLANGE 1                        NA         NA      UT     B-U-I    B6.40     140 RV-LIG-02      ISI-RBB01 SHT. 1  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                        140 B-U-I    B6.40 RV-LIG-04      ISI-RBB01 SHT. I  REACTOR VESSEL THREAD IN FLANGE 4                                                           B6.40     140 NA         NA      UT     B-U-I RV-LIG-05      ISI-RBB01 SHlT. I REACTOR VESSEL THREAD IN FLANGES5                        NA         NA      UT     B-U-I    B6.40     140 RV-LIG-06      ISI-RBB01 SHT. 1  REACTOR VESSEL THREAD IN FLANGE 6                        NA         NA      UT              B6.40     140 RV-LIG-07      IS1-RBB01 SilT. 1 REACTOR VESSEL THREAD IN FLANGE 7                        NA         NA      UT     B-G-I    B6.40      140 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                         Revision 0 Page 34 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3 IFrod3Examintions Relief Request or Component Name Drawing Number     Component Description                                Size Thickness NDE Method Category Item  Cal Block         Notes RV-LIG-08      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD 1N FLANGE 8                    NA        NA       UT     B-G-I    B6.40     140 RV-LIG-09      ISI-RBB0 1SHT. 1   REACTOR VESSEL THREAD IN FLANGE 9                    NA        NA       UT     B-G-1    B6.40     140 RV-LIG- 10     ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 10                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-I I     ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD TN FLANGE 11I                  NA        NA       UT     B-G-1    B6.40     140 RV-LIG- 12     ISI-RBB01 SHT. 1   REACTOR VESSEL TH-READ IN FLANGE 12                  NA        NA       UT     B-G-I    B6.40     140 RV-LIG-1 3     ISL-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 13                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG- 14     ISI-RBB0l SI-T. 1  REACTOR VESSEL THREAD IN FLANGE 14                   NA        NA       UT     B-G-I    B6.40     140 RV-LIG- 15     ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 15                   NA        NA       UT     B-G-I    B6.40     140 RV-LIG-1 6     ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 16                   NA        NA       UT     B-G-I    B6.40     140 RV-LIG- 17     ISI-RBB0I SHT. 1   REACTOR VESSEL THREAD IN FLANGE 17                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-1 8     ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 18                   NA        NA       UiT    B-G-1    B6.40     140 RV-LIG-1 9     ISI-RBB01 SHT. I   REACTOR VESSEL THREAD IN FLANGE 19                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-20      ISI-RBB01 SHIT. I  REACTOR VESSEL THREAD IN FLANGE 20                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-21      ISI-REBB1 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 21                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-22      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 22                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-23      ISI-RBB0 1 SHT. 1  REACTOR VESSEL THREAD IN FLANGE 23                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-24      ISI-RBB0 1 SHT. 1  REACTOR VESSEL THREAD IN FLANGE 24                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-25      ISI-RBB0 1 SHT. 1  REACTOR VESSEL THREAD IN FLANGE 25                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-26      ISI-RBB0 1 SHIT. 1 REACTOR VESSEL THREAD IN FLANGE 26                   NA        NA       UT     B-G-1    B640      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 SIHT. 1  REACTOR VESSEL THREAD TN FLANGE 28                   NA        NA       UT     B-G-1    B6.40     140 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                    Revision 0 Page 35 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE BB-3 Peid 3Examinations Relief Request or Component Name                                                                          Size Thickness NDE Method Category Item  Cal Block         Notes Drawing Number     Component Description RV-LIG-29      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 29                    NA        NA       UIT    B-G- 1   B6.40     140 RV-LIG-30      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 30                    NA        NA       UT     B-G- 1   B6.40     140 RV-LIG-31      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 31                    NA        NA       UT     B-G-I    B6.40     140 RV-LIG-32      ISI-RBB01 SHLT. 1  REACTOR VESSEL THREAD IN FLANGE 32                                                                 140 NA        NA       UT     B-U-i    B6.4u RV-LIG-33      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 33                    NA        NA       UT     B-U-i    86.40     140 RV-LIG-34      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 34                    NA        NA       UT     B-G-1    86.40     140 RV-LIG-35      ISI-RBB01 SHT. I   REACTOR VESSEL THREAD IN FLANGE 35                    NA        NA       UT     B-G-1    B6.40     140 RV-LIG-36      ISI-RBBO1 SHT. I   REACTOR VESSEL THREAD IN FLANGE 36                    NA        NA       UT     B-G-i    B6.40 140 RV-LIG-37      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 37                    NA        NA       UT     B-G-I    B6.40     140 RV-LIG-38      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 38                    NA        NA       UT     B-G-1    B6.40 140 RV-LIG-39      ISI-RBB01 SILT. 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-U-i    86.40     140 RV-LIG-41      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 41                    NA        NA       UT     B-G-I    B6.40     140 RV-LIG-42      ISI-RBB01 SHT. I   REACTOR VESSEL THREAD IN FLANGE 42                    NA        NA       UIT    B-U-i    86.40     140 RV-LIG-43      ISI-R.BBO1 SHlT. I REACTOR VESSEL THREAD IN FLANGE 43                    NA        NA       UT     B-U-i    86.40     140 RV-LIG-44      ISI-RBB01 SHLT. 1  REACTOR VESSEL THREAD IN FLANGE 44                    NA        NA       UT     B-U-I    B6.40     140 RV-LiG.-45     ISI-RBB01 SilT. 1  REACTOR VESSEL THREAD IN FLANGE 45                                                       B6.40     140 NA         NA      UT     B-U-I RV-LIG.-46     ISI-RBB01 SLITr.1  REACTOR VESSEL THREAD IN FLANGE 46                    NA         NA      UT     B-U-i1   86.40     140 RV-LIG-47      ISI-RBB01 SILT. 1  REACTOR VESSEL THREAD IN FLANGE 47                    NA         NA      UT     B-U-I    B6.40     140 RV-LIG-48      ISI-RBB01 SHlT. 1  REACTOR VESSEL THREAD IN FLANGE 48                    NA         NA      UiT    B-U-i    86.40     140 RV-LIG-49      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 49                    NA        NA       UT     B-U-i    86.40     140 WCRE-30                                                  4.1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 36 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3
[Peiod 3 xaminations ]
[System: BB Relief Request or Component Name                                                                          Size Thickness NDE Method Category Item  Cal Block         Notes Drawing Number     Component Description RV-LIG-50      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 50                    NA        NA       UT     B-G-1    B6.40     140 RV-LIG-51      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD I-N FLANGE 51                   NA        NA       UT     B-G-1    B6.40     140 RV-LIG-52      ISI-RBB0 1 SHT. 1  REACTOR VESSEL THREAD IN FLANGE 52                    NA        NA       UT     B-G-1    B6.40     140 RV-LIG-53      ISI-RBB01 SHT. 1   REACTOR VESSEL THREAD IN FLANGE 53                    NA        NA       UT     B-G-1    B6.40     140 RV-LIG-54      ISI-RBBO01 SHT. 1  REACTOR VESSEL THREAD IN FLANGE 54                    NA        NA       UT     B-G-I    B6.40     140 CH-WASI-i-01   ISI-RBB01I SHT. 1  REACTOR VESSEL WASHER AND BUSHING I                                     VT-I    B-G-1    B6.50 CH-WASH-02     ISI-RBB01 SI-T. I  REACTOR VESSEL WASHER AND BUSHING 2                                     VT-I    B-G-1    B6.50 CH-WASH-03     ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 3                                     VT-i    B-G-!    B6.50 CH-WASHI-04    ISI-RiBB01 SI-T. 1 REACTOR VESSEL WASHER AND BUSHING 4                                     VT-I    B-G-i    B6.50 CH-WASH-05     ISI-RBB0I SI-IT. 1 REACTOR VESSEL WASHER AND BUSHING 5                                     VT-1    B-G-1    B6.50 CH-WASI-i-06   ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 6                                     VT-i    B-G-1    B6.50 CH-WASH-07     ISI-RBB01 SI-T. 1  REACTOR VESSEL WASHER AND BUSHING 7                                     VT-i    B-G-1    B6.50 CH-WASH-08     ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 8                                     VT-i    B-G-1    B6.50 CH-WASH-09     ISI-RBB0i SHT. 1   REACTOR VESSEL WASHER AND BUSHING 9                                     VT-i    B-G-1    B6.50 CH-WASH-1I 0   ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 10                                    VT-i    B-G-1    B6.50 CH-WASH-1 1    ISI-RBBO01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 11                                    VT-i    B-G-1    B6.50 CH-WASH-i2     ISI-RBBOI SHT. 1   REACTOR VESSEL WASHER AND BUSHING 12                                    VT-I    B-G-I    B6.50 CH-WASI--13    ISI-RBBO1 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 13                                    VT-I    B-G-I    B6.50 CH-WASI--14    ISI-RBB01 SI-T. 1  REACTOR VESSEL WASHER AND BUSHING 14                                    VT-i    B-G-1    B6.50 CH-WASI-I 5    ISI-RBB01 SI-T. I  REACTOR VESSEL WASHER AND BUSHING 15                                    VT-I    B-G-1    B6.50 CH-WASI-I- 6   ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 16                                    VT-1    B-G-1    B6.50 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 37 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BB-3 Isystem: BB Relief Request or Thickness NDE Method          Item  Cal Block         Notes Component Name Drawing Number    Component Description                                Size                      Category CH-WASH- 17    ISI-RBB01 SI-T. 1 REACTOR VESSEL WASHER AND BUSHING 17                                   VT-I    B-G-I    B6.50 CH-WASH-1 8    ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 18                                   VT-I    B-G-I    B6.50 CH-WASH-19     ISI-RBB01 SHIT. 1 REACTOR VESSEL WASHER. AND BUSHING 19                                  VT-1    B-G-I    B6.50 CH-WASH-20     ISI-RBB01 SHT. I  REACTOR VESSEL WASHER. AND BUSHING 20                                  VT-i    B-G-1    B6.50 CH-WASH-21I    ISI-RBBO1 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 21                                   VT-1    B-G-1    B6.50 CH-WASH-22     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 22                                   VT-1    B-G-I    B6.50 CH-WASH-23     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 23                                   VT-l    B-G-1    B6.50 CH-WASH-24     ISI-RBB01 SHT. I  REACTOR VESSEL WASHER AND BUSHING 24                                   VT-i    B-G-I    B6.50 CH-WASH-25     ISI-RBBOI SHT. 1  REACTOR VESSEL WASHER AND BUSHING 25                                   VT-i    B-G-I    B6.50 CH-WASH-26     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 26                                   VT-I    B-G-I    B6.50 CH-WASH-27     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 27                                   VT-I    B-G-1    B6.50 CH-WASH-28     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 28                                   VT-I    B-G-1    B6.50 CH-WASH-29     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 29                                   VT-I    B-G-i    B6.50 CH-WASH-30     ISI-RBB01 SHT. 1  REACTOR. VESSEL WASHER. AND BUSHING 30                                 VT-1    B-G-I    B6.50 CH-WASH--31I   ISI-RBB0 1 SHT. 1 REACTOR. VESSEL WASHER AND BUSHING 31                                  VT-I    B-G-1    B6.50 CH-WASH-32     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSH{ING 32                                  VT-1    B-G-I    B6.50 CH-WASH-33     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 33                                   VT-I    B-G-1    B6.50 CH-WASH-34     ISI-RBB01 SHT. I  REACTOR VESSEL WASHER AND BUSHING 34                                   VT-I    B-G-1    B6.50 CH-WASH-35     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 35                                   VT-i    B-G-1    B6.50 CH-WASH-36     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 36                                   VT-I    B-G-1    B6.50 CH-WASH-37     ISI-RBB01 SHT. 1  REACTOR VESSEL WASHER. AND BUSHING 37                                  VT-1    B-G-I    B6.50 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                    Revision 0 Page 38 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE    BB-3 lSystem: BB]
Relief Request or Component Name        Drawing Number    Component Description                               Size Thickness NDE Method Category Item   Cal Block         Notes CH-WASH-38           ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 38                                  VT-i    B-G-I    B6.50 CH-WASH-39           ISI-RBB01 SET. 1   REACTOR VESSEL WASHER AND BUSHING 39                                  VT-I    B-G-i    B6.50 CH-WASH-40           ISI-RBB01 SET. 1   REACTOR VESSEL WASHER AND BUSHING 40                                  VT-i    B-G-i    B6.50 CH-WASH-41           ISI-RBB0i SHT. 1   REACTOR VESSEL WASHER AND BUSHING 41                                  VT-i    B-U-i    B6.50 CH-WASH--42          ISI-R.BB01 SHT. 1  REACTOR VESSEL WASHER AND BUSHING 42                                  VT-i    B-U-i    B6.50 CH-WASH-43           ISI-RBB0i SEIT. 1  REACTOR VESSEL WASHER AND BUSHING 43                                  VT-i    B-U-i    B6.50 CH-WASH-44           ISI-RBB0 1 SET. 1  REACTOR VESSEL WASHER AND BUSHING 44                                  VT-i    B-U-i    B6.50 CH-WASH-45           ISI-RBB01 SHT. 1   REACTOR VESSEL WASHER AND BUSHING 45                                  VT-i    B-U-i    B6.50 CH-WASH-46           ISI-R.BB0 1 SET. I REACTOR VESSEL WASHER AND BUSHING 46                                  VT-I    B-U-i    B6.50 CH-WASH-47           ISI-RiBB0I SHT. 1  REACTOR VESSEL WASHER AND BUSHING 47                                  VT-i    B-U-i    B6.50 CH-WASH-48           ISI-REBB0   SHT. 1 REACTOR VESSEL WASHER AND BUSHING 48                                  VT-i    B-U-i    B6.50 CH-WASH-49           ISI-RiBBO1 SHT. I  REACTOR VESSEL WASHER AND BUSHING 49                                  VT-I    B-U-i    B6.50 CH-WASH-50           ISI-RBB01 SHT. I   REACTOR VESSEL WASHER AND BUSHING 50                                  VT-i    B-U-i    B6.50 CH-WASH-51           ISI-RBBOL SET. 1   REACTOR VESSEL WASHER AND BUSHING 51                                  VT-i    B-U-i    B6.50 CH-WASH-52           ISI-RBBOI SHT. 1   REACTOR VESSEL WASHER AND BUSHING 52                                  VT-i    B-U-i    B6.50 CH-WASH-53           ISI-RBB01 SET. 1   REACTOR VESSEL WASHER AND BUSHING 53                                  VT-I    B-U-i    B6.50 CH-WASH-54           ISI-RBB01 SET. 1   REACTOR VESSEL WASHER AND BUSHING 54                                  VT-i    B-U-i    B6.50 PBB01 A-STUDS        M-712-00057        PBB01A PUMP MAIN BOLTS / STUDS (24)                 NA        NA       UT     B-U-i    B6.180 PBB01 A-FLANGE       ISI-PUMPS          PBB01A FLANGE SURFACE                                                 VT-i    B-U-i    B6.190                         4 PBB01 A-WASHERS/NUTS M-712-00057        PBB01A PUMP MAIN NUTS, BUSHINGS, WASHERS     (24)                     VT-i    B-U-I    B6.200                         5 WCRE-30                                                       WCRE-304.1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 39 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3
[Prid 3 xamiInationsI
[System: BB Relief Request or Size Thickness NDE Method          Item     Cal Block         Notes Component Name     Drawing Number    Component Description                                                            Category RV-INTERIOR        ISI-RBB01 SHT. 1  REACTOR VESSEL INTERIOR                                                  VT-3    B-N-1    B13.10 RV-CSL- 104-142-A  ISI-RBB01I SHT. 1 CORE SUPPORT LUG                                                         VT-3    B-N-2    B 13 .60 RV-CSL- 104-142-B  ISI-RBB01 SHT. 1  CORE SUPPORT LUG                                                         VT-3    B-N-2    B 13.60 RV-C SL- 104-142-C ISI-RBB01 SI-T. I CORE SUPPORT LUG                                                         VT-3    B-N-2    B 13.60 RV-CSL- 104-142-D  ISI-RBB01 SHT. 1  CORE SUPPORT LUG                                                         VT-3    B-N-2    B 13.60 RV-CSL-104-142-E   ISI-RBB01 SHT. 1  CORE SUPPORT LUG                                                         VT-3    B-N-2    B 13.60 RV-CSL- 104-142-F  ISI-RBB01 SHT. I  CORE SUPPORT LUG                                                         VT-3    B-N-2    B 13.60 RV-CORE STRUCT     ISI-RBB01 SHT. 1  REMOVABLE CORE SUPPORT STRUCTURES                                        VT-3    B-N-3    B 13.70 CH-214-1 12-B      ISI-RBB0 1 SHT. I PENETRATION 67 CRDM HOUSING WELD                                          PT     B-O      B 14.20 CH-214-1 12-E      ISI-RBB01 SHT. 1  PENETRATION 70 CRDM HOUSING WELD                                          PT     B-O      B 14.20 CH-2t4-1 12-G      ISI-RBB0 1 SHT. 1 PENETRATION 72 CRDM HOUSING WELD                                          PT     B-O      B 14.20 CH-215-1 12-B      ISI-RBB01 SHT. 1  PENETRATION 75 CRDM HOUSING WELD                                          PT     B-O      B 14.2 1 EBB01A-16-W        ISI-EBB01A SHT. 1 STEAM NOZZLE WELD                                      NA        3.95   UT/MT    C-B      C2.21        102 BB-02-H007         BB-0l-02          PIPING SUPPORT                                         3                 VT-3    F-A      FI.1 BB-02-H008         BB-01-02          PIPING SUPPORT                                         3                 VT-3    F-A      FI.1 BB-04-R014         BB-0 1-04 SILT. 1 PIPING SUPPORT                                         4                 VT-3    F-A      Fi.1 BB-04-C003         BB-01-04 SHT. 2   PIPING SUPPORT                                         4                 VT-3    F-A      FI.1 BB-04-R008         BB-01.-04 SI-T. 2 PIPING SUPPORT                                         4                 VT-3    F-A      FI.10 BB-l1l-HO01        BB-02-11I         PIPING SUPPORT                                         2                 VT-3    F-A      FI.I0 BB-0 l-R004        BB.-05-01         PIPING SUPPORT                                         14                VT-3    F-A      FI.10 WCRE-30                                                     4.1.4 Reactor Coolant System (BB)                                                         Revision 0 Page 40 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3
[System: BB Relief Request or Component Name Drawing Number    Component Description                                 Size Thickness NDE Method Category Item   Cal Block         Notes CRDMPL-SUP-5   ISI-CRDMPL        CRDM Upper Seismic Support                                              VT-3    F-A      F1.40 CRDMPL-SUP-6   ISI-CRDMPL        CRDM Upper Seismic Support                                              VT-3    F-A      FI.40 EBB01A-03 231  M-717-00002       SO A LOWER COLUMN SUPPORT                                               VT-3    F-A      F 1.40 EBB01A-04 231  M-717-00002       SG A LOWER COLUMN SUPPORT                                               VT-3    F-A      F1.40 PBB01 A-SUP-3  ISI-PUMPS         RCP A TIE ROD SUPPORT                                                   VT-3    F-A      F1.40 PBB0 1A-SUP-3A ISI-PUMPS         RCP A COLUMN SUPPORT                                                    VT-3    F-A      F 1.40 RBB-01-04      ISI-RBB01 SilT. 1 RV SUPPORT PAD 4                                                        VT-3    F-A      F 1.40                   I4R-02 TBB03-LUG-A-W  ISI-TBB03 SHT. 1  SEISMIC SUPPORT                                                         VT-3    F-A      FI.40                         11 TBB03-LUG-B-W  ISI-TBB03 SHT. I  SEISMIC SUPPORT                                                         VT-3    F-A      F1.40                         II TBB03-LUG-C-W  ISI-TBB03 SHLT. 1 SEISMIC SUPPORT                                                         VT-3    F-A      F1.40                         11 TBB03-LUG-D-W  ISI-TBB03 SI-T. I SEISMIC SUPPORT                                                         VT-3    F-A      F 1.40                        11 BB-0 1-$301-09 BB-03-01          3" NOZZLE TO 3" X 1.5' REDUCER                                           UIT    R-A      RI.1lI                    12, 13 3       0.438                                 112 BB-C01-S401-10 BB-04-01          3" NOZZLE TO 3" X 1 1/2" REDUCER                      3       0.438      UIT    R-A      RI 11      112            12, 13 BB-C01-S00 1-6 BB-05-01          14" PIPE TO 14' ELBOW                                 14       1.25      UT     R-A      RI.I11     130            12, 13 BB-C01-F 102   BB-01-C1          27 1/2' ELBOW-LOOP #1 RPV INLET SAFE-END              27.5     2.5       UIT    R-A      R1.20  SAP-07, 106            12 BB-C01-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-04-S01 1-D  BB-01-04 SI-T. I  6"X4" REDUCER TO 6" PIPE                              6       0.7 19    *UT     R-A      R1.20      117                12 BB-04-S002-E   BR-0 1-04 SHlT. 2 6"X4" EXPANDER TO 6" PIPE                             6       0.7 19     UT     R-A      R1.20      117                12 BB-C6-F001     BB-02-01          3" PIPE TO 3" NOZZLE ON C36-BCA-3 1"                  3       0.438      UT     R-A      R1.2C      112            12, 13 BB-06-PW6000   BB-02-0l          3" PIPE TO CAP (B.W.)                                 3       0.438      UT     R-A      R1.20      112                12 HB-24-W50 1    BB-06-01          2" PIPE TO 2" ELBOW                                   2       0.344      UIT    R-A      R1 .20     156                12 WCRE-30                                                   WR-04.1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 41 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3
[System: BB Relief Request or Size Thickness      NDE Method Category Item     Cal Block          Notes Component Name       Drawing Number     Component Description PBB01 A-FLYWH-EEL    ISI-PUMPS          PUMP FLYWHEEL                                        NA           NA      UT/PT/MT  AUG. 1   AUG.FW                             9 PBB01 B-FLYWHEEL     ISI-PUMPS          PUMP FLYWHEEL                                        NA           NA      UT/PT/MT  AUG. 1   AUG. FW                            9 PBB01 C-FLYWHEEL     ISI-PUMPS          PUMP FLYWHEEL                                        NA           NA      UT/PT/MT  AUG. 1   AUG.FW                             9 PBB01 D-FLYWHEEL     1SI-PUMPS          PUMP FLYWHEEL                                        NA           NA      UT/PT/MT  AUG. 1   AUG.FEW                            9 RV-30 1-121-A        ISI-RBB01 SHT. 1   LOOP #1 RPV OUTLET NOZZLE TO SAFE-END                                                                                          28 29        2.92        UT/VE    N-770-1  A-2           179 RV-30t -12 1-B       1SI-RBB01 SIHT. I  LOOP #2 RPV OUTLET NOZZLE TO SAFE-END                29        2.92        UT/VE    N-770-1  A-2           179                 28 RV-30 1-121-C        ISI-RBB01 SHT. I   LOOP #3 RPV OUTLET NOZZLE TO SAFE-END                29        2.92        UT/yE    N-770-1  A-2           179                 28 RV-301-121-D         ISI-RBB01 SHT. I   LOOP #4 RPV OUTLET NOZZLE TO SAFE-END                29        2.92        UT/VE    N-770-1  A-2           179                 28 RV-302-12 I-A        ISI-RBB0I SI-IT. 1 SAFE-END TO LOOP #1 RPV INLET NOZZLE                 27.5      2.79          UT     N-770-1  B179                             28, RV-302-121-B         IS1-RBBOI SHT. I   SAFE-END TO LOOP #2 RPV INLET NOZZLE                 27%5      2.79          UT     N-770-I  B179                             28, RV-302-121-C         ISI-RBBOI SHT. I   SAFE-END TO LOOP #3 RPV INLET NOZZLE                 27.5                                                  179                28, 2.79          UT     N-770-1  B RV-302-121-D         ISI-RBB01 SHT. I   SAFE-END TO LOOP #4 RPV INLET NOZZLE                 27.5      2.79          UT                            179                28, N-770-1  B TBB03-MWT090-WOL-DM  ISI-TBB03 SHT. 1   SURGE NOZZLE TO SAFE-END WELD OVERLAY                 14  See I, Note 21     UIT    N-770-1 DM-R    See I, Note 18 BB-01-MW7090-WOL-SS  BB-05-01           SURGE NOZZLE SAFE-END TO PIPE WELD OVERLAY            14  See I, Note 21     UT     I3R-05   SS-P    See I, Note 18 CH-107-101          ISI-RBB01 SHT. 1 RV VENT PENETRATION                                                           VE    N-729-1  B4. 10                        22 CH-1 12-201         ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    I                                                      VE    N-729-1  B4.10                         22 CH- 112-202-2       IS1-RBB01 SHT. 1 RV CRDM PENETRATION    2                                                      VE    N-729-1  84.10                         22 CH-1 112-202-3      ISI-RBB01 SHT. 1 RV CRDM PENETRATION    3                                                      VE    N-729-1  B4.10                         22 CH-1 12-202-4       ISI-RBBO1 SI-T. 1 RV CRDM PENETRATION    4                                                      VE    N-729-1  B4.10                         22 CH-1 12-202-5       ISI-RBB01 SI-T. 1 RV CRDM PENETRATION    5                                                      VE    N-729-1  B4.10                         22 CH-1 12-203-6       ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    6                                                      VE    N-729-1  B4. 10                        22 CH-1-i12-203-7      ISI-REBB0I SHT. 1 RV CRDM PENETRATION    7                                                      VE    N-729-1  B4.10                         22 Cl-i- 112-203-8     ISI-RBB01 SHT. 1 RV CRDM PENETRATION    8                                                      VE    N-729-1  B4.10                         22 CH-1 112-203-9      ISI-RBB01 SHT. 1 RV CRDM PENETRATION    9                                                      VE    N-729-1  B4.10                         22 CH-112-204-10       ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    10                                                     VE    N-729-1  B4.10                         22 CH-1 12-204-11      ISI-RBBO1 SHT. 1 RV CRDM PENETRATION     11                                                    VE    N-729-1  B4.10                         22 CH-1 12-204-12      ISI-RBBO1 SHT. I RV CRDM PENETRATION     12                                                    VE    N-729-1  B4.10                         22 CH-1 12-204-13      ISI-RBB01 SHT. I RV CRDM PENETRATION     13                                                    VE    N-729-1  B4.10                         22 CH-1 12-205-14      ISI-RBB01 SHT. 1 RV CRDM PENETRATION     14                                                    VE    N-729- I B4.10                         22 CH-1 12-205-15      ISI-RBB0 1 SHT. I RV CRDM PENETRATION     15                                                    yE    N-729-1  B4.10                         22 CH-1 12-205-16      ISI-RIBB01 SHT. I RV CRDM PENETRATION     16                                                    VE    N-729-1  B4.10                         22 WCRE-30                                                                                                                                                      Revision 0 4.1.4 Reactor Coolant System (BB)
Page 42 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE    BB-3 j~eid 3Examinations f
[System: BB Relief Request or Component Name    Drawing Number   Component Description                                 Size Thickness NDE Method Category  Item  Cal Block         Notes CH-1 12-205-17   ISI-RBB01 SHT. 1 RV CRDM PENETRATION     17                                               VE     N-729-1  B4.10                     22 CH-1 12-206-18   ISI-RBBOI SHT. 1 RV CRDM PENETRATION     18                                               VE     N-729-1I B4.10                     22 CH-i112-206-19   ISI-RBB01 SHT. 1 RV CRDM PENETRATION     19                                               VE     N-729-1  84.10                     22 CH-1 12-206-20   ISI-RBB0I SRT. 1 RV CRDM PENETRATION    20                                                VE     N-729-1  B4.10                     22 CR-I112-206-2 1  ISI-RBB01 SHT. 1 RV CRDM PENETRATION    21                                                VE     N-729-1  B4.10                     22 CH-1 12-207-22   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    22                                                VE     N-729-1  B4.10                     22 CR-i 112-207-23  ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    23                                                VE     N-729-1  B4.10                     22 Cl-I- 112-207-24 ISI-RBB01 SHT. 1 RV CRDM PENETRATION    24                                                VE     N-729-1  B4.10                     22 CR-i112-207-25   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    25                                                VE     N-729-1  B4.10                     22 CR-i 112-207-26  ISI-RBB01 SHT. 1 RV CRDM PENETRATION    26                                                VE     N-729-1  84.10                     22 CR-I 112-207-27  ISI-RBB01 SHT. 1 RV CRDM PENETRATION    27                                                VE     N-729-I  84.10                     22 CH-1 12-207-28   ISI-RBB01 SRT. 1 RV CRDM PENETRATION    28                                                VE     N-729-I  B4.10                     22 CR-i112-207-29   ISI-RBB0 1 SHT. I RV CRDM PENETRATION    29                                                VE     N-729-1  B4.10                     22 CH-1 12-208-30   ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    30                                                VE     N-729-1  84.10                     22 CH-1 12-208-31   ISI-REBB01 SHT. 1 RV CRDM PENETRATION    31                                                VE     N-729-1  84.10                     22 CR-i112-208-32   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    32                                                VE     N-729-1  84.10                     22 CR-I112-208-33   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    33                                                VE     N-729-1  84.10                     22 CR-i112-208-34   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    34                                                VE     N-729-1  B4.10                     22 CR-I112-208-35   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    35                                                VE     N-729-1  B4.10                     22 CH-1 12-208-36   ISI-RBB0 1 SHT. I RV CRDM PENETRATION    36                                                VE     N-729-I  B4.10                     22 CH-1 12-208-37   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    37                                                VE     N-729-1  B4.10                     22 CH-1 12-209-3 8  ISI-RBB01 SHT. 1 RV CRDM PENETRATION    38                                                VE     N-729-1  B4.I10                    22 CH-i-i12-209-39  ISI-RBB01 SHT. 1 RV CRDM PENETRATION    39                                                VE     N-729-1  B4.10                     22 CR-i112-209-40   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    40                                                VE     N-729-1  B4. 10                    22 CR-i112-209-41   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    41                                                VE     N-729-I  B4.10                     22 CH-1 12-210.-42  ISI-RBB01 SHT. I RV CRDM PENETRATION    42                                                VE     N-729-I  84.10                     22 CH-1 12-210-43   ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    43                                                VE     N-729-1  84.10                     22 CH-1 12-210-44   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    44                                                VE     N-729-1  B4. 10                    22 CR-I112-210-45   ISI-RBB0 1 SHT. I RV CRDM PENETRATION    45                                                VE     N-729- I B4. 10                    22 CR-I112-210-46   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    46                                                VE     N-729-1  B4.10                     22 CH-1 12-210-47   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    47                                                VE     N-729-1  B4.10                     22 CR-i112-210-48   ISI-RBB01 SRT. I RV CRDM PENETRATION    48                                                VE     N-729-1  B4.10                     22 CR-i112-210-49   ISI-RBB01 SHT. 1 RV CRDM PENETRATION    49                                                VE     N-729-1  B4.10                     22 CR-I112-211-50   ISI-RBB01 SHT. I RV CRDM PENETRATION    50                                                VE     N-729-1I B4.10                     22 CH-1 12-211-51   ISI-RBB01 SHT. I RV CRDM PENETRATION    51                                                VE!    N-729-1I B4.10                     22 CR-I112-211-52   ISI-RBB01 SHlT. 1 RV CRDM PENETRATION    52                                                VE     N-729-1  B4.10                     22 CH-112-211-53    ISI-RBB0 1 SHT. 1 RV CRDM PENETRATION    53                                                VE     N-729-1  B4. 10                    22 CR-i112-212-54   ISI-RBB01 SLIT. 1 RV CRDM PENETRATION    54                                                VE     N-729-1  B4. 10                    22 CH-1 12-212-55   ISI-RBB01 SHT. I RV CRDM PENETRATION    55                                                VE     N-729-1  B4.10                     22 CR-i112-212-56   ISI-RBB01 SilT. 1 RV CRDM PENETRATION    56                                                VE     N-729-1  B4.10                     22 CR-i112-212-57   ISI-RBB01 SHT. I RV CRDM PENETRATION    57                                                VE     N-729-1  B4.10                     22 CH-i112-212-58   ISI-RBBOi SHT. I RV CRDM PENETRATION    58                                                VE     N-729-1  B4. 10                    22 WCRE-30                                                   4.1.4 Reactor Coolant System (BB)                                                     Revision 0 Page 43 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3 I~eiod3 xaminations ]
Relief Request or Component Name   Drawing Number   Component Description                                Size Thickness NDE Method Category Item    Cal Block         Notes CH-1 12-212-59  ISI-RBB01 SHT. 1 RV CRDM  PENETRATION   59                                               VE     N-729-1  B4.10                       22 CH-1 12-212-60  ISI-RBB0 1 SHT. 1 RV CRDM  PENETRATION   60                                               VE     N-729-1  B4.10                       22 CH-1 12-212-61  ISI-RBB01 SHT. 1 RY CRDM  PENETRATION   61                                               YE     N-729-1  B4. 10                      22 CH-1 12-213-62  ISI-RBB0I SHT. 1 RV CRDM  PENETRATION   62                                               VE     N-729-1  B4.10                       22 Cl-I-i12-213-63 ISI-RBB01 SHT. 1 RV CRDM  PENETRATION   63                                               VE     N-729-1  B4.10                       22 CH-1 12-213-64  ISI-RBB0 1 SHT. 1 RV CRDM  PENETRATION   64                                               YE     N-729-1  B4.10                       22 CH-1 12-213-65  ISI-RBB0 1 SHT. 1 RV CRDM  PENETRATION   65                                               VE     N-729-1  B4.10                       22 CH-1 12-214-66  1SI-RBB01 SHT. 1 RV CRDM  PENETRATION   66                                               VE     N-729-1  B4.10                       22 CH-1 12-214-67  ISI-RBB01 SHT. I RV CRDM  PENETRATION   67                                               VE     N-729-1  B4.10                       22 CH-1 12-214-68  ISI-RBB01 SHT. I RV CRDM  PENETRATION   68                                               VE     N-729-1  B4.10                       22 CH-1 12-214-69  ISI-RBB0 1 SHT. 1 RV CRDM  PENETRATION   69                                               VE     N-729-1  B4.10                       22 CH-1 12-214-70  ISI-RBB01 SHT. 1 RV CRDM  PENETRATION   70                                               VE     N-729-1  84.10                       22 CH-1 12-214-71  ISI-RBB01 SLIT. 1 RV CRDM  PENETRATION   71                                               VE     N-729-1  B4. 10                      22 CH-1 12-214-72  ISI-RBB01 SHT. 1 RV CRDM  PENETRATION   72                                               VE     N-729-1  B4.10                       22 CH-112-214-73   ISI-RBB0I SHT. 1 RV CRDM  PENETRATION   73                                               YE     N-729-1  B4. 10                      22 CH-1 12-215-74  ISI-RBB01 SHT. 1 RV CRDM  PENETRATION   74                                               YE     N-729-1  B4.10                       22 CH-1 12-215-75  ISI-RBB01 SHT. I RV CRDM  PENETRATION   75                                               YE     N-729-1  B4.10                       22 CH-1 12-215-76  ISI-RBB01 SIT. 1 RV CRDM  PENETRATION   76                                               YE     N-729-1  B4.10                       22 CH-1 12-215-77  ISI-RBB01 SHT. I RV CRDM  PENETRATION   77                                               YE     N-729-1  B4.10                       22 CH-1 12-215-78  ISI-RBB0 1 SHT. I RY CRDM  PENETRATION   78                                               YE     N-729-1  B34.10                      22 RV-201-151-1    ISI-RBB01 SHT. I RV BMI PENETRATION I                                                    YE     N-722-1  B 15.80                     23 RV-201-151-2    ISI-RBB0 1 SHT. 1 RY BMI PENETRATION 2                                                    YE     N-722-I  B 15.80                     23 RV-201-151-3    ISI-RBB01 SHT. 1 RV BMI PENETRATION 3                                                    YE     N-722-1  B 15.80                     23 RV-201-151-4    ISI-RBB01 SHT. 1 RY BMI PENETRATION 4                                                    YE     N-722-1  B 15.80                     23 RV-201-151-5    ISI-RBB01 SHT. I RY BMI PENETRATIONS5                                                    YE     N-722-1  815.80                      23 RV-201I-151-6   ISI-RBB01 SHT. I RV BMI PENETRATION 6                                                    YE     N-722-1I B 15.80                     23 RV-201-151-7    ISI-RBB0 1 SIT. I RY BMI PENETRATION 7                                                    YE     N-722-1  B 15.80                     23 RV-201-151-8    ISI-RBB01 SHT. 1 RY BMI PENETRATION 8                                                    YE     N-722-1  B 15.80                     23 RV-20 1-151-9   ISI-RBB01 SHT. 1 RV BMI PENETRATION 9                                                    YE     N-722-1  B 15.80                     23 RV-201-151-10   ISI-RBB01 SIT. 1 RV BMI PENETRATION 10                                                   YE     N-722-1  B 15.80                     23 RV-201-151-1 1  ISI-RBB01 SHT. 1 RY BMI PENETRATION 11                                                   YE     N-722-1  B 15.80                     23 RV-201-151-12   ISI-RBB01 SHT. 1 RY BMI PENETRATION 12                                                   VE     N-722-1  B 15.80                     23 RV-201-151-13   ISI-RBB01 SHT. 1 RY BMI PENETRATION 13                                                   YE     N-722-1  B 15.80                     23 RV-201-151-14   ISI-RBB01 SIT. 1 RY BM1 PENETRATION 14                                                   YE     N-722-1  B15.80                      23 RV-201-151-15   ISI-RBB01 SHT. 1 RY BMI PENETRATION 15                                                   YE     N-722-1  B15.80                      23 RV-201-151-16   ISI-RBB01 SHT. I RV BMI PENETRATION 16                                                   YE     N-722-1  B 15.80                     23 RV-201-151-17   ISI-RBB01 SHT. 1 RY BMI PENETRATION 17                                                   VE     N-722-1  815.80                      23 RV-201-151-18   ISI-RBB01 SHT. I RY BMI PENETRATION 18                                                   YE     N-722-1  B 15.80                     23 RV-201-151-19   ISI-RBB01 SHT. I RY BMI PENETRATION 19                                                   YE     N-722-1  815.80                      23 RV-201-151-20   ISI-RBB01 SHT. 1 RY BMI PENETRATION 20                                                   VE     N-722-1I 815.80                      23 RV-201 - 151-21 ISI-RBB01 SI-T. 1 RY BMI PENETRATION 21                                                   VE     N-722-1  B 15.80                     23 WCRE-30                                                 4.1.4 Reactor Coolant System (BB)                                                      Revision 0 Page 44 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BB-3 Ieod3ExaminationsI
[System: BB Relief Request or Component Name                                                                              Size Thickness NDE Method Category Item    Cal Block         Notes Drawing Number     Component Description RV-201-151-22  ISI-RBB0 1 SHT. I  RV BMI PENETRATION 22                                                       VE     N-722-I  B 15.80 RV-201-*151-23 ISI-RBB01 SHT. 1  RV BMI PENETRATION 23                                                       VE     N-722-1  B15.80 RV-201-*151-24 ISI-RBB01 SHT. 1  RV BMI PENETRATION 24                                                       VE     N-722-1  B15.80 RV-201-151-25  ISI-RBB01 SHT. 1  RV BMI PENETRATION 25                                                       VE     N-722-1  B15.80 RV-201-151-26  ISI-RBB01 SHT. 1  RV BMI PENETRATION 26                                                       VE     N-722-1  B 15.80 RV-201-151-27  ISI-RBB01 SHT. 1  RV BMI PENETRATION 27                                                       VE     N-722-1  B15.80 RV-201-1 51-28 ISI-RIBB01 SHT. 1  RV BMI PENETRATION 28                                                       VE     N-722-I  B 15.80 RV-201--151-29 IS1-RBBO1 SHT. I  RV BMI PENETRATION 29                                                       VE     N-722- l B 15.80 RV-201-l51-30  ISI-R.BB01 SI-T. 1  RV BMI PENETRATION 30                                                       VE     N-722-1  B 15.80 RV-201--151-31 ISI-RBB01 SHT. I  RV BMI PENETRATION 31                                                       VE     N-722-1  B15.80 RV-201-151-32  ISI-RIBB0I SI-T. I  RV BMI PENETRATION 32                                                       VE     N-722-1  B15.80 RV-201-151-33  ISI-RBB01 SHT. 1  RV BMI PENETRATION 33                                                       VE     N-722-1  B 15.80 RV-201-151-34  ISI-RBB01 SHT. 1  RV BMI PENETRATION 34                                                       VE     N-722-1  B15.80 RV-201-151-35  ISI-RBB01 SilT. 1  RV BMI PENETRATION 35                                                       VE     N-722-1  B 15.80 RV-201-l 51-36 ISI-RBB01 SHT. 1  RV BMI PENETRATION 36                                                       VE     N-722- I B 15.80 RV-201-l151-37 ISI-RBB01 SHT. I  RV BMI PENETRATION 37                                                       VE     N-722-1  B15.80 RV-201-151-38  ISI-RBB01 SHT. 1  RV BMI PENETRATION 38                                                       VE     N-722-1  B15.80 RV-201-15I-39  ISI-RBBO1 SHT. 1  RV BMI PENETRATION 39                                                       VE     N-722-1  B 15,80 RV-20N1-51-40  ISI-R.BB01 SIIT. I  RV BMI PENETRATION 40                                                       VE     N-722-1  B 15.80 RV-201-151-41  1SI-RBB01 SHlT. 1  RV BMI PENETRATION 41                                                       VE     N-722-1  B 15.80 RV-201-*151-42 ISI-RBB0 1 SI-T. I  RV BMI PENETRATION 42                                                       VE     N-722- l B 15.80 RV-20 1-151-43 ISI-RIBB01 SHT. I  RV BMI PENETRATION 43                                                       VE     N-722-1  B 15.80 RV-201-151-44  ISI-RBB01 SHT. I  RV BMIE PENETRATION 44                                                      VE     N-722-1I B15.80 RV-201I-I51-45 1S1-RBB0 1 SHlT. 1  RV BMI PENETRATION 45                                                       VE     N-722-1  B15.80 RV-201-151-46  ISI-RIBB01 SHT. 1  RV BMI PENETRATION 46                                                       VE     N-722-1  B 15.80 RV-201-151-47  ISI-RBB01 SHT. 1  RV BMI PENETRATION 47                                                       VE     N-722-1  B 15.80 RV-201-151-48  ISI-RBB01 SHT. 1  RV BMI PENETRATION 48                                                       VE     N-722- 1 B 15.80 RV-201-151-49  ISI-RBB0I SHT. 1  RV BMI PENETRATION 49                                                       VE     N-722-1  B 15.80 RV-20N1-51-50  ISI-RBB01 SHT. I  RV BMI PENETRATION 50                                                       VE     N-722-I  B 15.80 RV-201-151-51  ISI-RBB01 SI-T. 1  RV BMI PENETRATION 51                                                       VE     N-722-1  B 15.80 RV-201-151-52  ISI-RBB01 SHT. 1  RV BMI PENETRATION 52                                                       VE     N-722-1  B15.80 RV-201-151-53  ISI-RBB01 SHT. 1  RV BMI PENETRATION 53                                                       VE     N-722-1  B 15.80 RV-201-151-54  ISI-RIBB01 SHT. 1  RV BMI PENETRATION 54                                                       VE     N-722-1  B 15.80 RV-201 -151-55 ISI-RBB01 SHT. 1  RV BMI PENETRATION 55                                                       VE     N-722-I  B 15.80 RV-201-151-56  ISI-RBB01 SHT. 1  RV BMI PENETRATION 56                                                       VE     N-722-1I B 15.80 RV-20I- 151-57 ISI-R.BBOI SilT. 1  RV BMI PENETRATION 57                                                       VE     N-722-1  B 15.80 RV-20l- 151-58 ISI-R.BB01 SHT. 1  RV BMI PENETRATION 58                                                       VE     N-722-1  B15.80 RV-30 1-121-A   ISI-RBB01 SHT. I LOOP  #1 RPV OUTLET   NOZZLE  TO SAFE-END                29       2.92      VE     N-722-1  B 15.90                    24 RV-301-12 1-B   ISI-RBB0I SHT. 1 LOOP  #2 RPV OUTLET   NOZZLE  TO SAFE-END                29       2.92      VE     N-722-1  B 15.90                    24 RV-301-12 1-C   ISI-RBB01 SI-T. 1 LOOP  #3 RPV OUTLET   NOZZLE  TO SAFE-END                29       2.92      VE     N-722-1  B15.90                     24 RV-301-121-D    ISI-RBB0 1 SHT. I LOOP  #4 RPV OUTLET   NOZZLE  TO SAFE-END                29       2.92      VE     N-722-1  B 15.90                    24 WCRE-30                                                    4.1.4 Reactor Coolant System (BB)                                                        Revision 0 Page 45 of 46

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BB-3 Ieid3Examinations
[  Sytem:BB            IRelief                       Request or Size   Thickness NDE Method  Category Item      Cal Block    Notes Component Name    Drawing Number    Component Description RV-302-12 1-B     ISI-RBB0 1 SHT. 1 SAFE-END TO LOOP #2 RPV INLET NOZZLE                      27.5       2.79      VE     N-722-1   B1 5.95                  25 RV-302-12 1-C     ISI-RBB01 SHT. 1  SAFE-END TO LOOP #3 RPV INLET NOZZLE                      27.5       2.79      VE     N-722-1   B15.95                   25 BB-0 1-S 102-TW-T BB-01-01          LOOP  # 1 NARROW  RANGE THERMO WELL,    TOP                                    VE     N-722-1   B15.200                  26 BB-01-S 102-TW-I  BB-01-01          LOOP  #1 NARROW   RANGE THERMO WELL,    INSIDE                                 VE     N-722-1   B15.200                  26 BB-01 -S 102-TW-O BB-01-01          LOOP  #1 NARROW   RANGE THERMO WELL,    OUTSIDE                                VE     N-722-1   B 15.200                 26 BB-0 1-S202-TW-T  BB-02-01          LOOP  #2 NARROW   RANGE THERMOWELL,     TOP                                    VE     N-722-1   B 15.200                 26 BB-0 1-S202-TW-I  BB-02-01          LOOP  #2 NARROW   RANGE THERMOWELL,     INSIDE                                 VE     N-722-1   B 15.200                 26 BB-01 -S202-TW-O  BB-02-0 1         LOOP  #2 NARROW   RANGE THERMOWELL,     OUTSIDE                                VE     N-722-1   B 15 .200                26 BB-01 -S302-TW-T  BB-03-0 1         LOOP  #3 NARROW   RANGE THERMO WELL,    TOP                                    VE     N-722-1   B 15.200                 26 BB-0 1-S302-TW-I  BB-03-01          LOOP  #3 NARROW   RANGE THERMO WELL,    INSIDE                                 VE     N-722-1   B 15.200                 26 BB-01 -S302-TW-O  BB-03-01          LOOP  #3 NARROW   RANGE THERMO WELL,    OUTSIDE                                VE     N-722-1   B 15.200                 26 BB-0 1-S402-TW-T  BB-04-01          LOOP  #4 NARROW   RANGE THERMO WELL,    TOP                                    VE     N-722-1   B 15.200                 26 BB-0 I-S402-TW-I  BB-04-0 1         LOOP  #4 NARROW   RANGE THERMO WELL,    INSIDE                                 VE     N-722-1   B 15.200                 26 BB-01-S402-TW-O   BB-04-0l          LOOP  #4 NARROW   RANGE THERMO WELL,    OUTSIDE                                VE     N-722-1   B15.200                  26 BB-01 -$201 -TW-T BB-01-01          LOOP #2 NARROW RANGE TI-ERMO WELL, TOP                                         VE      N-722-1  B 15.205                 25 BB-0 I-S301-TW-T  BB-04-01          LOOP #3 NARROW RANGE THERMO WELL, TOP                                          VE      N-722-1  B15.205                  25 HB-24-W502        BB-06-01          2" ELBOW T02" PIPE                                        2         0.344      UT      MRP-146  DH            156        27 HB-24-W5 12       BB-06-01          2' ELBOW T02" PIPE                                        2         0.344      UT      MRP-146  DH-           156        27 BG-23-W596A       BG-03-23          2" ELBOW T02" PIPE                                        2         0.344      UT      MRP-146  DH            156        27 BG-21-F027A       BG-01-21          3" PIPE TO 3" NOZZLE ON BB-56-BCA-27 1/2"                 3         0.438      UT      MRP-146  U-/H~         112        27 WCRE-30                                                     4.1.4 Reactor Coolant System (BB)                                                          Revision 0 Page 46 of 46

WOLF CREEK GENERATING STATION THIRD INTERVAL IST PROGRAM PLAN 4.1.5 Chemical and Volume Control System (BG)
A.      Applicable System Piping and Instrument Drawings
: 1. M-12BG01-Chemical and Volume Control System
: 2. M-12BG03-Chemical and Volume Control System 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 Generating Station Interval 4".
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 4".
D.       Applicable ISI Isometrics and ISI 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-01-01 Sheet 1        Chemical and Volume Control Normal Charging Line Containment Penetration
: 2. M-189-50BG-01-21 Sheet 1        Chemical and Volume Control Normal and Alternate Charging Lines 3     M-1 89-50BG-02-22 Sheet 1       Chemical and Volume Control Letdown Line 4     M-189-50BG-02-22 Sheet 2        Chemical and Volume Control Letdown Line Containment Penetration
: 5. M-189-50BG-03-23 Sheet 1        Chemical and Volume Control Excess Letdown Line
: 6. M-189-5013G-04-09 Sheet 1       Chemical and Volume Control RCP Seal Water Injection Containment Penetration
: 7. M-189-50BG-05-24 Sheet 1        Chemical and Volume Control Auxiliary Spray Line
: 8. M-189-50BG-06-02 Sheet 1        Chemical and Volume Control Centrifugal Charging Pump Suction
: 9. M-189-50BG-06-02 Sheet 2        Chemical and Volume Control CCP Discharge (HPSI Discharge)
: 10. M-189-50BG-06-10 Sheet 1 Chemical and Volume CCP Discharge to Seal Water Injection Filters 11i. M-189-50ISI-PUMPS Sheet 1 ISI Pumps WCRE-30                  4.1.5 Chemical and Volume Control System (BG)                        Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.5 Chemical and Volume Control System (BG)
E.        Summary of Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table 1 is a sunmmary 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 1S1 Database.
TABLE 1 SECTION XI AND AUGMENTED COMPONENT 

==SUMMARY==
AN]) SCHEDULE COMPONENT OR ITEM                 CODE             CODE             AUG.              AUG        TOTAL IN           EXAMS BY PERIOD & INTERVAL DESCRIPTION               CATEGORY          ITEM NO.       CATEGORY           ITEM NO.       SYSTEM       P.1   P__2   P.3       INTERVAL PIPING WELDED                   C-C             C3.20               --                             4          1     0     01 ATTACHMENTS PUMPS WELDED                    C-C             C3.30               --                             80               1     0              1 ATTACHMENTS PIPING COMPONENTS                  F-A             FI.10               --                            15         3      2     1              6 SUPPORTS PIPING COMPONENTS                  F-A             F1.20               --                            27          1     2     2              5 SUPPORTS SUPPORTS OTHER                   F-A             F1.40               --                            82                2     0              4 THAN PIPING SUPPORTS PIPING WELDS SUBJECT                 R-A             Ril.11                                            18         1      2     2              5 TO THERMAL FATIGUE                 Note 1           Note 1 PIPING WELDS NOT                  R-A             R1.20              --                            173         4      4     4              12 SUBJECT TO A DAMAGE                 Note 1           Note 1 MECHANISM PIPING WELDS SUBJECT                                                 USAR               3.6.2         76          0      0     0              0 TO HELB REQUIREMENTS              _  _   _  _ _     _    _   _  _     _  _     _  _      _  _   _ _ _  _  _   _ _ _    _   __  _   _   _ _   _ _   _  _  _   _
Note 1: See Section H for an explanation of Category R-A and Item R1 .XX nomenclature.
WCRE-30                                                  4.1.5 Chemical and Volume Control System (BG)                                              Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.5         Chemical and Volume Control System (BG)
F. Augmented ISI Requirements 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 Pipinu- 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-33 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-5O00 and IWB-5000, the Class 1 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 XI, 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 4.2.1i H. Risk Informed ISI Program A Risk Informed Inservice Inspection (RI-ISI) Program has been applied to Code Class 1 and 2 piping welds at WCGS. 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-1 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 through 4-4 of TR-1 12657 Rev. B-A.
Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table BG-l (Period 1 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-30                4.1.5 Chemical and Volume Control System (BG)                            Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BG-1
[Period 1 Examinations SSystem: BG Relief Request or Component Name Drawing 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-23-W593     BG-03-23        2"x2"x3/4" TEE TO 2" PIPE                                 2       0.344      UT     R-A      RI~ll      156           1,2 BG-23-W584     BG-03-23        2" TEE TO 2" PIPE                                         2       0.344      UIT    R-A      R1.20      156 BG-02-F045     BG-06-02 SHT. 2 4" PIPE TO 4" ELBOW                                       4       0.531      UT     R-A      RL.20      114 1
BG-02-FW3 12   BG-06-02 SHT. 2 4" PIPE TO 4" ELBOW                                       4       0.531      UT     R-A      R1.20      114 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-H001     BG-05-24        PIPING SUPPORT                                            2                 VT-3    F-A      FI.10 BG-2 I-R017    BG-01-21        PIPING SUPPORT                                            3                 VT-3    F-A      F!I0 BG-24-R003     BG-05-24        PIPING SUPPORT                                            2                 VT-3    F-A      FI.!
BG-02-A002     BG-06-02 SHT. 1 PIPING SUPPORT                                            8                 VT-3    F-A      F 1.20 PBG05A-SUP-1   BG-06-02 SHT. 1 CHARGING PUMP A SUPPORT                                   6                         F-A      F1.40 VT-3 PBG05A-SUP-2   BG-06-02 SHT. 1 CHARGING PUMP A SUPPORT                                   6                         F-A      F 1.40 WCRE-30                                              4.1.5 Chemical and Volume Control System (BG)                                               Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTHINTERVAL 1SI PROGRAM PLAN TABLE BG-2 F Period2Eaiations I SSystem:  BG Relief Request or Size    Thickness NDE Method          Item  Cal Block          Notes Component Name Drawing Number  Component Description                                                             Category PBG05A-SUP-3   BG-06-02 SHT. 1 CHARGING PUMP A INTEGRALLY WELDED ATTACH.            6                     PT     C-C      C3.30 BG-2 l-F013B   BG-01-21        3" PIPE TO VALVE 8378A                               3          0.438      UT     R-A      RI 11     112          1,2 BG-22-FW327A   BG-02-22 SET. 1 3" ELBOW TO 3" PIPE'"                                3          0.438      UIT    R-A      RI ll     112          1,2 BG-21-FW3 14   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      UIT    R-A      R1.20     114 BG-02-S056-A   BG-06-02 SHT. 2 4" TEE TO 4" PIPE                                    4          0.531      UT     R-A      R1.20     114 BG-10-FW066    BG-06-10        3" X 2" REDUCER TO 2" PIPE                           2          0.344      UIT    R-A      R1.20     156 BG-2 l-H008    BG-01-21        PIPING SUPPORT                                       3                    VT-3    F-A      FI.10 BG-22-H007     BG-02-22 SHT. 1 PIPING SUPPORT                                       3                    VT-3    F-A      FI.10 BG-02-R016     BG-06-02 SHT. 1 PIPING SUPPORT                                       6                    VT-3    F-A      F1.20 BG- 10-C528    BG-06-10        PIPING SUPPORT                                       2                    VT-3    F-A      F1.20 PBG05A-SUP-3   BG-06-02 SET. 1 CHARGING PUMP A SUPPORT                              6                    VT-3    F-A      FI.40 PBQ05A-SUP-4   BG-06-02 SET. I CHARGING PUMP A SUPPORT                              6                    VT-3    F-A      F1.40 WCRE-30                                             4.1.5 Chemical and Volume Control System (BG)                                             Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   BG-3 SPeriod 3 Examinations
[System: BG Relief Request or Component Name Drawing Number   Component Description                                      Size Thickness NDE Method Category Item   Cal Blo'      ck   Notes BG-24-FW553A   BG-05-24         BBV084 SAFE END TO 2" X 2" X 3/4' TEE                      2       0.344      UT     R-A      RI.11      156           1,2 BG-23-W594A    BG-03-23         2' PIPE TO 2" X 2" X 3/4" TEE                              2       0.344      UT     R-A      RI ll      156           1,2 BG-24-FW554    BG-05-24         2" X 2" X 3/4" TEE TO 2" PIPE                              2       0.344      UT     R-A      R1.20      156 BG-10-F003     BG-06-10         3" X2" REDUCER TO 2" PIPE                                  2       0.344      UT     R-A      R1.20      156 BG-02-S040-A   BG-06-02 SHlT. 2 4" ELBOW TO 4" PIPE                                        4       0.531      UT     R-A      R1.20      114 BG-02-S046-B   BG-06-02 SHlT. 2 4" TEE TO 4" X 3" REDUCER                                  4       0.531      UT     R-A      R1.20      114 BG-22-H008     BG-02-22 SHIT. 1 PIPING SUPPORT                                             3                 VT-3    F-A      FI.10 BG-02-C0 13    BG-06-02 SHT. 1  PIPING SUPPORT                                             8                 VT-3    F-A      F 1.20 BG-02-H007     BG-06-02 SHT. 1  PIPING SUPPORT                                             6                 VT-3    F-A      F1.20 WCRE-30                                                4.1.5 Chemical and Volume Control System (BG)                                                Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.6 Steam Generator Blowdown System (BM)
A. Applicable System Piping and Instrument Drawings
: 1. M-12BMO01-Steam Generator Blowdown System B. Classification of Components Details of the classification of the Steam Generator Blowdown System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
D. Applicable 151 Isometrics and 1SI 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-189-50 series.
: 1. M-189-50BM-01-01 Sheet 1 Steam Generator Blowdown Loop A & D
: 2. M-189-50BM-01-02 Sheet 1 Steam Generator Blowdown Loop B & C WCRE-30                4.1.6 Steam Generator B lowdown System (BM)                            Revision 0 Page 1 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.6 Steam Generator Blowdown System (BM~)
E. Summary of Components Subject To Section XI and Augmented NDElScheduled For Examination Table 1 is a sunmmary 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. P1__    P.22    P_.3      TNTERVAL PIPING WELDS SUBJECT                                             USAR             3.6.2          36        0      0       0                0 TO HELB REQUIREMENTS            __ _   _  _   _  _____           __  _  _  _  _  _   _   _  _ __   _   _ _  __   _ _   _  _ _   _ _  _ _  _    _   _   _  _ _
WCRE-30                                              4.1.6 Steam Generator Blowdown System (BM)                                                 Revision 0 Page 2 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.6 Steam Generator Blowdown System (BM)
F. Augmented IS1 Requirements The following Augmented ISI requirements apply to the Steam Generator Blowdown 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-33 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 XI, 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 RM-SI Program is not applicable to the BM system.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table BM-1 (Period 1 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-30                  4.1.6 Steam Generator Blowdown System (BM)                            Revision 0 Page 3 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.7 Borated Refueling Water System (&sect;BN)
A. Applicable System Piping and Instrument Drawings
: 1. M-12BN0 1-B orated Refueling Water System B. Classification of Components Details of the classification of the Borated Refueling Water System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
D. Applicable ISI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the B orated Refueling Water System. These drawings are part of the M-189-50 series.
1    M-189-50BN-01-01 Sheet 1         Borated Refueling Water Storage Supply
: 2. M-189-50BN-01-01 Sheet 2         Borated Refueling Water Storage Supply
: 3. M-189-50BN-01-01 Sheet 3         Borated Refueling Water Storage Supply WCRE-30                    4.1.7 B orated Refueling Water System (BN)                            Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.7 Borated Refueling Water System (RN)
E.       Summary of 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 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       P1    P__2    P3         INTERVAL PIPING WELDED                   C-C            C3.20               --                         4          1     0       01 ATTACHMENTS PIPING WELDS NOT                  R-A            R1.20               --                        127         0     0       0                0 SUBJECT TO A DAMAGE               Note 1           Note 1 MECHANISM PIPING COMPONENTS                  F-A            F1.20              --                         24          1     2       2                5 SUPPORTS Note 1: See Section H for an explanation of Category R-A and Item R1.XX nomenclature.
WCRE-30                                                   4.1.7 Borated Refueling Water System (BN)                                           Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1o7 Borated Refueling Water System (RN)
F.      Augmented ISI Requirements No Augmented IS1 requirements apply to the Borated Refueling Water System.
G.      System Pressure Testing In accordance with Section XI, IWA-5000 and IWC-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.
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 1 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.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table BN-1 (Period 1 Examinations), Table BN-2 (Period 2 Examinations),
and Table BN-3 (Period 3 Examinations).
WCRE-30                    4.1.7 Borated Refueling Water System (BN)                         Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BN-I
[Period 1 Examinations Relief Request or Component Name Drawing Number  Component Description                                      Size Thickness NDE Method Category Item  Cal Block         Notes BN-01-A001     BN-01-0I SHT. 2 INTEGRAL PIPING ATTACHMENTS                                                   PT     C-C      C3.20 14 BN-01-A001                                                                                                  VT-3    F-A      F1.20 BN-01-01 SHT. 2 PIPING SUPPORT WCRE-30                                              4.1.7 B orated Refueling Water System (BN)                                                 Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BN-2 I eid2Examinations
[System: BN Relief Request or Component Name Drawing Number  Component Description                                      Size Thickness NDE Method Category Item  Cal Block         Notes BN-01 -H003    BN-0l-01 SHT. 1 PIPING SUPPORT                                            24                 VT-3    F-A      F1.20 BN-0OI-C005    BN-01-01 SHT. 2 PIPING SUPPORT                                            24                 VT-3    F-A      F1.20 WCRE-30                                              4.1.7 B orated Refueling Water System (BN)                                                 Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE BN-3 IPeriod 3 Examinations L2Systm: BNJ 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                                                  8VT-3                 F-A      F 1.20 BN-0 l-R001    BN-01-01 SILT. 3 PIPING SUPPORT                                             12                 VT-3    F-A      FI1.20 WCRE-30                                               4.1.7 B orated 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- 12EFO01-Essential Service Water System
: 2. M-12EF02-Essential Service Water System
: 3. M-K2EF0 1-Essential Service Water System
: 4. M-K2EFO3-Essential Service Water System B. Classification of Components 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 4".
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 4".
B. Applicable ISI Isometrics and lSI 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-189-50EF-01-01            Sheet 1  Essential Service Water "A" Train Supply
: 2.        M-189-50EF-01-01            Sheet 2  Essential Service Water "A" Train Supply
: 3.        M-189-50EF-01-02            Sheet 1  Essential Service Water "A" Train Supply
: 4.         M-189-50EF-01-02            Sheet 2  Essential Service Water "A" Train Supply
: 5.         M-189-50EF-01-03            Sheet 1  Essential Service Water "A" Train Return
: 6.        M-189-50EF-01-03            Sheet 2  Essential Service Water "A" Train Return
: 7.        M-189-50EF-01-07            Sheet 1  Essential Service Water "A" Train Return
: 8.        M-189-50EF-01-08            Sheet 1  Essential Service Water "A" Train Supply
: 9.        M-189-50EF-01-09            Sheet 1  Essential Service Water Containment Cooling "A" Train Supply
: 10.       M-189-50EF-01-10            Sheet 1 Essential Service Water Containment Cooling "A" Train Return
: 11.       M-1 89-50EF-02-0 1          Sheet 1 Essential Service Water "B" Train Supply
: 12.       M-1 89-5OEF-02-0 1          Sheet 2 Essential Service Water "B" Train Supply
: 13.       M-1 89-5OEF-02-0 1          Sheet 3 Essential Service Water "B" Train Return
: 14.       M- 189-5OEF-02-04           Sheet 1 Essential Service Water "B" Train Supply
: 15.       M-1 89-5OEF-02-05           Sheet 1 Essential Service Water "B" Train Return
: 16.       M-1 89-50EF-02-05           Sheet 2 Essential Service Water "B" Train Return
: 17.       M-1 89-5OEF-02-06           Sheet 1 Essential Service Water "B" Train Supply
: 18.       M-1 89-5OEF-02-08           Sheet 1 Essential Service Water "B" Train Supply
: 19.       M-189-5OEF-02-08            Sheet 2 Essential Service Water "B" Train Supply
: 20.       M-189-5OEF-02-09            Sheet 1 Essential Service Water Containment Cooling "B" Train Supply
: 21.       M-189-50EF-02-10            Sheet 1 Essential Service Water Containment Cooling "B" Train Return
: 22.       M-189-50EF-03-0 1           Train A & B Underground Supply and Return Piping In Vaults WCRE-30                             WCRE-304.1.8 Essential Service Water System (EF)                           Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.8 Essential Service Water System (EF)
E.       Summary of 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 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     P1    P._2     P_33       INTERVAL PIPING WELDED                 C-C            C3.20                --                           4       0      1       01 ATTACHMENTS VESSEL WELDED                 D-A             D1.10               --                            41             1       0                 2 ATTACHMENTS PIPING WELDED                D-A             D1.20               -                            83       4      3       3                10 ATTACHMENTS PUMP WELDED                  D-A             D 1.30               --                           2       0      0       1                 1 ATTACHMENTS PIPING COMPONENT                F-A             F1.20                --                           3       0      1      0                  1 SUPPORTS PIPING COMPONENT                 F-A            F1.30                --                         258       9      9      11                29 SUPPORTS EQUIPMENT SUPPORTS                F-A             F1.40               --                           61              2      0                  3 (Other Than Piping)___                                              ____      _____
PIPING WELDS NOT                R-A             RI.20               --                           26       0      0      0                  0 SUBJECT TO A DAMAGE               Note 1           Note I MECHANISM Note 1: See Section H for an explanation of Category R-A and Item R1.XX nomenclature.
WCRE-30                                                       4.1.8 Essential Service Water System (EF)                                           Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.8 Essential Service Water System (EF)
F. Augmented ISI Requirements No Augmented 1SI requirements apply to the Essential Service Water System.
G. System Pressure Testing 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.
In accordance with Section XI, IWA-5000 and IWD-5000, the Class 3 pressure retaining components within the Essential Service Water System will receive a system leakage test per IWD-5 220 every 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 1 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-l1. No welds in the EF system were selected for examination in the RI-ISI program.
I. Components and Component Supports Selected/Scheduled For Examinntion The components and component supports selected for examination during Interval 4 are included in Table EF-1 (Period 1 Examinations), Table EF-2 (Period 2 Examinations),
and Table EF-3 (Period 3 Examinations).
WCRE-30                   4.1.8 Essential Service Water System (EF)                         Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL IS1 PROGRAM PLAN TABLE EF-1 SPeriod 1 Examinations
[System:  EF Relief Request or Cal Block          Notes Component Name    Drawing Number   Component Description                               Size  Thickness    NDE Method Category  Item FEF02A-SUPPORT- 1 EF-01-01 SHT. 1  VESSEL INTEGRAL ATTACHMENTS                         30                    VT-I    D-A      DI.10 EF-0 1-C004       EF-01-03 SHT. 2  PIPING INTEGRAL ATTACHMENTS                         30                    VT-I    D-A      D1.20 EF-01-C005        EF-02-01 SHT. 2  PIPING INTEGRAL ATTACHMENTS                         30                    VT-i    D-A      D1.20 EF-01-C005        EF-02-01 SHT. 2  PIPING SUPPORT                                      30                    VT-3    F-A      F 1.30 EF-01-C004        EF-01-03 SHT. 2  PIPING SUPPORT                                      30                    VT-3    F-A      F 1.30 EF-07-C003        EF-01-08         PIPING SUPPORT                                      8                     VT-3    F-A      F 1.30 K-EF-1 1-H007     EF-02-01 SHT. 1  PIPING SUPPORT                                      30                    VT-3    F-A      F 1.30 EF-05-HOI11       EF-02-05 SHT. 1  PIPING SUPPORT                                      24                    VT-3    F-A      FI1.30 EF-04-R009        EF-02-06         PIPING SUPPORT                                      14                    VT-3    F-A      F 1.30 EF-0 8-CO013      EF-02-08 SHT. 1  PIPING SUPPORT                                      8                     VT-3    F-A      F1.30 EF-203-H005       EF-03-0 1 SHT. 1 PIPING SUPPORT                                      30                    VT-3    F-A      F1.30 EF-203-H004       EF-03-0 1 SHT. 1 PIPING SUPPORT                                      30                    VT-3    F-A      FI.30 EF-203-H005       EF-03-01 SI-T.I  PIPING INTEGRAL ATTACHMENTS                         30                            D-A      D 1.20 VT-I EF-203-H004       EF-03-01 SHT.I   PIPING INTEGRAL ATTACHMENTS                         30                            D-A      D 1.20 PEF1lA-SUPPORT- 1 EF-01-01 SHT. 1  ESW PUMP A SUPPORT                                  30                    VT-3    F-A      F1.40 WCRE-30                                                         4.1.8 Essential Service Water System (EF)                                           Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EF-2 IPeriod 2 Examinations ISystem: EF      ]
Relief Request or Cal Block         Notes Component Name    Drawing Number   Component Description                               Size  Thickness  NDE Method Category Item GN-01I-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. I  PIPING INTEGRAL ATTACHMENTS                         24                  VT-I    D-A      D1.20 EF-06-A0 14       EF-02-06         PIPINiG INTEGRAL ATTACHMENTS                         8                  VT-I    D-A      D1,20 EF-203-H01 8      EF-03-01 SHT.I   PIPING INTEGRAL ATTACHMENTS                         30                  VT-I    D-A      D01.20 EF-02-R017        EF-01-09         PIPING SUPPORT                                       14                 VT-3    F-A      F1.20 EF-06-C026        EF-O1-02 SHT. 2  PIPING SUPPORT                                       8                  VT-3    F-A      F1.30 EF-03-C004        EF-01-03 SHT, l  PIPING SUPPORT                                      24                  VT-3    F-A      F1,30 EF-03-H004        EF-01-03 SHT. 2  PIPING SUPPORT                                       16                 VT-3    F-A      FI.30 EF-05-R005        EF-02-05 SHT. 1  PIPING SUPPORT                                      24                  VT-3    F-A      F1.30 EF-06-A014        EF-02-06         PIPING SUPPORT                                       8                  VT-3    F-A      F1.30 EF-203-H01 8      EF-03-01 SHT,1   PIPING SUPPORT                                       30                 VT-3    F-A      F1.30 EF-01-C001        EF-01-01 SHT.2   PIPING SUPPORT                                       30                 VT-3    F-A      F1.30 EF-01-C007        EP-02-01 SHT.2   PIPING SUPPORT                                       30                 VT-3    F-A      F1,30 EF-08-C002        EF-01-08         PIPING SUPPORT                                       8                  VT-3    F-A      F1.30 FEF02A-SUPPORT- 1 EF-01-01 SHT. 1  VESSEL SUPPORT                                       30                 VT-3    F-A      F1.40 FEF02A-SUPPORT-2  EF-01-01 SILT. 1 VESSEL SUPPORT                                       30                 VT-3    F-A      F1.40 WCRE-30                                                         4.1.8 Essential Service Water System (EF)                                         Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EF-3
[Period 3 Examinations    ]
[System:   EF Relief Request Component Name                                                                              Size Thickness NDE Method Category Item   Cal Block     or Notes Drawing Number    Component Description EF-03-R021         EF-01-03 SHT. 1   PIPING INTEGRAL ATTACH-MENTS                           24                VT-I    D-A      DI.20 EF-03-C016         EF-01 -03 SHT. 2  PIPING INTEGRAL ATTACHMENTS                            8                         D-A      D1.20 VT-i EF-203-H024        EF-03-0I SHT.I    PIPING INTEGRAL ATTACI-MvENTS                          24                        D-A      D1.20 VT-1 PEF01 A-SUPIORT- 1 EF-01-01 SHT. 1   ESW PUMP INTEGRAL ATTACHMENT                           30                        D-A      D1.30 VT-3 K-EF-l 1l-RO0l     EF-01-01 SHT. 1   PIPING SUPPORT                                         30                        F-A      F 1.30 VT-3 K-EF-1 i-R003      EF-01-01 SHT. I   PIPING SUPPORT                                         30                        F-A      F!1.30 VT-3 K-EF- I 1 -R00OS   EF-01-01 SHT. I   PIPING SUPPORT                                         30                        F-A      F1.30 VTr-3 EF-01 -C002        EF-0l-01 SHT. 2   PIPING SUPPORT                                         30                        F-A      F1.30 EF-02-A0 10        EF-01-01 SI-IT. 2 PIPING SUPPORT                                         18                VT-3    F-A      F1.30 EF-03-R021         EF-01-03 SHT. 1   PIPING SUPPORT                                         24                VT-3    F-A      F1.30 EF-03-C016         EF-01-03 SHT. 2   PIPING SUPPORT                                         8                 VT-3    F-A      F 1.30 EF-07-C009         EF-01-07          PIPING SUPPORT                                         8                 VT-3    F-A      F1.30 EF-05-R013         EF-02-05 SHT. 1   PIPING SUPPORT                                         24                VT-3    F-A      F 1.30 EF-06-H001         EF-02-06          PIPING SUPPORT                                         8                 VTr-3   F-A      F1.30 EF-203-H024        EF-03-0 1 SHT. 1  PIPING SUPPORT                                         24                        F-A      F1.30 WCRE-30                                                        4.1.8 Essential Service Water System (EF)                                          Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.9 Component Cooling Water System (EG)
A. Applicable System Piping and Instrument Drawings
: 1. M-12EG0 1-Component Cooling Water System
: 2. M-12EG02-Component Cooling Water System
: 3. M-12EG03-Component Cooling Water System B. Classification of Components Details of the classification of the Component Cooling Water System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
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 Cooling Water System. These drawings are part of the M-189-50 series.
: 1.      M-189-50EG-01-01           Sheet 1      Component Cooling Water "A" Train CCW Heat Exchanger
: 2.       M- 189-50EG-01-02          Sheet 1      Component Cooling Water "A" Train Supply
: 3.       M- 189-50EG-01-02          Sheet 2      Component Cooling Water "A" Train Return
: 4.       M-1 89-50EG-02-03          Sheet 1      Component Cooling Water "B" Train CCW Heat Exchanger
: 5.       M-1 89-50EG-02-03          Sheet 2      Component Cooling Water "B" Train
: 6.       M- 189-50EG-02-05          Sheet 1      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 1      Component Cooling Water Common Header
: 9.      M- 189-50EG-03-07          Sheet 1      Component Cooling Water Common Header
: 10. M- 189-50EG-04-01          Sheet 1      Component Cooling Water RHR Heat Exchanger Supply
: 11. M- 1 89-50EG-04-0 1        Sheet 2      Component Cooling Water RHR Heat Exchanger Return
: 12. M-189-50EG-05-06           Sheet 1      Component Cooling Water Letdown Heat Exchanger Supply
: 13. M- 189-50EG-05-06          Sheet 2      Component Cooling Water Letdown Heat Exchanger Return WCRE-30                            4.1.9 Component Cooling Water System (EG)                      Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.9 Component Cooling Water System (EG)
E. Summary of 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 1SI 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        P1    P2       P3         INTERVAL VESSEL WELDED               D-A             Dl.10               --                        10          4      2       0                 6 ATTACHMENTS PIPING WELDED               D-A             D 1.20              --                       47           2     2        2                 6 ATTACHMENTS PIPING COMPONENT              F-A             F1.30               --                       209          5     11       8                24 SUPPORTS EQUIPMENT SUPPORTS              F-A             F1.40               --                       20           4     2       4                 10 (OTHER THAN PIPING)
WCRE-30                                                4.1.9 Component Cooling Water System (EG)                                               Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.9 Component Cooling Water System (EG)
F. Augmented ISI Requirements No Augmented ISI requirements apply to the Component Cooling Water System.
G. System Pressure Testing In accordance with Section XI, 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-5220 every 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 EG system.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table EG-1 (Period 1 Examinations), Table EG-2 (Period 2 Examinations),
and Table EG-3 (Period 3 Examinations).
WCRE-30                  4.1.9 Component Cooling Water System (EG)                          Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EG-1 IPeriod 1 Examinations Component Name Drawing Number  Component Description                                  Size Thickness NDE Method Category Item   Relief Request    Notes EEGO1lA-SUP-1  EG-01-0 l       CCW HX INTEGRAL ATTACHMENT                                               VT-i    D-A      DI.10 EEGOIA-SUP-2   EG-01-01        CCW HX INTEGRAL ATTACHMENT                                               VT-I    D-A EEG01A-SUP-3   EG-01-01        CCW HX INTEGRAL ATTACHMENT                                               VT-i    D-A EEGO1A-SUP-4   EG-01-O1        CCW H-X INTEGRAL ATTACHMENT                                              VT-i    D-A EG-0i-R023     EG-01-01        PIPING INTEGRAL ATTACHMENTS                                              VT-i    D-A      D1.20 20 EG-02-A005     EG-01-02 SHT. 1 PIPING INTEGRAL ATTACHMENT                             12                VT-I    D-A      D1.20 EG-01i-R023    EG-01-01        PIPING SUPPORT                                         20                VT-3    F-A      FI.30 EG-02-A005     EG-01-02 SHT. 1 PIPING SUPPORT                                         12                VT-3    F-A      F1.30 EU-I 8-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      F 1.30 EG-06-H002     EG-03-06        PIPING SUPPORT                                         12                VT-3    F-A      F1.30 EEG01IA-SUP-i  EG-01-01        CCW H-X SUPPORT                                                          VT-3    F-A      Ft1.40 EEGO 1A-SUP-2  EG-01-01        CCW H-X SUPPORT                                                          VT-3    F-A      Ft1.40 EEG01A-SUP-3   EG-01-01        CCW f-IX SUPPORT                                                         VT-3    F-A      F 1.40 EEG01 A-SUP-4  EG-O1-01        CCW HX SUPPORT                                                           VT-3    F-A      Ft.40 WCRE-30                                               4.1.9 Component Cooling Water System (EG)                                                Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   EG-2 F  eiod 2ExaminationsI
[System:  EG Component Name    Drawing Number   Component Description                               Size  Thickness NDE Method Category Item   Relief Request    Notes EBGO01-SUPPORT-i1 EG-05-06         LETDOWN HX INTEGRAL ATTACHMENT                                         VT-i    D-A EBG01I -SUPPORT-2 EG-05-06         LETDOWN FIX INTEGRAL ATTACHMENT                                        VT-i    D-A      DI.10 EG-04-A001        EG-04-01 SHT. 2  PIPING INTEGRAL ATTACHMENTS                         18                 VT-i    D-A      D1.20 EG-06-C016        EG-05-06 SHT. 1  PIPING INTEGRAL ATT7ACHMENT                         6                  VT-i    D-A      D1.20 EG-1 8-COO01      EG-01-02 SI-T. 1 PIPING SUPPORT                                      12                 VT-3    F-A      F 1.30 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-H007        EG-04-0I SHT. 1  PIPING SUPPORT                                      18                 VT-3    F-A      F 1.30 EG-04-A001        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      Ft1.30 EG-06-C016        EG-05-06 SHT. 1  PIPING SUPPORT                                      6                  VT-3    F-A      F1.30 EG-03-R01 8       EG-02-03 SHT. 1  PIPING SUPPORT                                      20                 VT-3    F-A      F 1.30 EG-01-R03i        EG-04-01 SHT. 1  PIPING SUPPORT                                      18                 VT-3    F-A      F 1.30 EG-01-R026        EG-01-01         PIPING SUPPORT                                      20                 VT-3    F-A      F 1.30 EG-03-R019        EG-02-03 SHT. 2  PIPING SUPPORT                                      20                         F-A      F1.30 EBG0 1-SUPPORT-i1 EG-05-06         LETDOWN HIX SUPPORT                                                    VT-3    F-A      F1.40 EBG01-SUPPORT-2   EG-05-06         LETDOWN HIX SUPPORT                                                    VT-3    F-A      F1.40 WCRE-30                                                   4.1.9 Component Cooling Water System (EG)                                              Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1ST PROGRAM PLAN TABLE EG- 3 I eid3Examinations
[System:  EG Component Name Drawing Number    Component Descrip~tion                                 Size Thickness NDE Method Cateqory Item   Relief Request    Notes EG-07-C021     EG-03-07          PIPING INTEGRAL ATTACHMENT                             12                VT-i    D-A      DI1.20 EG-01-C001     EG-01-01          PIPING INTEGRAL ATTACHMENTS                            20                VT-i1   D-A      D1.20 EG-02-1-005    EG-0l-02 SHlT. 1  PIPING SUPPORT                                         12                VT-3    F-A      F1.30 EG-1 8-H-003   EG-0 1-02 SHT. 2  PIPING SUPPORT                                         12                VT-3    F-A      FL1.30 EG-03-H-005    EG-02-03 SHlT. 2  PIPING SUPPORT                                         20                VT-3    F-A      FI.30 EG-05-C001     EG-02-05 SHlT. 1  PIPING SUPPORT                                         12                VT-3    F-A      FI.30 EG- 18-H006    EG-02-05 SHT. 1   PIPING SUPPORT                                         12                VT-3    F-A      F1.30 EG-07-C021     EG-03-07          PIPING SUPPORT                                         12                VT-3    F-A      F1.30 EG-01-C001     EG-01-01          PIPING SUPPORT                                         20                VT-3    F-A      F1.30 EG-07-R026     EG-03-07          PIPING SUPPORT                                         12                VT-3    F-A      F1.30 PEG01IA-SUP-I  EG-01-01          PUMP SUPPORT                                           IS                VT-3    F-A      F1.40 EEC0 IA-SUP-I1 EG-01-02 SHlT. 1  FUEL POOL COOLING HX SUPPORT                                             VT-3    F-A      FI.40 EEC01A-SUP-2   EU-0 1-02 SHlT. 1 FUEL POOL COOLING HX SUPPORT                                             VT-3    F-A      F1.40 EEC01 A-SUP-3  EG-01-02 SHT. 1   FUEL POOL COOLING U-X SUPPORT                                            VT-3    F-A      F1.40 WCRE-30                                                    4.1.9 Component Cooling Water System (EG)                                            Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.10 Residual Heat Removal System (&sect;EJ)
A. Applicable System Piping and Instrument Drawings
: 1. M- 12EJ0 1-Residual Heat Removal System B. Classification of Components Details of the classification of the Residual Heat Removal System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
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- 189-50EJ-01-01           Sheet 1      Residual Heat Removal "A" Train RHR Pump Suction
: 2.        M-189-50EJ-01-01            Sheet 2      Residual Heat Removal "A" Train RHR Pump Discharge
: 3.        M-1 89-50EJ-0 1-01          Sheet 3      Residual Heat Removal "A" Train RHR Pump Suction
: 4.        M-189-50EJ-01-01            Sheet 4      Residual Heat Removal "A" Train RHR Pump Discharge to Safety Injection
: 5.        M-1 89-50E J-01-01          Sheet 5      Residual Heat Removal Return to Refueling Water Storage Tank
: 6.        M- 189-50E J-01-04          Sheet 1      Residual Heat Removal "A" Train RHR Pump Suction
: 7.        M-1 89-5OEJ-02-02           Sheet 1      Residual Heat Removal "B" Train RHR Pump Suction
: 8.        M-1 89-50EJ-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-1 89-5OEJ-02-02           Sheet 4      Residual Heat Removal "B" Train RHR pump Discharge to Safety Injection
: 11.       M- 189-50EJ-02-02           Sheet 5      Residual Heat Removal "B" Train RHR Pump Discharge to Safety Injection
: 12.       M-1 89-50EJ-02-04           Sheet 1      Residual Heat Removal "B" Train RHR Pump Suction
: 13.       M-l189-50EJ-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 Discharge to Safety Injection Loop No. 2 & 3
: 15.       M-1 89-501S1-EEJ01A         Sheet 1      RHR Heat Exchanger "A" EEJO01A
: 16.       M-1 89-501SI-EEJ01B         Sheet 1      RHR Heat Exchanger "B" EEJ01B
: 17.       M-1 89-501SI-PUMPS          Sheet 1      ISI Pumps WCRE-30                           4.1.10 Residual Heat Removal System (EJ)                            Revision 0 Page 1 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.10 Residual Heat Removal System (Li)
E.      Summary of Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table 1 is a sunmmary 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 1SI 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     P1__    P__2    P.33        INTERVAL PRESSURE RETAINING               B-G-2           B7.70               --                           6      *        *      *         *See Paragraph I, BOLTING-VALVES                                                                                                                       Notes 1 & 3 VALVE BODY                   B-M-2          B 12.50              --                           6      *        *      *         *See Paragraph I, EXCEEDING NPS 4                                                                                                                      Notes 2 & 3 PRESSURE RETAINING                C-A            CI.10               --                           2      0        0      0                Note 2 VESSEL WELDS-SHELL PRESSURE RETAINING                C-A           CI1.20               --                           2      0        0      0                Note 2 VESSEL WELDS-CIRC.
PRESSURE RETAINING                C-B            C2.33               --                           4      0        0      0                Note 2 NOZZLE WELDS-VES.
VESSEL WELDED                  C-C            C3.10               --                           2      0        0      1                  1 ATTACHMENTS PIPING WELDED                  C-C            C3.20               --                         43       2        1      2                  5 ATTACHMENTS PUMP WELDED                   C-C            C3.30               --                           6      0        0      11 ATTACHMENTS VESSEL WELDED                  D-A           DI.10                --                          10      0        3      2                  5 ATTACHMENTS PIPING COMPONENTS                 F-A            FI.10--                                         13       1       2      2                  5 SUPPORTS PIPING COMPONENTS                 F-A            F1.20               --                         131      7        7      9                 23 SUPPORTS WCRE-30                                                     4.1.10 Residual Heat Removal System (EJ)                                               Revision 0 Page 2 of 14

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

==SUMMARY==
AND SCHEDULE COMPONENT OR ITEM DESCRIPTION IJCATEGORY CODE       ICODE             1 AUG. 1AUG 1TOTAL IN [ P1 ITEM NO. jCATEGORY jITEM NO. JSYSTEM EXAMS BY PERIOD & INTERVAL P2     P3        INTERVAL EQUIPMENT SUPPORTS                 F-A              F1.40              -              -20                      3     4      3              10 (OTHER TH-AN PIPING)____________
PIPING WELDS SUBJECT                R-A              R1.11                                          19         0      0      66 TO THERMAL FATIGUE                 Note 1            Note 1 PIPING WELDS NOT                 R-A              R1.20              --                         504         14     15    18             47 SUBJECT TO A DAMAGE                Note 1            Note 1 MECHANISM__                  _   _  _    __    _  _  _     _____          _____        ___       __    __
RHR MIXING TEE                                                 MRP- 192       MRP192           10         0      10     0              10 WELDS Note 1: See Section H for an explanation of Category R-A and Item R1 .XX nomenclature.
Note 2: Code Case N-706-1 is utilized for the examination of these components. These components are in the scope of STS PE-043A/STS PE-043C system leakage tests that are performed every inspection period as required by Examination Category C-H.
WCRE-30                                                       4.1.10 Residual Heat Removal System (E J)                                          Revision 0 Page 3 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.10 Residual Heat Removal System (EJ)
F. Augmented ISI Requirements The following Augmented 1S1 requirements apply to the Residual Heat Removal System:
: 1. MRP-192. Material Reliability Program: Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants- This document provides recommendations for the evaluation and inspection of locations downstream of RHR mixing tees that may be susceptible to thermal fatigue. Downstream welds within four pipe diameters of the mixing tee should be examined. MRP letter 2015-0 19 added the recommendation that the welds of the mixing tee to the upstream piping should also be examined. The WCGS Residual Heat Removal weld locations determined to be affected by this have been identified with Category = MRP-192 and Item Number         = MRPI192. These locations require a volumetric examination every 6 years. These examinations are to be performed in accordance with the recommendations of MRP- 192.
G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWB-5000, the Class 1 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.
In accordance with Section Xl, 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 Pressure Testing are listed in Table 4.2.1 H. Risk Informed ISI Program A Risk Informed Inservice Inspection (RI-IST) Program has been applied to Code Class 1 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-l1, 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-1 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 through 4-4 of TR-i 12657 Rev. B-A.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table EJ-1 (Period 1 Examinations), Table EJ-2 (Period 2 Examinations), and Table EJ-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. 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 Category B-G-2, Notes 1 and 2.
: 2. Examination of the valve internal surface is required only when a valve is disassembled for maintenance or repair. The 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 method and that perform a similar function in the system. Examination may be alternatively performed on another valve within the group. Ifra valve has not been disassembled, examination is deferrable to subsequent periods. (Reference PIR 97-2539)
WCRE-30                             4.1.10 Residual Heat Removal System (E J)                              Revision 0 Page 4 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN
: 3. WCNOC procedures require that the ISI Coordinator be informed whenever a Class 1 component is disassembled for repair or maintenance and that the 1S1 Coordinator specify if a VT-i and/or VT-3 exam is required. Whenever a component is required to have a B-G-2 or B-M-2 exam performed, the 1SI Coordinator shall revise the applicable Table El-i, EJ-2, or EJ-3 and Table i to reflect the component being examined. Reference procedures AP i6A-003, ASME Section XI Repair and Replacement Program; and AI i6C-007, Work Order Planning.
: 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 Thermal Fatigue identified as the degradation mechanism.
: 6. These welds have been selected in accordance with the recommendations of MRP-192 and MRP letter 20i5-019. See Paragraph F above. The examinations of these welds are to include any/all associated long seam welds.
: 7. Weld end prep is not per MS-6 standards and there is no counter bore. Reference CCP 013539 Rev 2.
WCRE-30                   4.1.10 Residual Heat Removal System (El)                           Revision 0 Page 5 of i4

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EJ-1
[Period 1 Examinations ISystem:  EJ Relief Request or r*, ..... Cn* hl,,*b.*=                                                           C-.;-     Th;-.U,,n.*   Ni-nE hA.-hnfk   fl.,+,,,,,-
'.UllllJ.llI lll. LIdlIIU  l.JlIdWlIl* I'*IUr'IL) F
* II[U Ll, .u*SUIJ.I                                  ,uii1puiiI  [ielultiuii I'I.,L   UI~.*I.I IU  +,*~;      U V  I*II  x..l   lkI            *U+
EJ-04-A002                EJ-01-01 SHT. 4           PIPING INTEGRAL ATT'ACHMENTS                           6                               PT        C-C             C3.20 EJ-04-R008                EJ-02-04 SHT. 3           PIPING INTEGRAL ATTACHMENTS                            6                               PT        C-C             C3.20 EJ-04-C021                EJ-01-04                  PIPING SUPPORT                                         12                             VT-3       F-A             FI.10 EJ-0t -HO013              EJ-O01-01 SHIT. 3         PIPING SUPPORT                                         10                             VT-3       F-A             F 1.20 E J-01 -H0 14             EJ-01-01 SHT. 4           PIPING SUPPORT                                         10                             VT-3       F-A             F 1.20 EJ-04-A002                EJ-01-O1 SLIT. 4          PIPING SUPPORT                                         6                              VT-.3      F-A             F 1.20 EJ-04-C013                EJ-01-OI SHT. 4           PIPING SUPPORT                                         6                              VT-3       F-A             F 1.20 EJ-03-C007                EJ-02-02 SILT. 3          PIPING SUPPORT                                         8                              VT-3       F-A             F 1.20 EJ-03-RO15                E J-02-02 SHT. 3          PIPING SUPPORT                                         8                              VT-3       F-A             F 1.20 EJ-04-R008                E J-02-04 SHIT. 3         PIPING SUPPORT                                         6                              VT-3       F-A             Fl1.20 PEJ01IA-SUP-1             EJ-01-01 S1HT. 2          RHR PUMP A SUPPORT                                     8               0.322          VT-3       F-A             F1.40 PEJ01 A-SUP-2             EJ-01-0I SI-T. 2          RHR PUMP A SUPPORT                                     8               0.322          VT-3       F-A             FI.40 PEJ01 A-SUP-3             EJ-01-01 SHT. 2           RHR PUMP A SUPPORT                                     8               0.322          VT-3       F-A             Fl1.40 EJ-04-S0 16-B             E J-02-04 SI-IT. I        12" PIPE TO 12' ELBOW                                  12              1.125           UTl       R-A             R1.20       126 WCRE-30                                                                     4.1.10 Residual Heat Removal System (EJ)                                                                           Revision 0 Page 6 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL IS1 PROGRAM PLAN TABLE EJ-1 IPeriod 1 Examinations ISystem: EJ Relief Request or C'. n nnn~nmt NIknm            I*r*l^llnn   Ms imhor   C'nmnnn~n.+f lnrin+.nn, Size Thickness  NDE Method Categjory  Item  Cal Block          Notes
..... F ......................           I1 .........  ..... r ............. r .....                                                                   m   i EJ-01-FW342                    EJ-01-01 SHLT. 4        10" ELBOW TO 10" PIPE                                           10       0.365      UT     R-A        RI.20     204          4 EJ-01-FW343                    EJ-01-01 SHT. 4         10" PIPE TO 10" ELBOW                                           10       0.365      UT     R-A        RI.20     204 EJ-01-S025-B                   EJ-01-01 SHT. 5         10" PIPE TO 10" ELBOW                                           10       0.365      UT     R-A        R1.20     204 EJ-04-FW31 2                   EJ-01-01 SHT. 4        6' PIPE TO 10" X 10' X 6' TEE                                    6        0.7 19     UT     R.-A       R1.20     117 E J-01 -S025-C                 EJ-01-01 SHT. 5         10' ELBOW TO 10" PIPE                                           10       0.365      UT     R-A        R1.20     204 EJ-02-FW339                    EJ-02-02 SHT. 2         10" X 8" REDUCER TO 10" PIPE                                     10      0.365      UT     R-A        R1.20     204 EJ-02-S034-C                   EJ-02-02 SHT. 4         10" PIPE TO 10" ELBOW                                            10      0.365      UT     R-A        R1.20     204 EJ-02-S034-D                   E J-02-02 SHT. 4       10" ELBOW TO 10" PIPE                                             10    0.365        UT     R-A        R1.20     204 EJ-04-S025-B                   EJ-01-0l SHT. 4         10" X 10" X 6" TO 10" PIPE                                       10                 UT     R-A        R1.20     122 012 EJ-01-S016-B                   EJ-01-01 SHT. 3         8" PIPE TO 8" ELBOW                                                                 UT     R-A        RI.20     203 0.322 E J-01 -SO016-C                EJ-0l-01 SHT. 3         8" ELBOW TO 8" PIPE                                             8                   UT     R-A        R1.20     203 0.322 EJ-03-S003-F                   EJ-02-02 SiHT. 3        8' ELBOW TO 8" PIPE                                             8                   UT     R-A        R1.20     203 0.322 EJ-03-S003-H                   E J-02-02 SLIT. 3       8" ELBOW TO 8" PIPE                                                                 UT     R.-A       R1.20     203 WCRE-30                                                                                4.1.1l0 Residual Heat Removal System (E J)                                                  Revision 0 Page 7 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE E J-2
[Period 2 Examinations Relief Request or Cal Block         Notes Component Name     Drawing Number     Component Description                                  Size Thickness NDE Method Category Item EJ-03-R006         E J-02-02 SHT. 3   PIPING INTEGRAL ATTACHMENT                             8                  PT     C-C      C3.20 EEJ01 A-SUJPPORT-3 ISI-EEJ01A SliT. 1 SUPPORT LUG TO SHELL WELD                                                VT-1    D-A      DI.10 EEJ01 A-SUPPORT-4  ISI-EEJ01A SHT. 1 SUPPORT LUG TO SHELL WELD                                                 VT-i    D-A      DI.10 EEJ01 A-SUPPORT-5  ISI-EEJ01A SHT. 1 SUPPORT LUG TO HEAD WELD (HEAD)                                           VT-1    D-A      DI.10 EJ-04-R01 8        E J-01-04          PIPING SUPPORT                                                           VT-3    F-A      F1.10 12 EJ-04-R012         E J-02-04 SilT. 1  PIPING SUPPORT                                         12                VT-3    F-A      Fi.1 EJ-01l-H001        EJ-01-01 SLIT. 1   PIPING SUPPORT                                         14                VT-3    F-A      F1.20 EJ-01I-R029        EJ-0 1-01 SHT. 4   PIPING SUPPORT                                         10                VT-3    F-A      FI1.20 EJ-04-H002         EJ-01-01 SHAT. 4   PIPING SUPPORT                                         10                VT-3    F-A      F1.20 EJ-02-R027         E J-02-02 SHT. 2   PIPING SUPPORT                                         10                VT-3    F-A      Fl1.20 EJ-03-R005         EJ-02-02 SHT. 3    PIPING SUPPORT                                         8                 VT-3    F-A      F1.20 EJ-03-R006         EJ-02-02 SHiT. 3   PIPING SUPPORT                                         8                 VT-3    F-A      F1.20 EJ-02-R012         E J-02-04 SHT. 1   PIPING SUPPORT                                          12               VT-3    F-A      F1.20 EEJ01 A-SUPPORT-3  ISI-EEJ01A SHlT. 1 RHR H-X SUPPORT                                                          VT-3    F-A      F1.40 WCRE-30                                                       4.1.10 Residual Heat Removal System (EJ)                                                 Revision 0 Page 8 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL IS1 PROGRAM PLAN TABLE E J-2 SPeriod 2 Examinations
[System: EJ Relief Request or Size Thickness NDE Method Category Item   Cal Block          Notes Component Name    Drawing Number    Component Description EEJ01IA-SUPPORT-4 ISI-EEJ01A SHT. I RHR H-X SUPPORT                                                              VT-3    F-A      F1.40 EEJ01lA-SUPPORT-5 ISI-EEJ01A SHT. I RHR HX SUPPORT                                                               VT-3    F-A      F1.40 PEJ01IA-SUP-4     EJ-01-01 SHIT. 2  RHR PUMP A SUPPORT                                                           VT-3    F-A      F1.40 EJ-04-FO34        EJ-01-04          12" PIPE TO 12' ELBOW                                       12     1.125      UT     R-A      RI.20      126          4 EJ-02-S008-B      EJ-02-02 SHT. I   14" ELBOW TO 14" PIPE                                       14     0.438      UT     R-A      R1.20      192          4 EJ-02-FW3 17      EJ-02-04 SHT. 1   12" ELBOW TO 12" PIPE                                       12     0.375      UT     R-A      RI .20     183          4 EJ-02-S00 1-C     EJ-02-04 SHT. 1   12" PIPE TO 12" ELBOW                                       12     0.375      UT     R-A      R1.20      183          4 EJ-04-F01 9       EJ-02-04 SHT. I   12" PIPE TO 12" PIPE                                        12      0.5       UT     R-A      R1.20      128          4 EJ-0 1-SO018-B    EJ-01-01 SHiT. 3  10" X 10" X 10" TEE TO 10" PIPE                             10     0.365      UT     R-A      RI.20      204          4 EJ-0 1-SO018-C    EJI-01-O1 SHT. 3  10" PIPE TO 10" X 8" REDUCER                                10     0.365      UT     R-A      RI.20      204          4 EJ-01-S024-D      EJ-01-01 SHT. 4   10" PIPE TO 10" TEE                                          10    0.365      UT     R-A      R1.20      204          4 E J-0 1-S024-F    EJ-01-01 SHT. 4   10" TEE TO 10" PIPE                                          10    0.365      UT     R-A      R1.20      204          4 EJ-02-F050        EJ-02-02 SHIT. 5  10" PIPE TO 10" ELBOW                                        10    0.365      UT     R-A      R1.20      204           4 EJ-02-S022-B      EJ-02-02 SILT. 3  10" PIPE TO 10" X 10" X 8" TEE                               10    0.365      UT     R-A      R1.20      204           4 WCRE-30                                                         4.1.10 Residual Heat Removal System (EJ)                                                 Revision 0 Page 9 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   E J-2
[ Peiod 2Examinations SSystem: EJ Relief Request or Drawing Number   Component Description                                    Size  Thickness NDE Method Category  Item    Cal Block          Notes Component Name EJ-02-S022-D    E J-02-02 SHT. 3  10" X 10" X 8' TEE TO 10' PIPE                                     0.365     UT     R-A       RI.20       204 EJ-02-S045-B    EJ-02-02 SHT. 5   10" ELBOW TO 10" PIPE                                              0,365     UIT    R-A       R1.20       204 EJ-02-FW3 11    EJ-02-02 SirT. 3  8" PIPE TO 10" X 10" X 8" TEE                                     0.322      UT     R-A       R1.20       203 EJ-01-S0 10-B   EJ-01-01 SHT. 2   8" PIPE TO 10" X 8" EXPANDER                                      0.322      UT     k-A       R1.20       203 E J-01 -SO 17-D EJ-01-01 SET. 3  10" X 10" X 8" TEE TO 10" PIPE                                   0.365        UT     MRP-1 92 MRP1 92      204 EJ-0 1-S017-F   EJ-01-01 SHT. 3  10" PIPE TO 10" ELBOW                                            0.365        UT     MRP-1 92 MR.P192      204 EJ-0 1-S017-G   EJ-01-01 SHT. 3  10" ELBOW TO 10" PIPE                                            0.365        UT     MRP-1 92 MRIP192      204 EJ-01-S0 17-B   EJ-01-01 SHT. 3  10" PIPE TO 10" X 10" X 8" TEE                                   0.365        UT     MRP-1 92 MR.P192      204 E J-01 -F017    EJ-01-01 SHT. 3  8" PIPE TO 10" X 10" X 8" TEE                                    0.322        UIT    MRP- 192 MR.PI92      203 EJ-02-S022-D    E J-02-02 SHT. 3 10" X 10" X 8" TEE TO 10" PIPE                                   0.365        UT     MRP- 192 MRP 192      204 EJ-02-FW320     EJ-02-02 SHT. 3   10" PIPE TO 10" ELBOW                                            0.365       UT     MRP- 192 MRP192       204 EJ-02-S022-G    EJ-02-02 SHT. 3  10" ELBOW TO 10" PIPE                                            0,365        UT     MRP-1 92 MRP1 92      204 EJ-02-S022-B    EJ-02-02 SHT, 3   10" PIPE TO 10" X 10" X 8" TEE                                    0.365      UT     MRP- 192  MRP 192     204          6 EJ-02-FW311I    EJ-02-02 SHT. 3   8" PIPE TO 10" X 10" X 8" TEE                                     0.322      UT     MRP- 192  MRP 192     203          6 WCRE-30                                                       4.1.10 Residual Heat Removal System (EJ)                                                  Revision 0 Page 10 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE E J-3
[   Prio 3Examinations SSystem: EJ Relief Request or Cal Block         Notes Component Name    Drawing Number    Component Description                                 Size  Thickness NDE Method Category Item EEJ01A-S KIRT-w   ISI-EEJ01A SHT. I SUPPORT SKIRT WELD                                                        PT     C-C      C3.10 E J-0 I-C015      EJ-01-01 SHT. 3   PIPING INTEGRAL ATTACHMENTS                                               PT     C-C      C3.20 EJ-02-C012        EJ-02-02 SHT. 4   PIPING INTEGRALATTACHMENTS (8 LUGS)                   10                  PT     C-C      C3.20 PEJ01IA-SUP-I     EJ-01-01 SHIT. 2  RHR PUMP A INTEGRALLY WELDED ATT'ACHMENTS             8                   PT     C-C      C3.30 EEJ01A-SUPPORT-1  ISI-EEJ01A SHT. 1 SUPPORT LUG TO SHELL WELD                                                VT-1    D-A      DI.10 EEJ01 A-SUPPORT-2 ISI-EEJ0IA SHT. 1 SUPPORT LUG TO SHELL WELD                                                VT-i    D-A      DI.10 EJ-04-H007        E J-0 1-04        PIPING SUPPORT                                        12                 VT-3    F-A      FI.10 EJ-04-C020        E J-02-04 SHT. 1  PIPING SUPPORT                                        12                 VT-3    F-A      FI.10 E J-01l-C01 5     EJ-01-01 SHT. 3   PIPING SUPPORT                                                           VT-3    F-A      F1.20 E J-01I-R017      EJ-01-01 SHT. 1   PIPING SUPPORT                                        12                 VT-3    F-A      Ft.20 E J-01 -R019      Er-cl-cl SHT. 1   PIPING SUPPORT                                        14                 VT-3    F-A      F 1.20 EJ-02-R022        EJ-02-02 SHT. 3   PIPING SUPPORT                                        10                 VT-3    F-A      F1.20 EJ-02-C012        E J-02-02 SHT. 4  PIPING SUPPORT                                        10                 VT-3    F-A      F 1.20 EJ-04-R010        E J-02-04 SHT. 2  PIPING SUPPORT                                        6                  VT-3    F-A      F1.20 WCRE-30                                                     4.1.10 Residual Heat Re:moval System (EJ)                                                Revision 0 Page 11 o )f14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EJ-3 I eid3Examinations
[System: EJ Relief Request or Size Thickness NDE Method                 Cal Block          Notes Component Name     Drawing Number    Component Description                                                               Category Item EJ-04-C0I11        EJ-02-04 SHT. 3   PIPING SUPPORT                                            6                 VT-3    F-A      F 1.20 E J-0 1-C0 14      EJ'-01-01 SHT. 2  PIPING SUPPORT                                            10                VT-3    F-A      Ft.20 EJ-01-H006         EJ-01-01 SHT. 2   PIPING SUPPORT                                            10                VT-3    F-A      F 1.20 EEJ01A-SKIRT-w     ISI-EEJO1A SHT. 1 RHR HX SUPPORT                                                              VT-3    F-A      F1.40 EEJ01 A-SUPPORT-i1 ISI-EEJ01A SHT. 1 RHR H-X SUPPORT                                                             VT-3    F-A      F1.40 EEJ01 A-SUPPORT-2  ISI-EEJ01A SHT. 1 RI-R H-X SUPPORT                                                            VT-3    F-A      F1.40 EJ-04-F048A        EJ-01-04          12" PIPE TO VALVE HV-870 I1A                              12       1.125     UT     R-A      RI 11      126          4, 5 EJ-04-S016-G       EJ-02-04 SHT. 1   12" PIPE TO 12" ELBOW                                     12       1.125     UT     R-A      RI 11      126          4, 5 EJ-04-S0 16-H      EJ-02-04 SHT. 1   12' ELBOW TO 12" PIPE                                     12       1.125     UT     R-A      RI~ll      126          4,5 EP-0 1-MW7 152     EJ-01-01 SHT. 4   6" PIPE TO VALVE 8818A                                   6        0.719      UT     R-A      RI.I1      117          4,5,7 EP-02-MW7 162      EJ-02-04 SHT. 2   6" PIPE TO VALVE 8818C                                   6        0.719      UT     R-A      RI.II      117          4,5,7 EP-01 -MW7165      EJ-02-04 SHT. 2   6" PIPE TO VALVE 8818D                                   6        0.719      UT     R-A      RI 11      117          4,5,7 EJ-04-S014-D       EJ-02-04 SHT. 1   12" ELBOW TO 12" PIPE                                     12       1.125     UT     R-A      R1.20      126          4 E J-01 -F005       EJ-01-01 SHT. 1   14" PIPE TO 14" ELBOW                                     14      0.438      UT     R-A      R1.20      192          4 WCRE-30                                                        4.1.10 Residual Heat Removal System (EJ)                                                  Revision 0 Page 12 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EJ-3 SPeriod 3 Examinations Relief Request or Component Name Drawing Number    Component Description                                       Size Thickness NDE Method Category Item   Cal Block          Notes E J-01-FW3I111 EJ-01-01 SHT. 1   12" ELBOW TO 12" PIPE                                       12      0.375      UT     R-A      R1.20      183          4 EJ-01-FW333    EJ-01-01 SHT. 1   12" PIPE TO 12" PIPE                                        12      0.375      UT     R-A      R1.20      183          4 EJ-0I-S021-E   EJ-01-01 SHT. 2   10" PIPE TO 10' ELBOW                                       10      0.365      UT     R-A      R1.20      204          4 EJ-01 -S021 -F EJ-01-01 SHT. 2   10" ELBOW TO 10" PIPE                                       10      0.365      UT     R-A      RI.20      204          4 EJ-01-S026-E   El-0 1-01 SHlT. 5 8" PIPE TO 8" ELBOW                                         8       0.322      UT     R-A      R1.20      203          4 EJ-02-F021     E J-02-02 SHT. 2  10" TEE TO 10" PIPE                                         10      0.365      UT     R-A      R1.20      204          4 EJ-02-F031     E J-02-02 SHT. 4  10" TEE TO 10" PIPE                                         10      0.365      UT     R-A      Ri1.20     204          4 EJ-02-S0 16-H  E J-02-02 SHT. 2  10" PIPE TO 10" TEE                                         10      0.365      UT     R-A      R1.20      204          4 EJ-02-S0 16-K  E J-02-02 SilT. 2 10" TEE TO 10" PIPE                                         10      0.365      UT     R-A      R1.20      204          4 EJ-02-S023-B   EJ-02-02 SHT. 4   10" PIPE TO 10" TEE                                         10      0.365      UT     R-A      R1.20      204          4 EJ-02-S023-D   EJ-02-02 SHT. 4   10" TEE TO 10" PIPE                                         10      0.365      UIT    R-A      RI.20      204          4 EJ-04-F043     EJ-01-01 SHlT. 4  10" PIPE TO 10" X 10" X6" TEE                               10       1.00      UT     R-A      R1.20      122          4 EJ-04-FW91I0A  EJ-02-04 SHlT. 2  10" PIPE TO 10" X 10" X 6" TEE                              10       1.00      UT     R-A      R1.20      122          4 EJ-04-SO01-D   EJ-02-04 SHlT. 2  10" ELBOW TO 10" PIPE                                       10       1.00      UT     R-A      R1.20      122          4 WCRE-30                                                      4.1.10 Residual Heat Removal System (EJ)                                                  Revision 0 Page 13 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE E J-3
[System: EJ Relief Request or Size   Thickness NDE Method Category  Item   Cal Block          Notes Component Name   Drawing Number    Component Description EJ-04-S00I-G     EJ-02-04 SHT. 2   10" X 10' X 6" TEE TO 10" PIPE                          10        1.00      UT     R-A       R1.20      122 EJ-04-FW371      EJ-02-04 SILT. 2  10" X10" X6" TEE TO 6" PIPE                            6         0.7 19     UT     R-A       RI.20      117          4 E J-01-S017-D   EJ-01-01 SHlT. 3  10OX 10" X8" TEE TO 10" PIPE                            10      0.365        UT     MRP- 192 MR.PI92     204          6 E J-0 1-SO 17-F EJ-0I-01 SHT. 3   10" PIPE TO 10" ELBOW                                   10      0.365        UT     MRP-1 92 MRP 192     204          6 EJ-01-S017-G    EJ-01-0I SilT. 3  10" ELBOW TO 10" PIPE                                   10      0.365        UIT    MRP-1 92 MRP192      204          6 EJ-02-S022-D    EJ-02-02 SHT. 3   10" X10" X8" TEE TO 10"PIPE                             10      0.365        UT     MRP-1 92 MRPI92      204          6 EJ-02-FW320     EJ-02-02 SHlT. 3  10" PIPE TO 10" ELBOW                                   10      0.3 65       UT     MRP-1 92 MRP192      204          6 EJ-02-S022-G    EJ-02-02 SHlT. 3  10" ELBOW TO 10" PIPE                                   10      0.365        UT     MRP-1 92 MRP192      204          6 WCRiE-30                                                      4.1.10 Residual Heat Removal System (EJ)                                                 Revision 0 Page 14 of 14

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.11 High Pressure Coolant Injection System (EM~)
A.      Applicable System Piping and Instrument Drawings
: 1. M-l2EM01-High Pressure Coolant Injection System
: 2. M-12EM02-High Pressure Coolant Injection System*
* Except for ASME Class 2 components listed in Section 4.3 B.      Classification of Components Details of the classification of the High Pressure Coolant Injection System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
Note: for purposes of determining which EM system components are exempt based on size (i.e, NPS 4 inch vs NPS 11/2'/  inch for High Pressure Safety Injection systems), the pumps in the EM system, PEM01A and PEM01B, are defined as Intermediate Pressure Safety Injection Pumps (reference USAR Table 6.2.1-3). Thus, the NPS 4 inch exemption is applied. The Centrifugal Charging Pumps (CCPs), PBG05A 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 11/2'/   inch exemption rule. See the ISI Classification Basis Document for definition of which lines fall under each exemption.
D. Applicable ISI 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-189-50 series.
: 1.      M-189-50EM-01-01        Sheet 1        High Pressure Coolant Injection Safety Injection Pump "A" Suction
: 2.      M-189-50EM-02-01        Sheet 1        High Pressure Coolant Injection Safety Injection Pump "B" Discharge
: 3.      M-189-50EM-03-05        Sheet 1        High Pressure Coolant Injection Safety Injection Pumps to RH-R System
: 4.      M-189-50EM-04-03        Sheet 1        High Pressure Coolant Injection Safety Injection Pumps to RCS
: 5.      M-189-50EM-05-01        Sheet 1        High Pressure Coolant Injection Safety Injection Pump Suction Cross Tie
: 6.      M-189-50EM-05-01        Sheet 2        High Pressure Coolant Injection Safety Injection Pump Suction Cross Tie to CVCS
: 7.      M-189-50EM-06-02        Sheet 1        High Pressure Coolant Injection HPSI Discharge to RCS
: 8.      M-189-50EM-06-02        Sheet 2        High Pressure Coolant Injection HPSI Discharge to RCS
: 9.      M-189-50EM-06-03        Sheet 1        High Pressure Coolant Injection HPSI Discharge to RCS
: 10. M-189-50ISI-PUMPS Sheet 1              ISI Pumps WCRE-30                   4.1.11 High Pressure Coolant Injection System (EM)                                  Revision 0 Page 1 of 11

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1S1 PROGRAM PLAN 4.1.11 High Pressure Coolant Injection System (EMI)
E. Summary of 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 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       P1_!  P.2   P__3       INTERVAL PRESSURE RETAINING           B-G-2            B7.50               --                             4         *      *    *        *See Paragraph I, BOLTING-PIPING                                                                                                                 Notes 1 & 4 PRESSURE RETAINING           B-G-2            B7.70               --                             4*               *    *        *See Paragraph I, BOLTING-VALVES                                                                                                                  Notes 2 & 4 VALVE BODY              B-M-2            B 12.50             --                             4*                *   *        *See Paragraph I, EXCEEDING NPS 4                                                                                                                 Notes 3 & 4 PRESSURE RETAINING            C-A             C1.20                --                            20               0    22 VESSEL WELDS-CIRC.
PRESSURE RETAINING            C-B             C2.21                --                            20                1   12 NOZZLE-SHELL WELD VESSEL WELDED              C-C              C3.10               --                            4         0       1   0                 1 AT1TACHMENTS PIPING WELDED              C-C             C3.20               --                            24         1       1   1                3 ATITACHMENTS PIPING COMPONENTS             F-A             FI. 10              --                            76         7      6    7               20 SUPPORTS PIPING COMPONENTS             F-A             FI.20               --                            83         4      5    5                14 SUPPORTS WCRE-30                                                  4.1.11 High Pressure Coolant Injection System (EM)                                  Revision 0 Page 2 of 11

WOLF CREEK GENERATING STATION FOURTH 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]_  P_.2  P.33     INTERVAL EQUIPMENT SUPPORTS                                                                                                                    4 (OTHER THAN PIPING)
PIPING WELDS SUBJECT                                                                                                                   0 TO THERMAL FATIGUE PIPING WELDS SUBJECT                                                                                                                   2 TO IGSCC or TGSCC PIPING WELDS NOT                                                                                                                     3 SUBJECT TO A DAMAGE MECHANISM Note 1: See Section H for an explanation of Category R-A and Item R1.XX nomenclature.
WCRE-30                                                   4.1.11 High Pressure Coolant Injection System (EM)                               Revision 0 Page 3 of 11

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.11 High Pressure Coolant Injection System (EM)
F. Augmented 1SI Requirements No Augmented 1S1 requirements apply to the High Pressure Coolant Injection System.
G. System Pressure Testing In accordance with Section XI, IWA-5000 and IWB-5000, the Class 1 pressure retaining components within the High Pressure Coolant Injection System will receive a system leakage test per IWB-5220 prior to plant startup following each refueling outage.
In accordance with Section XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining components within the High Pressure Coolant Injection System will receive a system leakage test per IWC-5 220 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 1 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-1 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 through 4-4 of TR-1 12657 Rev. B-A.
Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table EM-i (Period 1 Examinations), 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 Category B-G-2, Notes 1 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 ofbolted connection is required only once during the interval. See Category B-G-2, Notes 1 and 2.
: 3. Examination of the valve internal surface is required only when a valve is disassembled for maintenance or repair. The 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 that perform 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-30                           4.1.11 High Pressure Coolant Injection System (EM)                      Revision 0 Page 4 ofl11

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN
: 4. WCNOC procedures require that the IS1 Coordinator be informed whenever a Class 1 component is disassembled for repair or maintenance and that the ISI Coordinator specify' if a VT-1 and/or VT-3 exam is required. Whenever a component is required to have a B-G-2 or B-M-2 exam performed, the 1SI Coordinator shall revise the applicable Table EM-i, EM-2, or EM-3 and Table i to reflect the component being examined. Reference procedures AP 16A-003, ASME Section XI Repair and Replacement Program; and Al 16C-007, Work Order Planning.
: 5. These welds have been selected per the RM-SI Program. The requirements for examination of these welds are included in Paragraph H above.
: 6. These welds have IGSCC identified as the degradation mechanism.
WCRE-30                    4.1.11 High Pressure Coolant Injection System (EM)                Revision 0 Page 5 of ii

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE    EM-I ISystem: EM Relief Request or Cal Block         Notes Component Name    Drawing Number   Component Description                                   Size  Thickness   NDE Method Category Item EM-01-A003        EM-05-01 SHT. I  PIPING INTEGRAL ATTACHMENTS                             6                     PT     C-C      C3.20 EM-05-R001        EM-03-05         PIPING SUPPORT                                          6                    VT-3    F-A      Fl.10 EM-03-C012        EM-04-03         PIPING SUPPORT                                          6                    VT-3    F-A      FI.10 EM-03-C013        EM-04-03         PIPING SUPPORT                                          6                    VT-3    F-A      FI.10 EM-03-A005        EM-06-03         PIPING SUPPORT                                          1.5                  VT-3    F-A      Fl.10 EM-03-C033        EM-06-03         PIPING SUPPORT                                          1.5                  VT-3    F-A      Fl. 10 EM-03-R01 5       EM-06-03         PIPING SUPPORT                                          1.5                  VT-3    F-A      FI.10 EM-03-R01 8       EM-06-03         PIPING SUPPORT                                          1.5                  VT-3    F-A      FI,1 EM-0Ol-H015       EM-02-01         PIPING SUPPORT                                          8                    VT-3    F-A      F 1.20 EM-01l-A003       EM-05-0l SHT. 1  PIPING SUPPORT                                          6                    VT-3    F-A      F1.20 EM-01-C016        EM-05-0 1 SHT. 2 PIPING SUPPORT                                          6                    VT-3    F-A      F1,20 EM-02-R005        EM-06-02 SHT. 2  PIPING SUPPORT                                          3                    VT-3    F-A      F 1.20 TEM0 1-SUPPORT-i1 EM-06-02 SHT. 2  B.I.T. TANK SUPPORT                                                          VT-3    F-A      F1.40 WCRE-30                                                   4.1.11 High Pressure Coolant Injection System (EM)                                           Revision 0 Page 6 of 11

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EM-I I eid1Examinations Ssystem: EM Relief Request or Component Name                                                                                                     Category Item  Cal Bloc      ck   Notes Drawing Number Component Description                                    Size Thickness   NDE Method EM-05-S005-B   EM-03-05       6" PIPE TO 6" ELBOW                                      6       0.719        UT     R-A      RI.20     117              5 EM-05-S005-C   EM-03-05       6" ELBOW TO 6" PIPE                                       6      0.719        UT     R-A      R1.20     117              5 WCRE-30                                              4.1.11 High Pressure Coolant Injection System (EM)                                           Revision 0 Page 7 of l11

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EM-2 I   erod2Examinations I
[System:  EM Relief Request or Size   Thickness  NDE Method          Item  Cal Block          Notes Component Name  Drawing Number  Component Description                                                               Category TEM0 1--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-06-02 SHT. 2 VESSEL INTEGRAL ATTACHMENTS                                                  PT     C-C      C3.10 EM-02-R010      EM-06-02 SHT. l PIPING INTEGRAL ATTACHMENTS                            4                     PT     C-C      C3.20 EM-05-C008      EM-03-05        PIPING SUPPORT                                         2                    VT-3    F-A      FI.10 EM-05-R004      EM-03-05        P]PING SUPPORT                                         2                    VT-3    F-A      FI.10 EM-03-C008      EM-06-03        PIPING SUPPORT                                         3                    VT-3    F-A      FI.10 EM-03-C035      EM-06-03        PIPING SUPPORT                                         1.5                  VT-3    F-A      FI.10 EM-03-C047      EM-06-03        PIPING SUPPORT                                         1.5                  VT-3    F-A      FI.I EM-03-R01 6     EM-06-03        PIPING SUPPORT                                         1.5                  VT-3    F-A      FI.10 WCRjE-30                                              4.1.11 High Pressure Coolant Injection System (EM)                                          Revision 0 Page 8 of 11

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EM-2 IPeriod 2 Examinations ISystem: EM Relief Request or Size Thickness   NDE Method          Item   Cal Block          Notes Component Name   Drawing Number   Component Description                                                                Category EM-01-C044       EM-01-01         PIPING SUPPORT                                           8                   VT-3    F-A      F1.20 EM-01-C017       EM-05-01 SHT. l  PIPING SUPPORT                                           6                   VT-3    F-A      F 1.20 EM-01-H003       EM-05-01 SHT. 1  PIPING SUPPORT                                           6                   VT-3    F-A      F 1.20 EM-01-H016       EM-05-01 SHT. 1  PIPING SUPPORT                                          6                    VT-3    F-A      F1.20 EM-02-RO1O       EM-06-02 SiLT. 1 PIPING SUPPORT                                          4                    VT-3    F-A      FI.20 TEM01 -SUPPORT-2 EM-06-02 SlT. 2  B.I.T. TANK SUPPORT                                                          VT-3    F-A      FI.40 TEM01-SUPPORT-3  EM-06-02 SHT. 2  B.I.T. TANK SUPPORT                                                          VT-3    F-A      F1.40 EM-03-S01 5-B    EM-04-03         6" PIPE TO 6" ELBOW                                     6        0.719        UT     R-A      R1.20      117          5 WCRE-30                                                  4.1.11 High Pressure Coolant Injection System (EM)                                           Revision 0 Page 9 of 11

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EM-3 SSystem:  EM Relief Request or Size    Thickness  NDE Method           Item  Cal Block         Notes Component Name  Drawing Number  Component Description                                                               Category EM-02-H002      EM-06-02 SHT. 2 PIPING INTEGRAL ATTACHMENTS                           4                      PT     C-C      C3.20 TEM01-SEAM-2-W  EM-O6-O2 SHT. 2 TOP HEAD TO SHELL WELD                                NA           2.00      UT     C-A      C 1.20     144 TEM01 -SEAM-3-W EM-06-02 SHT. 2 BOFIqOM HEAD TO SHELL WELD                            NA           2.00      UT     C-A      C 1.20     144 TEM01 - W       EM-06-02 SHT. 2 OUTLET NOZZLE TO TOP HEAD WELD                        NA           2.00     UT/PT   C-B      C2.21      144 EM-05-R002      EM-03-05        PIPING SUPPORT                                                              VT-3    F-A      F1.1 EM-03-C016      EM-04-03        PIPING SUPPORT                                        2                     VT-3    F-A      FI.1 EM-03-HO04      EM-O4-03        PIPING SUPPORT                                        6                     VT-3    F-A      FI.1 EM-03-RO05      EM-04-03        PIPING SUPPORT                                        6                     VT-3    F-A      FI.10 EM-03-RO08      EM-04-03        PIPING SUPPORT                                        2                     VT-3    F-A      FI.1 EM-03-CO29      EM-06-03        PIPING SUPPORT                                         1.5                  VT-3    F-A      FI.10 EM-O3-CO34      EM-C6-O3        PIPING SUPPORT                                         1.5                  VT-3    F-A      FlICI EM-0 1-CO015    EM-05-01 SHT. 1 PIPING SUPPORT                                        6                     VT-3    F-A      F 1.20 EM-01-CO36      EM-O5-01 SHT. I PIPING SUPPORT                                        6                     VTr-3   F-A      FI1.20 WCRE-30                                               4.1.11 High Pressure Coolant Injection System (EM)                                           Revision 0 Page 10 ofll1

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EM-3 SSse:EM Relief Request or Component Name  Drawing Number   Component Description                                 Size   Thickness   NDE &#xa3;Method Category Item   Cal Block         Notes 3
EMv-32-R007     EMv-06-02 SriT.i rlr*ltG SUPPRT.Jr                                     4                      V?-     F-A      P1.23 EM-02-R01 1     EM-06-02 SHT. 1  PIPING SUPPORT                                        4                      VT-3    F-A      F1 .20 EM-02-H002      EM-06-02 SHT. 2  PIPING SUPPORT                                        4                      VT-3    F-A      F 1.20 TEM01-SUPPORT-4 EM-06-02 SHT. 2  B.I.T. TANK SUPPORT                                                          VT-3    F-A      F 1.40 EM-03-S01 1-F   EM-04-03         6" PIPE TO 6" ELBOW                                   6                       UT     R-A      RI.16      117 0.7 19                                                5,6 EM-03-S01 1-G   EM-04-03         6" ELBOW TO 6" PIPE                                   6         0.7 19        UT     R-A      Ri. 16     117          5, 6 WCRE-30                                                4.1.11 High Pressure Coolant Injection System (EM)                                            Revision 0 Page 11 of 11

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.12 Containment Spray System (EN)
A. Applicable System Piping and Instrument Drawings
: 1. M- 12EN0 1-Containment Spray System B. Classification of Components Details of the classification of the Containment Spray System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
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-01-01          Sheet 1 Containment Spray "A" Train Pump  Suction
: 2.       M- 189-50EN-01-01          Sheet 2 Containment Spray "A" Train Pump Discharge
: 3.       M-189-50EN-01-01           Sheet 3 Containment Spray "A" Train Pump Bypass
: 4.       M-1 89-50EN-02-02          Sheet 1 Containment Spray "B" Train Pump Suction
: 5.       M-1 89-50EN-02-02          Sheet 2 Containment Spray "B" Train Pump Discharge
: 6.       M-1 89-50EN-02-02          Sheet 3 Containment Spray "B" Train Pump Bypass
: 7.       M-1 89-50ISI-PUMPS         Sheet 1 ISI Pumps WCRE-30                   4.1.12 Containment Spray System (EN)                                     Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.12 Containment Spray System (EN)
E.      Summary of Components Subject To Section XI and Augmented NDE/Scheduled For Examination Table 1 is a sumimary 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       P1. P__2     P__3        INTERVAL PIPING WELDED                 C-C             C3.20              --                          7          1     0       1                 2 ATTACHMENTS PUMP WELDED                  C-C             C3.30                              -60                          0       11 ATTACHMENTS PIPING                   F-A             F1.20              --                          24         3     1       26 SUPPORTS SUPPORTS OTHER THAN                F-A             F1.40--63                                                       0       03 PIPING SUPPORTS PIPING WELDS NOT                 R-A             R1.20              --                         137         0     0       00 SUBJECT TO A DAMAGE MECHANISM.                 Note 1           Note 1 Note 1: See Section H for an explanation of Category R-A and Item R1 .XX nomenclature.
WCRE-30                                                      4.1.12 Containment Spray System (EN)                                              Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.12 Containment Spray System (EN)
F. Augmented ISI Requirements No Augmented IS1 requirements apply to the Containment Spray System.
G. 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-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 1 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-578-1 .No welds in the Containment Spray System were selected for examination in the RI-ISI program.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table EN- 1 (Period 1 Examinations), Table EN-2 (Period 2 Examinations),
and Table EN-3 (Period 3 Examinations).
WCRE-30                    4.1.12 Containment Spray System (EN)                             Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EN-I IPeriod 1 Examinations
[System:  EN Relief Request or Item   Cal Block         Notes Component Name Drawing Number   Component                                           Size Thickness NDE Method Category EN-01I-A003    EN-01-01 SHiT. 3 PIPING INTEGRAL ATTACHMENTS                         6                  PT     C-C      C3.20 EN-02-H005     EN-02-02 SHIT. 2 PIPING SUPPORT                                       10               VT-3    F-A      F 1.20 EN-0OI-A003    EN-01-01 SHiT. 3 PIPING SUPPORT                                      6                 VT-3    F-A      F1.20 EN-01-C005     EN-01-01 SHT. 2  PIPING SUPPORT                                       10               VT-3    F-A      F 1.20 PEN01lA-SUP-I  EN-01-01 SIIT. 1 CONTAINMENT SPRAY "A" PUMP SUPPORT                   12               VT-3    F-A      F1.40 PEN01 A-SUP-2  EN-01-01 SliT. 1 CONTAINMENT SPRAY "A" PUMP SUPPORT                   12               VT-3    F-A      F1.40 PEN01A-SUP-3   EN-O1-01 SLIT. 1 CONTAINMENT SPRAY "A" PUMP SUPPORT                   12               VT-3    F-A      FI1.40 WCRE-30                                                  4.1.12 Containment Spray System (EN)                                                Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EN-2 SPeriod 2 Examinations SSystem:   EN 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               VT-3    F-A      Fl1.20 WCRE-30                                           4.1.12 Containment Spray System (EN)                                                Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EN-3
[Sse  EN Relief Request or Item   Cal Block         Notes Component Name Drawing Number   Component                                          Size Thickness NDE Method Category EN-02-R007     EN-02-02 SHlT. 2 PIPING INTEGRAL ATTACHMENTS                        10                 PT     C-C      C3.20 PEN01lA-SUP-I  EN-01-01 SHT. l  CS PUMP A INTEGRALLY WELDED ATTACHMENTS            12                 PT     C-c      C3.30 EN-01-R008     EN-0l-0l SLIT. 1 PIPING SUPPORT                                     12                VT-3    F-A      FI.20 EN-02-R007     EN-02-02 SHT. 2  PIPING SUPPORT                                     10                VT-3    F-A      F 1.20 WCRE-30                                                  4.1.12 Containment Spray System (EN)                                               Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.13 Accumulator Safety Injection System (EP)
A. Applicable System Piping and Instrument Drawings
: 1. M- 12EP0 1-Accumulator Safety Injection System B. Classification of Components Details of the classification of the Accumulator Safety Injection System components for ISI are in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
C. Nonexempt and Exempt ASME Class Components A listing of Nonexempt and Exempt ASME Class components is included in "Inservice Inspection Classification Basis Doctument Wolf Creek Generating Station Interval 4".
D. Applicable IST Isometrics and 1SI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Accumulator Safety Injection System. These drawings are part of the M-189-50 series.
: 1.       M-189-50EP-01-O1             Sheet 1         Accumulator   Safety Injection  Loop 1
: 2.       M-189-5OEP-02-02             Sheet 1         Accumulator   Safety Injection  Loop 2
: 3.       M-1 89-50EP-03-02            Sheet 1         Accumulator   Safety Inj ection Loop 3
: 4.       M-189-50EP-04-0l             Sheet 1         Accumulator   Safety Injection  Loop 4 WCRE-30                   4.1.13 Accumulator Safety Injection System (EP)                                Revision 0 Page 1 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI 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 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 1S1 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      P1  P2     P3         INTERVAL PRESSURE RETAINING                B-G-2           B7.50               -               -2                      *    *      *       *See Paragraph I, BOLTING-PIPING                                                                                                                    Notes 1 & 4 PRESSURE RETAINING                B-G-2            B7.70              --                            12        *    *     *        *See Paragraph I, BOLTING-VALVES                                                                                                                     Notes 2 &4 VALVE BODY                    B-M-2           B 12.50             --                            12        *   *      *        *See Paragraph I, EXCEEDING NPS 4                                                                                                                    Notes 3 & 4 PIPING COMPONENT                   F-A            Fi.l 0             -                            29         3   2      4                9 SUPPORTS PIPING WELDS SUBJECT                 R-A "          Rl.16              --                            12        0   0      22 TO IGSCC OR TGSCC                Note 1          Note 1 PIPING WELDS NOT                   R-A            RI.20              --                           109        0   2      02
 'SUBJECT TO A DAMAGE                Note 1          Note 1 MECHANISM Note 1: See Section H for an explanation of Category R-A and Item R1 .XX nomenclature.
WCRE-30                                                         4.1.13 Accumulator Safety Injection System (EP)                                    Revision 0 Page 2 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.13 Accumulator Safety Injection System (EP)
F.      Augmented 1SI 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 1 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.
In accordance 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 1 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 fr'om Code Case N-578-1l 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-1 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 through 4-4 of TR-112657 Rev. B-A.
I. Components and Component Supports Selected/Schleduled For Examination The components and component supports selected for examination during Interval 4 are included in Table EP-1 (Period 1 Examinations), Table EP-2 (Period 2 Examinations),
and Table EP-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 Category B-G-2, Notes 1 and 3.
: 2. Examination of Pressure Retaining Bolting is performed in accordance with Category B-G-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 Category B-G-2, Notes 1 and 2.
: 3. Examination of the valve internal surface is required only when a valve is disassembled for maintenance or repair. The 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 that perform 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-30                 4.1.13 Accumulator Safety Injection System (EP)                           Revision 0 Page 3 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN
: 4. WCNOC procedures require that the ISI Coordinator be informed whenever a Class 1 component is disassembled for repair or maintenance and that the ISI Coordinator specify if a VT-i and/or VT-3 exam is required. Whenever a component is required to have a B-G-2 or B-M-2 exam performed, the ISI Coordinator shall revise the applicable Table EP-1, EP-2, or EP-3 and Table i to reflect the component being examined. Reference procedures AP 16A-003, ASME Section Xl Repair and Replacement Program; and Al 16C-007, Work Order Planning
: 5. These welds have been selected per the RI-ISI Program. The requirement for examination of these welds is given in Paragraph H above.
: 6. These welds have IGSCC identified as the degradation mechanism.
WCRE-30 4.1.13 Accumulator Safety Injection System (EP)                       Revision 0 Page 4 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EP-I SPeriod 1 Examinations
[System:   EP Relief Request or Cal Block         Notes Component Name Drawing Number Component Description                                 Size  Thickness  NDE Method Category item EP-02-H006     EP-02-02       PIPING SUPPORT                                        10                  VT-3    F-A      FI.10 EP-0I-H006     EP-04-0 1      PIPING SUPPORT                                        2                   VT-3    F-A      FI.10 EP-0I1-R008    EP-04-0 t      PIPING SUPPORT                                        2                   VT-3    F-A      FI.I WCRE-30                                              4.1.13 Accumulator Safety Injection System (EP)                                           Revision 0 Page 5 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN TABLE EP-2
[System:  EP Relief Request or Size   Thickness  NDE Method          Item  Cal Block         Notes Component Name Drawing Number Component Description                                                              Category EP-01I-1004    EP-04-01       PIPING SUPPORT                                        10                   VT-3    F-A      FI.10
*EP-0 l-R005    EP-04-01       PIPING SUPPORT                                        10                   VT-3    F-A      FI.10 EP-l0 -S004-C  EP-0 I-01      10" PIPE TO 10" ELBOW                                 10                    UT     R-A      R1.20    122            5 EP-01-S004-D   EP-01-01       10" ELBOW TO 10" PIPE                                 10                    UT     R-A      RI.20    122            5 WCRE-30                                               4.1.13 Accumulator Safety Injection System (EP)                                           Revision 0 Page 6 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE EP-3 SSystem:  EP Relief Request or Cal Block         Notes Component Name Drawing Number Component Description                                Size   Thickness  NDE Method Category Item EP-01-R013     EP-01-0Ol      PIPING SUPPORT                                       10                   VT-3    F-A      FI.10 EP-0 1-C004    EP-04-01       PIPING SUPPORT                                       2                    VT-3    F-A EP-0Ol-RO01    EP-04-O01      PIPING SUPPORT                                       6                    VT-3    F-A      FI.10 EP-0 1-HO010   EP-01-01       PIPING SUPPORT                                       6                    VT-3    F-A      FI.10 EP-0 1-S003-K  EP-01-01       10" PIPE TO 10" ELBOW                                10                    UT     R-A      Rl.16     122          5, 6 EP-01 -S003-L  EP-01-01       10" ELBOW TO 10" PIPE                                10          1         UT     R-A      Rl.16     122          5, 6 WCRE-30                                              4.1.13 Accumulator Safety Injection System (EP)                                           Revision 0 Page 7 of 7

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.14 Auxiliary Feedwater Pump Turbine System (FC)
A. Applicable System Piping and Instrument Drawings
: 1. M-12FC02-Auxiliary Feedwater Pump Turbine System B. Classification of Components Details of the classification of the Auxiliary Feedwater Pump System components for ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
D. Applicable ISI Isometrics and ISI 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 1    Auxiliary Turbines Auxiliary Feedwater Pump Turbine Steam Supply Piping WCRE-30            4.1.14 Auxiliary Feedwater Pump Turbine System (FC)                                  Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.14 Auxiliary Feedwater Pump Turbine System (FC)
E. Summary of 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 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      P_.1   P__2     P_3       INTERVAL PIPING WELDS SUBJECT               --                            USAR           3.6.2           17        2        1      25 TO HELB REQUIREMENTS            __  _     _  _   __    _  _ _     __  _  _  _    __  _   _ _  _   _ _  _ _ _  _   _  _   _ _   _ _ _ _   _   _   _   _  _ _
WCRE-30                                       4.1.14 Auxiliary Feedwater Pump Turbine System (FC)                                              Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.14 Auxiliary Feedwater Pump Turbine System (FC)
F. Augmented ISI Requirements The following Augmented 1S1 requirements apply to the Auxiliary Feedwater Pump System:
: 1. WCGS USAR Sections 3.6.1, Postulated Pipin* 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 Pipine- 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-33 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-1 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 Figure 4-1 through 4-4 of TR-1 12657 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.
Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table FC-1 (Period 1 Examinations), Table FC-2 (Period 2 Examinations),
and Table FC-3 (Period 3 Examinations).
WCRE-30             4.1.14 Auxiliary Feedwater Pump Turbine System (FC)                       Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE FC-1 SPeriod 1 Examinations
[System:   FC Relief Request or Component Name Drawing Number Component Description                                   Size Thickness NDE Method Category Item Cal Block         Notes FC-01-F022     FC-01-0[       VALVE V001 TO 4" PIPE                                   4       0.337      UT     USAR     3.6.2     159 FC-0I-F023     FC-01-01       4" PIPE TO VALVE V024                                   4       0.337      UT     USAR     3.6.2     159 WCRE-30                                      4.1.14 Auxiliary Feedwater Pump Turbine System (FC)                                            Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE FC-2 I eid2Examinations
[System:  FC Relief Request or Component Name Drawing Number Component Description                                    Size   Thickness NDE Method Category Item  Cal Block         Notes FC-01-S02 1-C  FC-01-01       4" PIPE TO 4" ELBOW                                           40.337          UT     USAR     3.6.2     159 WCRE-30                                        4.1.14 Auxiliary Feedwater Pump Turbine System (FC)                                              Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE FC-3
[System:  FC Relief Request or Component Name Drawing Number Component Description                                 Size  Thickness NDE Method Category Item  Cal Block         Notes FC-0l-F026     FC-01-01       4" PIPE TO VALVE V002                                 4        0.337      UT     USAR     3.6.2     159 FC-0]-F027      FC-01-0I       VALVE V025 TO 4" PIPE                                 4        0.337      UT     USAR     3.6.2     159 WCRE-30                                              Auxiliary Feedwater Pump Turbine System (FC)
WCRE-304.1.14                                                                                  Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.15 Containment Cooling System (GN)
A. Applicable System Piping and Instrument Drawings
: 1. M- 12GN0 1-Containment Cooling System B. Classification of Components Details of the classification of the Containment Cooling System components for 1SI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
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-01-01            Sheet 1          Containment Cooling System  "A" Train Supply
: 2.       M-189-50GN-01-01            Sheet 2          Containment Cooling System  "A" Train Return
: 3.       M-189-50GN-01-01            Sheet 3          Containment Cooling System  "A" Train Cooler "A" Supply and Return Headers
: 4.       M-189-50GN-01-01            Sheet 4          Containment Cooling System  "A" Train Cooler "C" Supply and Return Headers
: 5.       M-1 89-50GN-02-02           Sheet 1          Containment Cooling System  "B" Train Supply
: 6.       M-1 89-50GN-02-02           Sheet 2          Containment Cooling System  "B" Train Return
: 7.       M-1 89-50GN-02-02           Sheet 3          Containment Cooling System  "B" Train Cooler "B" Supply and Return Headers
: 8.       M-1 89-50GN-02-02           Sheet 4          Containment Cooling System  "B" Train Cooler "D" Supply and Return Headers WCRE-30                4.1.15 Containment Cooling System (GN)                                  Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH 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 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 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        P1_   P2       P__3       INTERVAL PIPING WELDED              D-A             D1.20               --                        41           1     2       2                 5 ATT[ACHMENTS PIPING COMPONENT             F-A             F1.30               --                        112         4      3       7                14 SUPPORTS WCRE-30                                                4.1.15 Containment Cooling System (GN)                                              Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.15 Containment Cooling System (GN)
F. Augmented 1S1 Requirements No Augmented ISI requirements apply to the Containment Cooling System.
G. System Pressure Testing In accordance with Section XI, JWA-5000 and IWD-5000, the Class 3 pressure retaining components within the Containment Cooling System will receive a system leakage test per IWD-5220 every 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 Containment Cooling System.
Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table GN-1 (Period 1 Examinations), Table GN-2 (Period 2 Examinations),
and Table GN-3 (Period 3 Examinations).
WCRE-30                4.1.15 Containment Cooling System (GN)                           Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE GN-1 I eid1Examinations SSystem: GN Component Name Drawing Number   Component Description                                  Size Thickness NDE Method Category Item   Relief Request    Notes GN-01-C017     GN-0 1-01 SHT. 2 PIPING INTEGRAL ATTACHMENTS                             14               VT-i    D-A      D1.20 GN-0l-C003     GN-01-01 SHT. 1  PIPING- SUPPORT                                        14                VT-3    F-A      F 1.30 GN-O1-C01!7    GN-01-01 SHT. 2  PIPING SUPPORT                                         14                VT-3    F-A      F 1.30 GN-02-H001     GN-02-02 SHT. 2  PIPING SUPPORT                                         10                VT-3    F-A      FI.30 M-620-003-24   GN-02-02 SHT. 4  PIPING SUPPORT                                        6                  VT-3    F-A      FI.30 WCRE-30                                                 4.1.15 Containment Cooling System (GN)                                                 Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE GN-2 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                        8                    VT-i    D-A      D1.20 M-620-003- l 0 GN-0I-0I SHT. 3  PIPING INTEGRAL ATTACHMENTS                        8 "VT-I                      D-A      D1.20 M-620-003-09   GN-0I1-01 SHT. 3 PIPING SUPPORT                                     8                    VT-3    F-A      F1.30 M-620-003-1 0  UN-O1-O1 SHT. 3  PIPING SUPPORT                                      8                   VT-3    F-A      F 1.30 GN-02-C006     GN-02-02 SHT. 1  PIPING SUPPORT                                      10                  VT-3    F-A      F1.30 WCRE-30                                                 4.1.15 Containment Cooling System (GN)                                                 Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE GN-3 IPeriod 3 Examinations ISystem:   GN Component Description                                 Size Thickness NDE Method Category item   Relief Request     Notes Component Name Drawing Number M-620-003-1 3  GN-01 -01 SHT. 3 PIPING INTEGRAL ATTACHMENTS                           6                 VT-i    D-A      D1.20 M-620-003-14   GN-01-0 1 SHT. 3 PIPING INTEGRAL ATTACHMENTS                           6                 VT-I    D-A      D1.20 GN-01l-C016    GN-01-01 SHT. I  PIPING SUPPORT                                         14               VT-3    F-A      F 1.30 M-620-003-1 3  GN-01-01 SHT. 3  PIPING SUPPORT                                         6                VT-3    F-A      F 1.30 M-620-003-I4   GN-01-0 1 SHT. 3 PIPING SUPPORT                                        6                 VT-3    F-A      F1.30 GN-02-C026     GN-02-02 SIHT. 1 PIPING SUPPORT                                         10               VT-3    F-A      F 1.30 GN-01 -R001    GN-01-01 SHT. 1  PIPING SUPPORT                                         14               VT-3    F-A      F 1.30 GN-0 l-R005    GN-01-01 SHT. 2  PIPING SUPPORT                                         14               VT-3    F-A      F 1.30 GN-0 l-R008    GN-02-02 SHIT. 1 PIPING SUPPORT                                         10               VT-3    F-A      F 1.30 WCRE-30                                                 4.1.15 Containment Cooling System (GN)                                                 Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.16 Standby Diesel Generator Systems jKJ)
A. Applicable System Piping and Instrument Drawings
: 1. M- 12KJ 01-Standby Diesel Generator Cooling System
: 2. M-12KJ02-Standby      Diesel Generator "A" Intake Exhaust, F.O. & Start Air System
: 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
: 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 ISI are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
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 4".
D. Applicable 1SI Isometrics and ISI Equipment Drawings The following isometrics and drawings detail the nonexempt components and items subject to NDE in the Standby Diesel Generator Systems. These drawings are part of the M-189-50 series.
: 1.       M- 189-50K J-01-01      Sheet 1    Standby Diesel Engine  Diesel Generator "A" Cooling Water Piping
: 2.        M-189-50KJ-01-01        Sheet 4    Standby Diesel Engine  Diesel Generator "A" Exhaust Piping
: 3.        M-1 89-50KJ-02-04       Sheet 1    Standby Diesel Engine  Diesel Generator "B" Cooling Water Piping
: 4.        M- 189-50K J-02-04      Sheet 4    Standby Diesel Engine  Diesel Generator "B" Exhaust Piping WCRE-30               4.1.16 Standby Diesel Generator Systems (K J)                                 Revision 0 Page 1 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI PROGRAM PLAN 4.1.16 Standby Diesel Generator Systems (KJ)
E.      Summary of Components Subject To Section XJ 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 1S1 Database.
TABLE 1 SECTION XI AND AUGMENTED COMPONENT 

==SUMMARY==
AND SCHEDULE COMPONENT OR ITEM            CODE             CODE              AUG.          AUG        TOTAL TN          EXAMS BY PERIOD & INTERVAL DESCRIPTION           CATEGORY         ITEM NO.        CATEGORY        ITEM NO.      SYSTEM       P1L   P2       P3         INTERVAL VESSEL WELDED              D-A             DI.10               -              -12                    2      2      2                  6 ATTACHMENTS PIPING WELDED              D-A             D1.20               --                         10         I      1      0                  2 ATTACHMENTS PIPING COMPONENT             F-A             F1.30               --                         28         1      1       1                 3 SUPPORTS EQUIPMENT SUPPORTS             F-A             F1.40               --                         12         2      2      2                  6 (OTHER THAN PIPING)
WCRE-30                                               4.1.16 Standby Diesel Generator Systems (K J)                                           Revision 0 Page 2 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.1.16 Standby Diesel Generator Systems (KJ)
F. Augmented ISI Requirements The following Augmented 1SI requirements apply to the Standby Diesel Generator Systems:
: 1. USNRC Reuulatorv Guide 1.137. Revision 0 - Fuel-Oil Systems for 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 implementation of the testing and VT-2 examinations required by Articles IWD-2000 and IWD-5000 of ASME Section XI, 2007 Edition with the 2008 Addenda.
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-5 220 every 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 Standby Diesel Generator Systems.
I. Components and Component Supports Selected/Scheduled For Examination The components and component supports selected for examination during Interval 4 are included in Table KJ- 1 (Period 1 Examinations), Table K J-2 (Period 2 Examinations),
and Table KJ-3 (Period 3 Examinations).
WCRE-30                   4.1.16 Standby Diesel Generator Systems (KJ)                     Revision 0 Page 3 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE KJ-1 IPeriod 1 Examinations Component Name Drawing Number     Component Description                               size Thickness   NDE Method Category Item   Relief Request     Notes EKJ06A-SUP- 1  KJ1-01-01 SI-IT. 1 JACKET WATER EKJ06A INTEGRAL ATTACHMENT                                   VT-i  D-A      DI.10 EKJ06A-SUP-2   KJ1-01-01 SHT. 1   JACKET WATER EKJ06A INTEGRAL ATTACHMENT                                   VT-1  D-A      DI.10 KJ-01-C016     K J-02-04 SHT. 4   PIPING INTEGRAL ATTACHMENT                          42                    VT-I  D-A      D1.20 KJ-01-C016     KJ-02-04 SHT. 4    PIPING SUPPORT                                      42                    VT-3  F-A      F 1.30 EKJ06A-SUP- 1  KJ1-01-01 SHIT. 1  JACKET WATER HX SUPPORT                                                   VT-3  F-A      F 1.40 EKJ06A-SUP-2   KJ1-01-01 SHT. 1   JACKET WATER HX SUPPORT                                                   VT-3  F-A      F1.40 WCRE-30                                                       4.1.16 Standby Diesel Generator Systems (K J)                                      Revision 0 Page 4 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   KJ-2 IPeriod 2 Examinations
[System:  KJ Component Name Drawing Number   Component Description                                Size  Thickness  NDE Method Category Item   Relief Request    Notes EKJ03A-SUP-l1  KJ-01-01 SHT. I  INTERCOOLER HIX INTEGRAL ATTACHMENT                                        VT-1  D-A      DI.10 EKJ03A-SUP-2   KJ-01-01 SHT. 1  INTERCOOLER HX INTEGRAL ATTACHMENT                                         VT-i  D-A      DI.10 KJ-01-R008     KJ-01-01 SHT. 4  PIPING INTEGRAL ATTACHMENTS                          28                    VT-i  D-A      D1.20 KJ-0 1-RO08    KJ-0l=01 SHT. 4  PIPING SUPPORT                                       28                    VT-3  F-A      F 1.30 EKJO3A-SUP-1   KJ-01-01 SHT. 1  INTERCOOLER H-X SUPPORT                                                    VT-3  F-A      F1.40 EKJ03A-SUP-2   KJ=01-01 SHlT. 1 INTERCOOLER HX SUPPORT                                                     VT-3  F-A      F 1.40 WCRE-30                                                      4.1.16 Standby Diesel Generator Systems (KJI)                                      Revision 0 Page 5 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE   KJ-3
[System:  KJ Component Name Drawing Number    Component Description                               Size   Thickness  NDE Method Category Item   Relief Request    Notes EKJ04A-SUP- 1  1(1-01-01 SHT. 1  LUBE OIL EKJ04A INTEGRAL ATTACHMENT                                       VT-I   D-A      DI.10 EKJ04A-SUP-2   KJ3-01-01 SilT. 1 LUBE OIL EKJ04A INTEGRAL ATTACHMENT                                       VT-i   D-A      DI.10 K.J-01l-R004   KJ-02-04 SHlT. 4  PIPING SUPPORT                                      28                    VT-3   F-A      F1.30 EKJ04A-SUP-1   KJ3-01-01 SHT. 1  LUBE OIL COOLER HX SUPPORT                                                VT-3   F-A      F1.40 EKJ04A-SUP-2   KJ3-01-01 SHT. 1  LUBE OIL COOLER 1-X SUPPORT                                               VT-3   F-A      FI1.40 WCRE-30                                                       4.1.16 Standby Diesel Generator Systems (KJ)                                       Revision 0 Page 6 of 6

WOLF CREEK GENERATING STATION FOURTH INTERVAL 1SI 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) 4.2.2     Chemical and Volume Control System (M-12BG02) 4.2.3      Chemical and Volume Control System (M-12BG04) 4.2.4      Chemical and Volume Control System (M-12BG05) 4.2.5      Fuel Pool Cooling and Clean-Up System (M-12EC01) 4.2.6      Fuel Pool Cooling and Clean-Up System (M-12EC02)*
4.2.7      Miscellaneous Buildings HVAC (M-12GF0 1) 4.2.8      Fuel Building HVAC (M-12GG02) 4.2.9      Control Building HVAC (M-12GK01) 4.2.10     Auxiliary Building HVAC (M-12GK03) 4.2.11     Auxiliary Building HVAC (M-12GL01, M-12GL02, M-12GL03) 4.2.12     Containment Hydrogen Control System (M- 12GS01)*
4.2.13     Liquid Radwaste System (M-12HB01)*
4.2.14     Emergency Fuel Oil System (M-12JE01) 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-12SJ01) 4.2.18     Nuclear Sampling System (M-12SJ04)
* Except for ASME Class 2 components listed in Section 4.3 B.        Classification of Components Details of the classification of the components subject to ASME Section XI System Pressure Testing are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
            *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 4".
D.        System Pressure Testing In accordance with Section XI, IWA-5000 and IWB-5000, the Class 1 pressure retaining components included on the P&IDs of Section A will receive a system leakage test per IWB -5220 prior to plant startup following each refueling outage.
In accordance with Section XI, IWA-5000 and IWC-5000, the Class 2 pressure retaining components included on the P&IDs of Section A will receive a system leakage test per IWC-5 220 each inspection period.
In accordance with Section XI, IWA-5000 and IWD-5000, the Class 3 pressure retaining components included on the P&IDs of Section A will receive a system leakage test per IWD-5 220 each inspection period.
Procedures used to perform System Pressure Testing are listed in Table 4.2.1 WCRE-30                   4.2 Systems Subject to Section XI Pressure Testing Only                      Revision 0 Page 1 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN TABLE 4.2-1 SYSTEM PRESSURE TESTING PROCEDURES Procedure Number                         Procedure Title STS P-021A Train A Emergency Diesel Fuel Oil and Keep Warm System STS P-021A Pressure Test STS P-021B Train B Emergency Diesel Fuel Oil and Keep Warm System Pressure Test STS PE-021C      Train A Emergency Diesel FO, LO, J Wtr, Intclr, Roc Arm, Crank Vac, Air In & Exh Train B Emergency Diesel FO, LO, J Wtr, Intclr, Roc Arm, STS P-021D Crank Vac, Air In & Exh ST S PE-021E     Train A Emergency Fuel Oil Transfer System Pressure Test STS  P E-021F    Train B Emergency Fuel Oil Transfer System Pressure Test STS  PE-021G     Train A Emergency Diesel Air Start System Pressure Test STS  PE-021H     Train B Emergency Diesel Air Start System Pressure Test STS  PE-040A     Reactor Coolant System Pressure Test STS  PE-040C     Reactor Coolant System Pressure Test (10 Year)
STS  PE-040E     RPV Head Bare Metal Inspection STS  PE-041A     Steam Generator System Pressure Test (Ctmt)
STS  P E-041D    Steam Generator System Pressure Test (Non-Ctmt)
STS  PE-042A     CVCS Normal Ops (Ctmt)
STS  PE-042B     CVCS VCT Tank Room Chemical and Volume Control System NCP Discharge Header STS P-042C Pressure Test STS P-042D Chemical and Volume Control System CCP A Discharge Header Pressure Test Chemical and Volume Control System CCP B Discharge Header STS P-042E Pressure Test STS PE-042F      CVCS Normal Ops (Aux Bldg)
STS PE-042G      LID Reheat Heat Exchanger STS PE-042H      CVCS Excess Letdown Piping Pressure Test STS P0421  CVCS Boric Acid Tank A and Boric Acid Transfer Pump A Pressure Test CVCS Boric Acid Tank B and Boric Acid Transfer Pump B STS P-042J Pressure Test STS PE-042K      CVCS Immediate Borate Test STS PE-043A      RHR Train A Normal Ops STS P-043B Residual Heat Removal System Hot Leg Discharge and CCP/SI Pump 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-58, 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 Train 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-30                     4.2 Systems Subject to Section XI Pressure Testing Only Revision 0 Page 2 of 3

WOLF CREEK GENERATING STATION FOURTH 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 P-049C   A Train Underground Essential Service Water System Piping STS P-049C   Flow Test B Train Underground Essential Service Water System Piping STS PE-049D       FlwTs STS PE-049FloA TriEsetaSevcWaeSytmnValsPsueTest 515 PE-049F       B Train Essential Service Water System In Vaults Pressure Test STS PE-049A       CompoinEsentiCol Sring Water System PEG ValAPressure s       Test STS P E-O50B      Component Cooling Water System PEG01C Pressure Test STS PE-O5OC       Coinponent Cooling Water System PEG01B Pressure Test STS PE-O5OD       Component Cooling Water System PEG01D Pressure Test STS P-050E   Pressure Test of CCW System RHR Heat Exchangers, and in STS P-050E   Containment Service Loop STS PE-O051       Borated Refueling Water Storage Pressure Test STS PE-052A       Auxiliary Feedwater Pump Turbine Pressure Test STS PE-053A       A Train Auxiliary Feedwater Pressure Test STS P-053B   Auxiliary Feedwater Pressure Test Using Turbine Driven AFW 515 P-053B   Pump STS PE-053C       Essential Service Water To Auxiliary Feedwater Pressure Test STS P-053D   Auxiliary Feedwater Pressure Test Using Condensate Storage 515 P-053D   Tank 5T5 PE-053E       B Train Auxiliary Feedwater Pressure Test STS PE-053F       Essential Service Water to MDAFP A Pressure Test STS PE-053G       Essential Service Water to MDAFP B Pressure Test STS PE-053H       Essential Service Water to TDAFP Pressure Test STS P-055E   Containment Hydrogen Analyzer A Piping through P-1O1 and P-STS P-055E   97 Pressure Test Containment Hydrogen Analyzer B Piping Through P-99 and P-STS P-055F   56 Pressure Test Pressure Test of Containment Hydrogen Control Piping Through STS PE-055G       Pl1adP9 Pressure Test of Containment Hydrogen Control Piping Through STS PE-055H       P99ad-5 Pressure Test of Floor and Equipment Drain Piping Between LF STS PE-055Q       HV-105 and LF HV-106 Pressure Test of Nuclear Sampling Piping through P-64, P-69, STS PE-055W       adP9 WCRE-30                     4.2 Systems Subject to Section XI Pressure Testing Only       Revision 0 Page 3 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN 4.3     WCGS SYSTEMS EXCLUDED FROM SECTION XI PRESSURE TESTING PER iWA-5110(c)
A. Applicable Components The following ASME Class 2 components are excluded from Section XI System Pressure Testing per IWA-5 110(c):
P&ID Number                Line Number(s)                 Penetration M-12BB02                   B B- 103-HCB- 1"                   P-62 M- 12BL0 1                 BL-028-HCB-3"                      P-25 M-12BM01                   BM-053-HBB-3"                      P-78 M-12EC02                   EC-067-HCB-6"                      P-53 M-12EC02                   EC-072-HCB-6"                      P-54 M-12EC02                   EC-08 1-HCB-3"                     P-55 M-12EM01                   EM-071-BCB-3/4"                    P-92 M-12EP01                   EP-055-FBB- 14"                    P-45 M-12GP01                   GP-001-HBB-6"                      P-34 M-12GP01                   GP-003-HBB-I"                      P-5 1 M-12GP01                   GP-005-HBB-1"                      P-5 1 M-12GS01                   GS-025-HBB-6"                      P-65 M-12GT01                   GT-007-HBB-36"                     V-i160 M-12GT0 1                  GT-004-HBB-36"                     V-i161 M-12GT01                   GT-029-HB B-i8"                    V-i161 M-12GT01                   GT-034-HBB-i18"                    V-160 M- 12GT0 1                 GT-033-HBB-1 8"                    V-160 M-12GT01                   GT-030-HBB-1 8"                    V-i161 M-12HB01                   HB-015-HCB-3"                      P-26 M-12HB01                   HB-025-HBB-3/4"                    P-44 M-12HD01                   HD-0 15-HBB-2"                     P-43 M-12KA01                   KA-244-HCB-1 1/2"                  P-30 M-12KA01                   KA-259-HCB-1 1/2"                  P-30 M-1 2KA02                  KA-05 1-HBB-4"                     P-63 M-12KA02                   KA-261-HBB-I"                      P-63 M-12KA05                   KA-732-HB B- 1"                    Personnel Hatch M-12KA05                   KA-733-HB B- 1"                    Personnel Hatch M-12KB01                   KB-001-HCB-2"                      P-98 M- 12KC02                  KC-560-HBB-4"                      P-67 M-12LF09                   LF-842-HCB-6"                      P-32 M-12SJ04                   SJ-024-BCB-l"                      P-57 B.      Classification of Components Details of the classification of the components that are excluded from Section XI System Pressure Testing per IWA-5 110(c) are included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
C.      ASME Class Components A listing of the ASME Class 2 components excluded from Section XI System Pressure Testing per IWA-5 110(c) is included in "Inservice Inspection Classification Basis Document Wolf Creek Generating Station Interval 4".
WCRE-30     4.3 WCGS Systems Excluded From Section XI Pressure Testing Per IWA-5 110(c)             Revision 0 Page 1 of 1

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Attachment A Assessment of the Surface Condition of Dissimilar Metal Welds This attachment provides the report that assesses the surface condition of dissimilar metal (DM) welds scheduled for examination under the requirements of ASME Section XI, Appendix VIII, Supplement 10. The report also addresses the effect that mitigation strategies will have on the ability to perform required examinations.
Scope:
The welds at Wolf Creek that are currently scheduled for examination under Supplement 10 are the DM welds connecting the RV nozzles to the safe-ends of the loop piping. These welds are divided into two groups: The hot leg DM welds, and the cold leg DM welds. The 4 hot leg DM welds have essentially the same configuration, and the 4 cold leg DM welds have essentially the same configuration. The primary difference between the two groups is the length of the safe end. See the measurements and profiles documented in References 4 and 5 (these profiles are discussed in the "Assessment" below). The longer safe ends of the cold leg nozzles allow more coverage to be obtained if examinations are performed from the OD.
NOTE: The DM welds connecting the safe ends to the pressurizer nozzles were overlaid in RF15, Fall 2006. The pressurizer overlaid welds are now examined in accordance with Supplement 11 (as modified by the PDI program) as stated in relief request I3R-05, and are thus excluded from the scope of this document.
B ackground:
The initial PDI examination of the RV DM welds was conducted in RF14, spring of 2005. These exams were conducted from the interior of the RV, on the ID surface of the welds. As part of the examination, ID surface profiling was performed. These profiles are electronically recorded, and are vaulted as part of the RF14 STS PE-300 surveillance data (the profiles are electronically stored with the examination raw data on a hard drive that is in the vault along with the hard copy of the completed surveillance).
The hot leg DM welds were subsequently examined in RF17, and the cold leg DM welds were subsequently examined in RF 18. The exams were performed from the ID, and profiling was again performed (The vendor had refined the profiling software and hardware, resulting in more precise profile data). Again, these profiles are electronically recorded, and are vaulted as part of the RF17/RF1 8 STS PE-300 surveillance data (again the profiles are on a hard drive in the vault with the hard copy of the surveillance).
Assessment:
Measurements and profiles were taken of the OD surface in RF 14 (02-244741-007), and again in RF 16 (06-289464-005) in conjunction with the bare metal visual examinations. The results indicate that it is possible to obtain coverage of the cold leg DM welds from the OD (this is using encoded phased array techniques, not manual examination). However, it is not possible to obtain the required coverage from the OD of the hot leg. This is due to the length of the safe end being longer on the cold leg welds than on the hot leg welds.
As stated in the background above, the subject welds have been examined from the ID, with the ID surface profiles being recorded and vaulted as part of the surveillance data of STS PE-300 performed in RF 14, RFl17 and RF 18 (see background above). The hot leg examinations have achieved 100% coverage in both axial and circumferential directions. The cold leg examinations have achieved 100% coverage in the axial direction (looking for circumferential flaws), but have been limited in the circumferential direction due to presence of internal roughness.
Relief was requested and granted by the NRC to utilize a supplemental eddy current examination in lieu of achieving coverage in the circumferential direction due to the presence of internal surface roughness (reference 6).
The use of the supplemental eddy current on the ID surface is considered to be at least as effective as UT in detecting surface breaking flaws.
WCRE-30                                             Attachment A                                             Revision 0 Page 1 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN Surface Condition Improvement:
Due to the location and configuration of these welds, it is not practical to attempt to improve the surface of these welds unless done in conjunction with a mitigation strategy. As noted in the discussion of mitigation strategy effects below, consideration of the examination surface condition is part of the mitigation strategy selection process.
Mitigation strategy effects:
There are four PWSCC mitigation strategies that are being considered for the RV DM welds. Each strategy is listed along with a discussion of the effect the strategy, if implemented, would have on the examination of the weld. The process of selecting a mitigation strategy includes consideration of the post mitigation examination surface.
Mechanical Stress Improvement Process (MSIP'): This process uses a clamp to deform (squeeze) the piping adjacent to the weld, thus changing the ID wetted surface stress from a tensile stress to a compressive stress. Use of this mitigation strategy would require that the weld examination still be performed in accordance with supplement 10.
MSIP has been demonstrated to have negligible effect on subsequent examinations.
Weld Overlay (WOL):
This process involves the application of weld metal over the existing welds. This process will change the examination surface on the GD surface of the welds. It is required that the GD surface meet the examination specifications after the overlay is applied. If post overlay ISI examinations are performed from the GD surface, then the examinations will not be performed in accordance with supplement 10 (they would be performed in accordance with supplement 11I, as modified by the PDI program, or under an NRC approved alternative). The WOL is required to have a final GD configuration and surface that allows the performance of Supplement 11 exams. If post overlay ISI examinations are performed from the ID surface, then the examinations would be performed in accordance with supplement 10. The WGL mitigation will have negligible effect on subsequent ID exams.
Weld Inlav/Cladding:
This process requires that the ID surface of the weld be machined and then weld metal deposited, isolating the Alloy 82/182 weld metal from the primary water. Use of this mitigation strategy would be expected to improve the ID surface. However, limitations in the initial vendor tooling preclude full restoration of the ID surface to allow full coverage of the DM and SS welds. If this mitigation strategy is selected, the examination would still be performed in accordance with supplement 10, but the inability of the vendor tooling to fully restore the ID surface for improving coverage of subsequent exams significantly limits selection of this technique.
Water Jet Peening:
This process is characterized by the production of cavitation bubbles in a submerged jet. The process involves sweeping ultra high-pressure water jets over the surface to be peened so that cavitation bubbles form and collapse on the work piece. This results in a compressive stress region being created on the surface of the metal and to a depth of about 1 mam. Use of this mitigation strategy would not improve the ID surface for examination purposes. If this mitigation strategy is selected, the examination would still be performed in accordance with supplement 10.

== Conclusion:==

The current process that Wolf Creek utilizes to perform examination of the DM welds is satisfactory. Any attempt at surface improvement would need to be in conjunction with a PWSCC mitigation strategy for these locations.
Mitigation strategies are currently being evaluated and the effect of the mitigation on subsequent examinations is a significant consideration in the evaluation process.
WCRE-30                                            Attachment A                                              Revision 0 Page 2 of 3

WOLF CREEK GENERATING STATION FOURTH INTERVAL ISI PROGRAM PLAN

==References:==
: 1. Incoming correspondence 09-00324: Issuance of Nondestructive Evaluation: "Guideline for Conducting Ultrasonic Examinations of Dissimilar Metal Welds"
: 2. EPRI Report 1018181, Guideline for Conducting Ultrasonic Examinations of Dissimilar Metal Welds
: 3. STS PE-300, Inservice Examinations, RFI4, RF17 and RF18 Vaulted Records
: 4. Work order 02-244741-007
: 5. Work order 06-289464-005
: 6. Correspondence 09-00372: Relief Request 13R-06, Alternative to the Examination Requirements of ASME Code Section XI for Class 1 Piping Welds Examined From the Inside of the Reactor Vessel WCRE-30                                         Attachment A                                        Revision 0 Page 3 of 3

Enclosure II Wolf Creek Unit 1 Internal Events PRA Gap Assessment to Support RI-ISI (22 Pages)

Westinghouse Non-Proprietary Class 3 O Westinghouse To:               File                                                                     Date:    December 18, 2014 cc:               David Gerlis Kyle Christiansen Daniel Sadlon From:             Alexander Rubbicco Ext:              860-731-6375 Fax:
Your Ref:         N/A Our Ref:          LTR-RAM-II-14-083, Rev. 0

==Subject:==
Wolf Creek Unit 1 Internal Events PRA Gap Assessment to Support RI-ISI This letter transmits the results of the completed gap assessment completed on the Wolf Creek Unit 1 internal events probabilistic risk assessment. This assessment determined whether the current Rev. 7 model of record meets the supporting requirements in Table 2-2 of EPRI TR 1021467-A to support the Wolf Creek Unit 1 ten year RI-ISI update.
Author:              Electronically Approved*                         Reviewer:           ElectronicallyApproved*
Alexander Rubbicco                                                   David Gerlits Risk Applications and Methods II                                     Risk Applications and Methods II Manager:             ElectronicallyAprvd Daniel Sadlon -
Resource Manager Risk Applications and Methods II This document is the property of and contains Proprietary Information owned by Westinghouse Electric Company LLC and/or its subcontractors and suppliers. It is transmitted to you in confidence and trust, and you agree to treat this document in strict accordance with the terms and conditions of the agreement under which it was provided to you.
                 *Electronically approvedrecords are authenticatedin the electronic document management system.
                                            &#xa9;2014 Westinghouse Electric Company LLC All Rights Reserved

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 2 of 22 Table of Contents 1.0   Background and Purpose ..........................................................................
1.1   Purpose .............................................................................................. 3 1.2   Background ...........................................................................................
1.1   Open Items ..........................................................................................
2.0   Summary of Results and Conclusions .......................................................... 4 3.0   References .......................................................................................... 5 4.0   Methodology......................................................................................... 6 5.0   Results............................................................................................... 6 5.1   Supporting Requirement Evaluation of ASME/ANS RA-Sb-2005 to ASME/ANS RA-Sa-2009........................................................................................... 6 Appendix A: Customer Comments ..................................................................... 21

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 3 of 22 1.0     Background and Purpose 1.1     Purpose This report documents the evaluation of the Wolf Creek Unit 1 internal events probabilistic risk assessment (PRA) model with respect to the supporting requirements required by Table 2-2 in Electric Power Research Institute (EPRI) Technical Report (TR) 1021467-A (Reference 1). The supporting requirements contained in this technical report relate to the PRA standard endorsed in Regulatory Guide 1.200 Rev. 1 (Reference 2). The supporting requirements in the associated table will first be correlated to their appropriate RA-Sa-2009 (Reference 5) supporting requirement equivalent, which is endorsed in Regulatory Guide 1.200, Rev. 2 (Reference 3).
Subsequently, the model will be evaluated based on the intent and wording of the supporting requirements in the American Society of Mechanical Engineers (ASME)/American Nuclear Society (ANS) PRA Standard RA-Sa-2009 (Reference 5). This evaluation follows methodology, guidance and justification found in EPRI TR 1021467-A (Reference 1).
1.2     Background Wolf Creek Nuclear Operating Corporation (WCNOC) developed an EPRI risk-informed in-service inspection (RI-ISI) program for Wolf Creek Generating Station (WCGS). One aspect of a RI-ISI program is to maintain the RI-ISI program as a living program. The RI-ISI program is required to be reviewed and updated every ten years of commercial operation. That analysis allows for WCNOC to update the PRA program to meet the requirements of EPRI TR 1021467-A (Reference 1) Traditional Approach. As part of the application of this methodology the PRA must meet the supporting requirements mentioned in EPRI TR 1021467-A (Reference 1) Traditional Approach. This letter will document whether the current Rev. 7 model of record meets these supporting requirements and will also document any gaps associated with not meeting these requirements.
1.1     Open Items
: 1. The newest HRA document and associated supporting MAAP timings (References 7 and
: 12) have not been formally approved but have been completed and reviewed by Wolf Creek. As part of this open item the dependency analysis has also not been completed.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II- 14-083, Rev. 0 Page 4 of 22 2.0     Summary of Results and Conclusions Evaluating WCNOC current PRA to date against the supporting requirements outlined in the EPRI technical report, as required to be met to implement the technical report's methodology found that many of the required supporting requirements were fulfilled. Noted deficiencies during the 2006 peer review (Reference 6) related to human reliability analysis, initiating events, Level 2 and quantification have been sufficiently rectified by issuance of additional documentation and analysis. This documentation has been issued relatively recently and includes roadmaps for meeting the PRA standard explicitly at Capability Category (CC) I1.
Additionally, many of the supporting requirements required per the EPRI technical report were previously assessed as met during the 2006 peer review at least the required level (often CC-I) or higher.
As such, several supporting requirements were found to no__t meet the entire intent of the supporting requirement. It was assessed that they meet the majority of the intent of the supporting requirement but needed additional analysis to be fully met. This specifically relates to supporting requirements HR-A3 and DA-D3 in which the original F&Os have not been resolved.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 5 of 22 3.0     References
: 1. EPRI TR-1021467-A, "Nondestructive Evaluation: Probabilistic Risk Assessment Technical Adequacy Guidance for Risk-Informed In-Service Inspection Programs," June 2012.
: 2. Regulatory Guide 1.200, Revision 1, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities,"
USNRC, January 2007.
: 3. Regulatory Guide 1.200, Revision 2, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities,"
USNRC, March 2009.
: 4. RA-Sb-2005, "Addenda to ASME RA-S-2002 Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications," American Society of Mechanical Engineers, New York, NY, December 2005.
: 5. ASME/ANS-Ra-Sa-2009, Addenda to ASME/ANS RA-S-2008 Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, ASME, 2009.
: 6. Review of the Wolf Creek Generating Station Probabilistic Risk Assessment Against the Requirements of the ASME PRA Standard (Addenda B), October 2006.
: 7. WCNOC-PSA-HRA, "Wolf Creek Generating Station Human Reliability Analysis           - Post Initiators," Rev. 0-A DRAFT.
: 8. WCNOC-PSA-001, "Wolf Creek Generating Station PSA Initiating Event Analysis," Rev.
1, September 2013.
: 9. PSA-09-005, "WCGS PRA Level 2 Update," Rev. 0.
: 10. WCNOC-PSA-022, "Accident Sequence Quantification," Rev. 0, September 2013.
: 11. PSA-05-0021, "Pre-Initiator Human Reliability Analysis," Rev. 0, March 2006.
: 12. LTR-RAM-II-14-051, "Wolf Creek MAAP Analyses to Support HRA Timings," Rev. 0-A DRAFT.
: 13. WCNOC-PSA-003, "Wolf Creek Generating Station PSA Accident Sequence Analysis,"
Rev. 0, September 2013.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 6 of 22 4.0     Methodology The WCNOC Rev. 7 model of record and any associated supporting documentation will be evaluated based on the supporting requirements as outlined in Table 2-2 of EPRI TR 1021467 (Reference 1). The supporting requirements in this table are based on the ASME/ANS RA-Sb-2005 PRA standard (Reference 4). As it is currently required that PRA models must meet ASME/ANS RA-Sa-2009 (Reference 5) per Regulatory Guide 1.200, Rev. 2 (Reference 3),
the supporting requirements in Table 2-2 of EPRI TR-1 021467 (Reference 1) are assessed and matched to their equivalent ASME/ANS RA-Sa-2009 (Reference 5) requirement.
The next step in this report is to evaluate the WCNOC PRA model and any associated documentation to the supporting requirements (and their 2009 equivalents) found in the EPRI technical report. This was completed by evaluating the results of the 2006 WCNOC PRA review.
Any of the supporting requirements met during this peer review and which were not changed in the update to ASME/ANS RA-Sa-2009 (Reference 5) were again assessed as met. For supporting requirements not met (either partially or fully) or for supporting requirements in which the wording or intent was changed were re-assessed to determine whether they were met at least the level of requirement required by the EPRI TR.
5.0     Results 5.1     Supporting Requirement Evaluation of ASME/ANS RA-Sb-2005 to ASME/ANS RA-Sa-2009 As noted previously, Table 2-2 of EPRI TR 1021467-A (Reference 1) contains the supporting requirements to implement the EPRI Traditional RI-ISI methodology. This table contains the supporting requirements as found in the ASME/ANS RA-Sb-2005 PRA standard (Reference 4).
This section will evaluate this standard to the revised version of the standard (ASME/ANS RA-Sa-2009) (Reference 5) which is the latest PRA standard endorsed by the NRC in Regulatory Guide 1.200 Rev. 2 (Reference 3). This analysis is shown in Table 5.1-1.
Table 5.1-1: Assessment of ASME/ANS RA-Sb-2005 versus ASMEIANS RA-Sa-2009 Capability Required        Category Supporting        Required RA-Sa-2009 Requirement for RI-ISI            Equivalent             Assessment*
AS-Al10           I             AS-Al10          None, no change to text.
AS-A7             Il/I          AS-A7            None, no change to text.
AS-A9             II            AS-A9            None, no change to text.
DA-B1             I              DA-B1           None, no change to text.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 7 of 22 Table 5.1-1: Assessment of ASMEIANS RA-Sb-2005 versus ASMEIANS RA-Sa-2009 Capability Required        Category Supporting       Required        RA-Sa-2009 Requirement for RI-ISI            Equivalent             Assessment*
DA-B2            II/I            DA-B2           None, no change to text.
DA-C7            I               DA-C7           None, no change to text.
DA-C9            II/I            DA-C9           None, no change to text.
HR-B1            I               HR-B1           None, no change to text.
HR-C2            I               HR-C2           None, no change to text.
HR-D2            I               HR-D2           None, no change to text.
HR-D3            I               HR-D3           None, no change to text.
HR-D7            Il/I            HR-D7           None, no change to text.
HR-E3            I               HR-E3           None, no change to text.
HR-E4            I               HR-E4           None, no change to text.
HR-Fl            Il/I            HR-Fl           None, no change to text.
HR-F2            I               HR-F2           None, no change to text.
HR-G1            I               HR-G1           None, no change to text.
HR-G3            I               HR-G3           None, no change to text.
HR-G4            I               HR-G4           None, no change to text.
HR-G5            I               HR-G5           None, no change to text.
HR-HI            I               HR-HI           None, no change to text.
IE-A3a           II/I            IE-A4           None, no change to text.
IE-A4            I               IE-A5           None, no change to text.
IE-A4a           I               IE-A6           None, no change to text.
IE-A6            I               IE-A8           None, no change to text.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 8 of 22 Table 5.1-1: Assessment of ASMEIANS RA-Sb-2005 versus ASMEIANS RA-Sa-2009 Capability Required       Category Supporting       Required      RA-Sa-2009 Requirement      for RI-ISI     Equivalent             Assessment*
IE-A7            I              IE-A9           None, no change to text.
None, minor wording IE-B3            I              IE-B3           change, no impact on PRA.
Wording change, PRA model should be reviewed to assure the new wording is IE-C11           II/I           IE-C13          met.
IE-C12           Il/I           IE-C14          None, no change to text.
None, corrected the referenced table number, no LE-B1                           LE-B1           impact on PRA.
None, minor wording LE-B2            I              LE-B2           change, no impact on PRA.
None, minor wording LE-C1            I              LE-CI           change, no impact on PRA.
LE-C10           I              LE-C13          None, no change to text.
LE-C2a           I              LE-C2           None, no change to text.
None, minor wording LE-C2b           I              LE-C3           change, no impact on PRA.
Only changes to the referenced SR # are made.
No changes have been LE-C3            ILE-C4                         made to those SRs.
LE-C4            I              LE-C5           None, no change to text.
LE-C8a           I              LE-C9           None, no change to text.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 9 of 22 Table 5.1-1: Assessment of ASMEIANS RA-Sb-2005 versus ASME/ANS RA-Sa-2009 Capability Required       Category Supporting      Required     RA-Sa-2009 Requirement      for RI-ISI   Equivalent              Assessment*
LE-C8b          I            LE-C1 0          None, no change to text.
LE-C9a          I            LE-C11I          None, no change to text.
LE-C9b          I            LE-C12           None, no change to text.
LE-DIla         I            LE-D1            None, no change to text.
None, minor wording LE-Dlb          I            LE-D2            change, no impact on PRA.
LE-D2           I            LE-D3            None, no change to text.
LE-D3        -I              LE-D4            None, no change to text.
LE-D4           I            LE-D5            None, no change to text.
LE-D5           I            LE-D6            None, no change to text.
LE-D6           I            LE-D7            None, no change to text.
LE-E2           I             LE-E2           None, no change to text.
LE-E3           I             LE-E3           None, no change to text.
None, reduced back-references from QU-A, B, &
C to QU-A & B. No impact LE-Fla          I            LE-F1            on PRA.
LE-G3           I            LE-G3            None, no change to text.
QU-A2b          I            QU-A3            Minor wording changes.
QU-D3           I            QU-D4            None, no change to text.
QU-D5a          I            QU-D6            None, no change to text.
QU-E3           I            QU-E3            None, no change to text.

Westinghouse Non-Proprietary Class 3 LTR-RAM-JI-I14-083, Rev. 0 Page 10 of 22 Table 5.1-1: Assessment of ASME/ANS RA-Sb-2005 versus ASMEIANS RA-Sa-2009 Capability Required        Category Supporting       Required       RA-Sa-2009 Requirement       for RI-ISI      Equivalent              Assessment*
QU-F3            I              QU-F3             None, no change to text.
SC-A2            I               SC-A2            None, no change to text.
SC-A5            I               SC-.A5           None, no change to text.
SC-B1I           I               SC-BI            None, no change to text.
SC-B2            II              SC-B2            None, no change to text.
SY-A15           Il/I            SY-A16           None, no change to text.
SY-A20           I               SY-A22           None, no change to text.
SY-A4            I               SY-A4            None, no change to text.
SY-A7            II/I            SY-A7            None, no change to text.
SY-B1            I               SY-B1            None, no change to text.
SY-B11I          I               SY-B1 0          None, no change to text.
SY-B2            II/I            SY-B2            None, no change to text.
SY-B7            I               SY-B7            None, no change to text.
 &deg;upoaaes torequirement.
supporting    me woraing to correct errors, reierences, linlKS or etc. are not consiaerea cnanges to tie Based on this assessment the appropriate supporting requirements are assessed starting from the peer review performed at Wolf Creek in 2006. As noted previously this peer review was completed to the ASME/ANS RA-Sb-2005 (Reference 4) version of the PRA standard. The supporting requirements contained in Table 5.1-1 were first evaluated to the previously performed peer review. If the supporting requirement was met and there were no changes to the wording or intent of the supporting requirement from 2005 to 2009, then the supporting requirement will be assessed as met. The supporting requirements required to meet the EPRI RI-ISI are evaluated in Table 5.1-2 and are assessed to determine if they are met or not met based on the current model of record and the associated documentation available at the time of this assessment.
Note: the peer review was completed evaluating the WCNOC PRA model and documentation at CC-Il. Therefore, if a supporting requirement is assessed as previously met, it is at least met at CC-Il or higher. As the EPRI technical report only requires that at most CC-Il be met, no

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 11 of 22 designation is generally given for at what capability category the supporting requirement is met at.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 12 of 22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category       RA-Sa-2009 Requirement         Required for RI-ISI      Equivalent                        2006 Peer Review Assessment AS-A10O                                    AS-A10                  Previously   met and satisfied.
AS-A7                II/I                  AS-A7                   Previously   met and satisfied.
AS-A9                II                    AS-A9                   Previously   met and satisfied.
DA-B1I                                     DA-B1                   Previously   met and satisfied.
DA-B2                Il/I                  DA-B2                   Previously   met and satisfied.
DA-C7                IDA-C7                                        Previously   met and satisfied.
DA-C9                Il/I                  DA-C9                   Previously   met and satisfied.
HR-B1I                                     HR-B1                   Previously   met and satisfied.
In the 2006 peer review only the portion related to generic operating experience was not met. As this is a requirement to meet CC-I I/Ill and CC-I it specifically excludes this portion of the requirement, therefore this SR is met at CC-I and satisfies the EPRI TR requirement for this supporting requirement. This analysis is contained in PSA-05-021, Rev.
HR-C2                IHR-C2                                        0 (Reference 11).
HR-D2                IHR-D2                                        Previously met and satisfied.
HR-D3                IHR-D3                                        Previously met and satisfied.
HR-D7                Il/I                  HR-D7                   Previously met and satisfied.
The inclusion of operator interviews has been completed in Reference 7 and the associated HRA Calculator attachment file. Therefore this supporting requirement is judged to be met at CC-Il which exceeds the requirement found in the HR-E3                                      HR-E3                   EPRI technical report.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 13 of 22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category       RA-Sa-2009 Requirement         Required for RI-ISI      Equivalent                       2006 Peer Review Assessment While it was found during the 2006 peer review that Wolf Creek did not meet CC-Il/Ill, there is no specific requirement or action for meeting CC-I. Therefore it is assessed that this HR-E4                IHR-E4                                       SR is met for use with the EPRI technical report.
HR-Fl                IlI/                  HR-Fl                   Previously met and satisfied.
This has been completed in Reference 7 and the associated HRA Calculator attachment file. Therefore this supporting requirement is judged to be met at CC-Il which exceeds the HR-F2                IHR-F2                                        requirement found in the EPRI technical report.
HR-G1I                                     HR-G1                   Previously met and satisfied.
This has been completed in Reference 7 and the associated HRA Calculator attachment file. Therefore this supporting requirement is judged to be met at CC-Il which exceeds the HR-G3                IHR-G3                                       requirement found in the EPRI technical report Thermal-hydraulic analyses have been performed in Reference 12. This document uses thermal-hydraulic analyses to support associated HRA timings. Therefore, this supporting requirement is assessed to at least meet CC-Il of HR-G4                                      HR-G4                  this supporting requirement.
This has been completed in Reference 7 and the associated HRA Calculator attachment file. Therefore this supporting requirement is judged to be met at CC-Il which exceeds the HR-G5                                      HR-G5                  requirement found in the EPRI technical report.
This has been completed in Reference 7 and the associated HRA Calculator attachment file. Therefore this supporting requirement is judged to be met at CC-Il which exceeds the HR-Hi                                      HR-HI                  requirement found in the EPRI technical report.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 14 of 22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category        RA-Sa-2009 Requirement         Required for RI-ISI       Equivalent                        2006 Peer Review Assessment Met at least CC-li in WCNOC-PSA-001, Section 2.2.2 (Reference 8). Specifically the Licensee Event Reports were evaluated to determine whether any trip or unidentified initiating event occurred. If it was found to be a relevant plant trip or initiating event, it was included in the PRA IE-A3                Il/I                  IE-A3                   model.
A systematic approach for assessing the possibility of an initiating event occurring due to the failure of a system is performed WCNOC-PSA-O01, Rev. 1, Section 2.4, (Reference 8). A system by system evaluation approach was taken to ensure that all system initiating events were IE-A4                                      IE-A5                   considered.
While there is no explicit discussion of maintenance alignments within WCNOC-PSA-OO1 Rev. 1 (Reference 8) review of the system initiator models indicate that maintenance alignments are taken into consideration along with common cause failure. Therefore, CC(-1l is assessed as IE-A4a                           I         IE-A6                   met.
Interviews documented in WCNOC-PSA-OO1, Rev. 1, IE-A6               IIE-A8                                        Appendix A (Reference 8).
Previously not met. Specifically evaluated and addressed in WCNOC-PSA-001, Sections 2.2.2 and 2.2.3 (Reference 8) through review of the licensee event reports, outage history IE-A7                                      IE-A9                   and analysis of similar plants to WCNOC. Met at CC-Il.
Initiating events are created in WCNOC-PSA-O01, Rev. 1, Section 3 (Reference 8). While initiating events are grouped, they are not subsumed and are shown independently.
IE-B3                                      IE-B3                  Therefore this supporting requirement is met at CC-Il.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II- 14-083, Rev. 0 Page 15 of22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category       RA-Sa-2009 Requirement         Required for RI-ISI      Equivalent                         2006 Peer Review Assessment Initiating events are calculated appropriately using generic or plant data as appropriate in WCNOC-PSA-001, Rev. 1, IE-C11               Il/I                  IE-C13                  Section 4 (Reference 8). Met at CC-I/Il.
IE-C12               Il/I                  IE-C14                  Previously met and satisfied.
Met in PSA-09-0005 Sections 3.1.3 and 3.2 (Reference 9) based on the items required to be analyzed which were identified in the ASME/ANS Standard Table 2-2.8-3. Met at LE-B1I                                     LE-B1                   CC-Il.
LE-B2                ILE-B2                                        Previously met and satisfied.
LE-C1i                                     LE-C1                   Previously met and satisfied.
Containment bypass considered and analyzed in PSA                                                                   0005 (Reference 9) in Sections 2, 3.1.3, 3.2.1 3.2.2, 4.1 and LE-C10                                     LE-C13                 6.4.4. Met at CC-II.
Operator actions related to SAMG guidance are included and documented in PSA-09-0005 Section 2 and Section 3 (Reference 9). For example, actions are credited for low pressure injection, reactor coolant system depressurization, thermally induced steam generator tube ruptures, and pressure induced steam generator tube ruptures. Therefore, LE-C2a              _________LE-C2                                this SR is met at CC-Il.
This supporting requirement is met in PSA-09-0005 Section 6.2.4 (Reference 9) which evaluates whether equipment can LE-C2b                                     LE-C3                  be repaired to prevent a release. Met at CC-Il.
Met at CC-Il and evaluated in PSA-09-0005 in Section 3.2 LE-C3                ILE-C4                                       (Reference 9).
LE-C4                ILE-C5                                        Previously met and satisfied.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 16 of 22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category       RA-Sa-2009 Requirement         Required for RI-ISI      Equivalent                       2006 Peer Review Assessment Equipment survivability is considered in PSA-09-0005 Sections 3.2.10 and 3.2.11 (Reference 9). Operator actions credited are usually evaluated to have a relatively high human error probability (e.g., OPA-LEV2-RCSDEP).
LE-C8a                                     LE-C9                   Therefore this SR is met at CC-Il.
Assessed and documented in PSA-09-0005 in Section 6.2.4 LE-C8b               ILE-C10                                       (Reference 9).
No actions, credit or equipment is justified to be operable following the failure of containment. Therefore CC-I is met LE-C9a                                     LE-C1 1                as required by the EPRI technical report.
No actions, credit or equipment is justified to be operable following the failure of containment. Therefore CC-I is met LE-C9b               I                     LE-C12                 as required by the EPRI technical report.
LE-D1A               ILE-D1                                        Previously met and satisfied.
LE-DIB               ILE-D2                                        Previously  met and  satisfied.
LE-D2                ILE-D3                                        Previously  met and  satisfied.
LE-D3                I__________LE-D4                              Previously  met and  satisfied.
LE-D4                I__________LE-D5                              Previously  met and  satisfied.
Met in PSA-09-0005 Section 3.2 with associated sensitivities LE-D5                ILE-D6                                       in Section 6 (Reference 9).
LE-D6                ILE-D7                                        Previously met and satisfied.
WCNOC used split fractions other than 1/0 in developing their accident progression event trees. This is documented LE-E2                                      LE-E2                  in PSA-09-0005, Section 3.2 (Reference 9). Therefore, CC-Il

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 17 of 22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category      RA-Sa-2009 Requirement        Required for RI-ISI      Equivalent                        2006 Peer Review Assessment is assessed as met.
WCNOC has developed P0S and CET evaiuations in Section 3.2 of PSA-09-0005 (Reference 9). Therefore, CC-Il LE-E3                ILE-E3                                       is assessed as met.
Evaluated in the quantitative evaluation performed in PSA-LE-F1A               ILE-F1                                      09-0005 in Section 6.2.3 at CC-II (Reference 9).
Relative contribution of contributors is performed in PSA                                                                  0005 in Sections 6.1 and 6.2 (Reference 9). This supporting LE-G3                                     LE-G3                  requirement is met at CC-Il.
Evaluated in Section 5.0 of WCNOC-PSA-022, Rev. 0.
Additionally SOKC is evaluated by using type codes when QU-A2b                                    QU-A3                   parametric uncertainty is evaluated. This SR is met at CC-Il.
Evaluated in Section 9.0 of WCNOC-PSA-022, Rev. 0 QU-D3                                     QU-D4                  (Reference 10). Met at CC-Il.
Evaluated in Sections 5.0 and 7.0 of WCNOC-PSA-022, QU-D5a                                    QU-D6                  Rev. 0 (Reference 10). Met at CC-Il.
Evaluated in Section 8.1 of WCNOC-PSA-022, Rev. 0 QU-E3                                     QU-E3                  (Reference 10). Met at CC-Il.
Evaluated in Sections 5.0 and 7.0 of WCNOC-PSA-022, QU-F3                IQU-F3                                      Rev. 0 (Reference 10). Met at CC-Il.
SC-A2                ISC-A2                                      Previously met and satisfied.
This supporting requirement is met at CC-I as WCNOC considers a mission time of at least 24 hours in WCNOC-PSA-0003 (Reference 13). As noted in the peer review report, CC-Il could be met with additional documentation SC-A5                                     SC-AS                  upgrades, but these are not needed to meet the

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 18 of 22 Table 5.1-2: Assessment of the Supporting Requirements Against the Current WCNOC PRA Required Supporting       Capability Category       RA-Sa-2009 Requirement         Required for RI-ISI      Equivalent                        2006 Peer Review Assessment requirements for use of the EPRI technicai report.
SC-B1I                                     SC-B1                   Previously met at CC-I and therefore satisfied.
SC-B2                II                    SC-B2                   Previously met and satisfied.
While it was noted in the peer review this supporting requirement has only partially met the significance of the finding is low. This is mainly related to a documentation issue in which proper referencing of the analysis was not completed. As it is a documentation issue and is rated as a Category D finding, not resolving this finding would not impact the use of the EPRI RI-ISI methodology. Excluding pre-initiator human failure events would only increase the importance and contribution to risk from other components SY-A15               Il/I                  SY-A16                 that make of the system fault tree model.
SY-A20               ISY-A22                                       Previously met and satisfied.
This supporting requirement was previously met in the 2006 peer review at CC-I and therefore meets the requirements SY-A4                I                     SY-A4                  for using the EPRI technical report.
SY-A7                Il/I                  SY-A7                   Previously met and satisfied.
SY-B 1               ISY-B1                                        Previously met and satisfied.
SY-B11i                                    SY-B10                  Previously met and satisfied.
SY-B2                Il/I                  SY-B2                  Previously met and satisfied.
SY-B7                I__________SY-B7                              Previously met and satisfied.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 19 of 22 Additionally, any significant F&Os that were found during the 2006 must be closed out regardless of whether the EPRI RI-ISI technical report specifies that a capability category be met with the exception of internal flooding as it is normally a model on its own that does not impact non-internal flooding parts of the PRA. As the peer review was completed using older methodology, all findings or discrepancies were noted as F&Os and ranked based on a qualitative scale from A to D. Based on the new peer review methodology that is practiced today, C and D level findings are considered non-significant to the results or methodology and are now labeled as "suggestions."
Suggestions are not required to be closed out to submit the PRA for applications while F&Os require that a resolution be created and documented. Based on Table 4-2 of Reference 6, Table 5.1-3 shown below evaluates whether these significant F&Os were properly resolved. All supporting requirements shown in this table were categorized at a B level from Reference 6.
Table 5.1-3: Assessment of the Supporting       Requirements of B Category F&Os RA-Sa-2009 Supporting Requirement               Equivalent               Evaluation IE-A4                                IE-A5                    Previously evaluated in Table 5.1-2.
IE-A4a                               IE-A6                    Previously evaluated in Table 5.1-2.
IE-A7                                IE-A9                    Previously evaluated in Table 5.1-2.
IE-B3                                IE-B3                    Previously evaluated in Table 5.1-2.
The initiating event frequency is calculated using generic and plant specific data in Section 4.0 of Reference 8. Parametric uncertainty values are also provided for each specific IE-C1                                IE-C1                    initiating event.
Initiating event frequencies were calculated based on reactor year in Section 4.0 of Reference 8. Additionally, a plant availability factor is considered in Section 4.2 of I-3IE-C5                                             Reference 8.
Bayesian updating performed in Section 4.2 of I-4IE-C6                                             Reference 8 as appropriate.
Evaluated and documented in Section 4.0 of AS-B3                                AS-B3                    Reference 13.
SC-E31                               SC-B1                    Previously evaluated in Table 5.1-2.
A review and effort to document practices that involve mechanisms that simultaneously affect equipment in diverse systems was not completed. Therefore this supporting HR-A3                                HR-A3                    requirement is not met.
HR-G4                                HR-G4                    Previously evaluated in Table 5.1-2.
HR-H3                                HR-H3                    See open item 1.
Not met, some testing and maintenance events still lack parametric uncertainty values. It is recommended a comprehensive review be performed to ensure all fault tree model data includes the proper parametric uncertainty DA-DJ3                               DA-D3                    values.
QU-A4                                QU-A5                    Met in Section 3.3 of Reference 10.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 20 of 22 Table 5.1-3: Assessment of the Supporting Requirements of B Category F&Os RA-Sa-2009 Supporting Requirement         Equivalent               Evaluation Met in Section 4.0 and associated subsections QU-B2                          QU-B2                    of Reference 10.
Not applicable. A single top-logic linked fault QU-C3                          QU-C3                    tree is used rather than linking of event trees.
Evaluated in Section 5.0 Table 5-6 of QU-D4                          QU-05                    Reference 10.
Met in Section 8.4 of Reference 10 for the QU-E4                          QU-E4                    quantification process.
LE-B1                          LE-B1                    Previously evaluated in Table 5.1-2.
LE-C2a                         LE-C2                    Previously evaluated in Table 5.1-2.
LE-E2                          LE-E2                    Previously evaluated in Table 5.1-2.

Westinghouse Non-Proprietary Class 3 LTR-RAM-II-14-083, Rev. 0 Page 21 of 22 Appendix A: Customer Comments

Westinghouse Non-Proprietary Class 3 LTR-RAMIvI--14-083, Rev. 0 Page 22 of 22 Table A-I: Customer Comments and Resolutions______
Customer Reference  Comment(s):                            Comment        Comment Resolution:                   Resolution Comment  Document                                          Prepared                                             Prepared Number:  SectionByy
: 1. All        Document should be Non-Proprietary JC Patel           Agreed, document classification was   AAR Class 3.                              ______changed            to class 3.                   _____
: 2. All        Several instances of AMSE appear in David             Corrected.                            AAR the document.                         Alford}}