L-2024-129, Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval

Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval

ML24220A148
Person / Time
Site:	Saint Lucie  (NPF-016)
Issue date:	08/07/2024
From:	Rasmus P Florida Power & Light Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
L-2024-129
Download: ML24220A148 (1)

Text

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 RE:

St. Lucie Nuclear Plant Unit 2 Docket No. 50-389 Renewed Facility Operating License NPF-16 L-2024-129 10 CFR 50.55a(g)(5)(iii)

August?, 2024 Relief Request (RR) #14. Limited Coverage Exams Due to Impractical lnservice Inspection Requirements - Fourth Ten-Year lnservice Inspection Program Interval Pursuant to 1 O CFR 50.55a(g)(5)(iii), Florida Power & Light Company (FPL) requests for St. Lucie Nuclear Plant, Unit 2 (St. Lucie Unit 2), relief from selected inservice inspection (ISi) requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, on the basis that compliance with the ISi examination requirements is impractical. As required by 1 O CFR 50.55a(g)(5)(iii),

relief is being requested from the impractical examination requirements by no later than twelve months following expiration of the Fourth 10-Year ISi Interval for St. Lucie Unit 2, which ended August 7, 2023.

The enclosure to this letter provides FPL's basis for the determination of impracticality and an evaluation of proposed alternative. The proposed alternative provides an acceptable level of quality and safety by providing reasonable assurance of the structural integrity of the subject examination areas. FPL requests approval of the enclosed relief request within one year of satisfactory acceptance review.

This letter contains no new regulatory commitments.

Should you have any questions regarding this submittal, please contact Mr. Kenneth Mack, Licensing and Regulatory Compliance Senior Manager, at 561-904-3635.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on the 7th day of August 2024.

Sincerely, d111a------

Paul Rasmus General Manager, Regulatory Affairs Enclosure cc:

USNRC Regional Administrator, Region II USNRC Project Manager, St. Lucie Nuclear Plant, Units 1 and 2 USNRC Senior Resident Inspector, St. Lucie Nuclear Plant, Units 1 and 2 Mr. Clark Eldredge, Florida Department of Health Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#l4, REVISION 0 Proposed Alternative In Accordance With 10 CFR 50.55a(g)(5)(iii)

--lnservice Inspection Impracticality--

1.0 ASME Code Component(s) Affected Class 1 and 2 pressure retaining welds in piping under risk informed (Rl)-ISI.

2.0 Applicable ASME Code Edition and Addenda L-2024-129 Enclosure The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Rules for lnservice Inspection of Nuclear Power Plant Components,Section XI, 2007 Edition with Addenda through 2008 as amended by 1 OCFR50.55a, is the code of record for the St. Lucie Unit 2, 4th 10-year interval.

3.0

Applicable Code Requirement

In the safety evaluation dated August 10. 2015 (ML 1495A 196), the NRG authorized the licensee to implement RR#7, a risk informed (Rl)-ISI program, as an alternative to the ASME Code,Section XI, ISi requirements for Class 1 (i.e., Examination Category B-F and B-J) and Class 2 (i.e.,

Examination Category C-F-1 and C-F-2) piping welds in the fourth 10-year ISi interval of St. Lucie Unit 2. The risk informed program was developed in accordance with the NRG-approved methodology of Electric Power Research Institute (EPRI) Topical Report (TR)-112657, Revision B-A, "Revised Risk-Informed lnservice Inspection Evaluation Procedure," (ML013470102).

Exam Cat.

Item No.

Examination Requirements R-A R1.11 Essentially 100% volumetric examination of the circumferential welds. Risk Informed Selection.

R-A R1.16 Essentially 100% volumetric examination of the circumferential welds. Risk Informed Selection.

R-A R1.20 Essentially 100% volumetric examination of the circumferential welds. Risk Informed Selection.

Page 1 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#14, REVISION 0 L-2024-129 Enclosure ASME Section XI requires examination of 100 percent of the weld length as defined in the applicable Code Tables and shown in the applicable Code Figures. The alternative requirements of ASME Section XI, Code Case N-460, approved for use in Regulatory Guide 1.147, Revision 20, allow credit for essentially 100 percent coverage of welds provided greater than 90 percent of the required volume has been examined.

1 O CFR 50.55a(b)(2)(xv)(A) requires the following examination coverage when applying Supplement 2 to Appendix VII I:

(1)

Piping must be examined in two axial directions, and when examination in the circumferential direction is required, the circumferential examination must be performed in two directions, provided access is available.

(2)

Where examination from both sides is not possible, full coverage credit may be claimed from a single side for ferritic welds. Where examination from both sides is not possible on austenitic welds, full coverage credit from a single-side may be claimed only after completing a successful single-side Appendix VIII demonstration using flaws on the opposite side of the weld.

4.0 Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the 100 percent coverage of the subject weld(s) due to geometric or design configuration, which limited the examination coverage that can be obtained. Due to St. Lucie Unit 2's use of the Risk-Informed ISi concept, the welds examined within the Risk Segment were selected to gain the highest examination coverage possible.

In the case of austenitic piping welds, there is currently no Performance Demonstration Initiative (POI) qualified single-sided examination procedures which have been demonstrated to provide equivalency to dual-sided examination procedures. Current technology cannot reliably detect or size flaws on the far side of an austenitic weld. POI Performance Demonstration Qualification Summary (PDQS) certificates for austenitic piping list the limitation that single-sided examinations are performed on a "best-effort" basis. The "best-effort" statement is provided in place of a complete single-side qualification to demonstrate that the examiner's qualification and any subsequent weld examinations are based on applying the best available technology.

Relief is requested from compliance with the essentially 100 percent required examination coverage for piping welds listed in the tables based on the geometric configurations that limited examination access. The coverage obtained during the examination for single sided exams have no code coverage credit taken for the far side of the weld (i.e., no austenitic weld will have greater than 50 percent coverage).

Preservice examinations with limitations resulting in coverage <90 % are detailed in Table U2 PSI and Figures 1-10. Preservice welds met the requirements of ASME Section Ill prior to PSI Examination.

lnservice examinations with limitations resulting in coverage <90 % are detailed in Table U2-14-ISI and Figures 11-16 5.0 Burden Caused by Compliance For the Class 1 stainless steel piping welds selected per the guidelines of the RI-ISi Program, the limitations listed in Table U2-14-ISI are limited by their design configurations. Single-side coverage was obtained for the pipe-to-valve weld configuration, and limited dual-side coverage was obtained for other weld configurations as noted.

Page 2 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#14, REVISION 0 L-2024-129 Enclosure Overall, it is only possible to obtain UT interrogation of greater than 90% of the required code examination volume or surface areas for the inservice welds in this request with extensive weld or component design modifications. Examinations have been performed to the maximum extent possible, and radiography is impractical due to the amount of work being performed in the areas on a 24-hour basis when the welds are available for examination. Using radiography would result in numerous work-related stoppages and increased exposure due to the shutdown and startup of other work in the areas. Water may need to be drained from systems or components where radiography is performed, which increases the radiation dose rates over a much broader area than the weld being examined. Significant impracticality is associated with the performance of weld or area modifications or the use of radiography to increase the examination coverage.

The UT examination techniques used for welds in this request for relief were reviewed to determine If additional coverage could be achieved by improving those techniques. None could be identified, and the examinations were performed to the maximum extent possible. Therefore, St. Lucie has determined that obtaining essentially 100% coverage is not feasible and impractical without adding additional burden consisting of significant redesign work, increased radiation exposure, and/or potential damage to the plant or the component itself.

6.0 Proposed Alternative and Basis for Use The subject welds received a volumetric examination to the maximum extent practical, utilizing the best available techniques as qualified through POI. The POI technique was used to examine the far side of the weld using the search unit angle(s) and frequencies as required by the POI Generic procedure (PDI-UT-2). Additionally, a visual (VT-2) examination was performed for each refueling outage on the applicable system as required by ASME Section XI.

Based on the volumetric examination coverage obtained with acceptable results and the visual (VT-

2) examination performed each refueling outage with acceptable results, it is reasonable to conclude that service-induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of the structural integrity of the subject welds.

7.0 Duration of Proposed Alternative Relief is requested for the Fourth 10-year lnservice Inspection interval for St. Lucie Nuclear Plant, Unit 2, which began on August 8, 2013, and ended on August 7, 2023 8.0 Precedents Note: Industry requests for relief due to impracticality associated with limited weld examinations are common and are filed by all licensees. Some of the more recent NRC approvals of requested relief are:

1.

Seabrook Unit 1 - Relief Requests 31R-18 and 31R-19, relief from the requirements of the ASME Code (EPID L-2021-LLR-0098) dated August 18, 2021. (Accession No. ML21230A157)

2.

Point Beach Nuclear Plant Units 1 and 2 -

Relief RR-4L3 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),

Section XI, for the fourth 10-year lnservice Inspection interval (Tac Nos. MF1144 and MF1145)

(Accession No. ML13079A144).

3.

St. Lucie Unit 1 - Safety Evaluation for Relief Request RR-15, Revision 0, regarding limited piping examinations (EPID L-2019-LLR-0018) dated February 7, 2019. (Accession No. ML192548533)

Page 3 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#14, REVISION 0 L-2024-129 Enclosure

4.

Salem Generating Station Unit 2 - Relief Request Associated with Fourth Interval lnservice Inspection Limited Examinations of Weld Coverage (EPID L-2022-LLR-0066) dated September 7, 2022. (Accession No. ML23139A147) 9.0 References

1.

St. Lucie Unit 2 ISi Program Plan Revision 4 (Document No. 4th-lSI-PSL-2-Program Plan)

2.

Relief Request No. 7 Regarding Risk Informed lnservice Inspection Program for the Class 1 and 2 (TAC NO. MF5406) (Accession No. ML15196A623)

3.

PNNL-26157, Rev. 1, Summary of Literature Search of Relief Requests on ASME Code,Section XI, Volumetric Examination Coverage Requirements for Piping Butt Welds. (Accession No. ML17318A120)

4.

NRC presentation, "Coverage Relief Requests," Industry/NRG NOE Technical Information Exchange Public Meeting January 13-15, 2015 (Accession No. ML15013A266)

Page 4 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 L-2024-129 Enclosure St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#14, REVISION 0 Table U2-14-PSI Pre-Service Risk-Informed Piping Examinations with Limited Coverage for the Fourth ISi Interval Welds met Construction Code Requirements of ASME Section Ill prior to PSI examination.

System Component ID Exam Category Year Exam Angle and Limitation Description/

Diameter Item No.

of Configuration Fig.

Coverage Wave Mode Results Comments Schedule Exam Material Safety Injection Component Configuration:

Preservice Examination:

Sl-151-FW-4-R 45°s Single-sided exam due to Risk Category 7a-Low Risk 12" Diameter R-A 2018 Pipe to Valve 1

50%*

60°S downstream valve (V3247}.

Examination Procedure:

Sch. 160 R1.20 60°L NOE 5.4 (POI -UT-2}

Stainless Steel No Recordable Indications Safety Injection Component Configuration:

Preservice Examination:

RC-153-FW-1-R 45°s Single-sided exam due to Risk Category 4-Medium Risk 12" Diameter R-A 2018 Pipe to Valve 2

50%*

60°S upstream valve (V3247}.

Examination Procedure:

Sch. 160 R1.20 60°L NOE 5.4 (POI -UT-2).

Stainless Steel No Recordable Indications Safety Injection Component Configuration:

Preservice Examination:

Sl-181-FW-14 45°s Single-sided exam due to Risk Category 6a-Low Risk 3" Diameter R-A 2020 Valve to Pipe 3

50%

60°S downstream valve (V3526}.

Examination Procedure:

Sch. 160 R1.20 70°s NOE 5.4 (POI -UT-2}

Stainless Steel No Recordable Indications Safety Injection Component Configuration:

Preservice Examination:

Sl-191-FW-1 45°s Single-sided exam due to Risk Category 6b-Low Risk 3" Diameter R-A 2020 Pipe to Valve 4

50%

60°S upstream valve (V3526}.

Examination Procedure:

Sch. 160 R1.16 70°s NOE 5.4 (POI -UT-2}

Stainless Steel No Recordable Indications Page 5 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 Table U2-14-PSI L-2024-129 Enclosure Pre-Service Risk-Informed Piping Examinations with Limited Coverage for the Fourth ISi Interval Welds met Construction Code Requirements of ASME Section Ill prior to PSI examination.

System Component ID Exam Category Year Exam Angle and Limitation Description/

Diameter Item No.

of Configuration Fig.

Coverage Wave Mode Results Comments Schedule Exam Material Safety Injection Component Configuration:

Preservice Examination:

Sl-191-FW-2000 45°s Single-sided exam due to Risk Category 2 High Risk 3" Diameter R-A 2020 Pipe to Valve 5

50%

60°S downstream valve {V3527).

Examination Procedure:

R1.11 Sch. 160

?0°s NDE 5.4 {PDI -UT-2)

Stainless Steel No Recordable Indications Safety Injection Component Configuration:

Preservice Examination:

Sl-191-FW-2001 45°s Single-sided exam due to Risk Category 2 High Risk 3" Diameter R-A 2020 Pipe to Valve 6

50%

60°S upstream valve {V3527).

Examination Procedure:

Sch. 160 R1.11

?0°s NDE 5.4 {PDI -UT-2)

Stainless Steel No Recordable Indications Safety Injection Component Configuration:

Preservice Examination:

Sl-191-FW-2003 Single-sided exam due to Risk Category 4 Medium Risk 3" Diameter R-A 45°s adjacent upstream valve to Examination Procedure:

Sch. 160 R1.20 2020 Pipe to Pipe 7

50%

60°S pipe weld {V3527).

NDE 5.4 {PDI -UT-2) 70°s Stainless Steel No Recordable Indications Safety Injection Component Configuration:

Preservice Examination:

Sl-515-FW-2001 Single-sided exam due to Risk Category 7a Low Risk 6" Diameter 45°s upstream valve {V3247) and Examination Procedure:

Sch. 160 R-A 60°S Downstream Weld 51-515-NDE 5.4 {PDI -UT-2)

R1.20 2021 Valve to Pipe 8

50%

70°s Stainless Steel 60°L FW-2000 No Recordable Indications Page 6 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 Table U2-14-PSI L-2024-129 Enclosure Pre-Service Risk-Informed Piping Examinations with Limited Coverage for the Fourth ISi Interval Welds met Construction Code Requirements of ASME Section Ill prior to PSI examination.

System Component ID Exam Category Year Exam Angle and Limitation Description/

Diameter Item No.

of Configuration Fig.

Coverage.

Wave Mode Results Comments Schedule Exam Material Safety Injection Component Configuration:

Preservice Examination:

Sl-113-FW-2000 Single side exam due to Risk Category 7a Low Risk 6" Diameter 45°s adjacent weld, Sl-113-12-SW-Examination Procedure:

Sch. 160 R-A 60°S 1, obstructing access to NDE 5.4 (PDI -UT-2)

R1.20 2021 Pipe to Pipe 9

50%

?0°s Stainless Steel 60°L Upstream Side.

No Recordable Indications Safety Injection Component Configuration:

Preservice Examination:

Sl-113-FW-2001 45°s Single-sided exam due to Risk Category 7a Low Risk 6" Diameter R-A Pipe to Valve 50%

60°S downstream valve (V3259).

Examination Procedure:

R1.20 2021 10

?0°s Sch. 160 60°L NDE 5.4 (PDI -UT-2)

Stainless Steel No Recordable Indications Page 7 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 Table U2-14-1SI Risk-Informed Piping Examinations with Limited Coverage for the Fourth ISi Interval System Year Component ID Exam Category of Configuration Fig.

Exam Angle and Limitation Description/

Diameter-Schedule Item No.

Exam Coverage Wave Mode Results Material Safety Injection Stainless:

Weld Configuration/

RC-151-FW-2 45°s Component Geometry 12" Diameter R-A Elbow to Safe 60°S R1.20 2017 End 11 86%

60°L Sch. 160 Stainless Steel to Cass Side:

CASS(CFSM)

PAUT No Recordable Indications Safety Injection Stainless:

Weld Configuration/

RC-152-FW-2 45°s Component Geometry 12" Diameter R-A Elbow to Safe 60°S 2017 12 85%

Sch. 160 R1.20 End 60°L Stainless Steel to Cass Side:

Recordable Indication of 360° CASS(CFSM)

PAUT Intermittent ID Root Geometry Safety Injection Stainless:

Weld Configuration/

RC-153-FW-2 45°s Component Geometry 12" Diameter R-A 2017 Elbow to Safe 13 83%

60°S Sch. 160 R1.20 End 60°L Stainless Steel to Cass Side:

CASS(CFSM)

PAUT No Recordable Indications Safety Injection Stainless:

Weld Configuration/

RC-154-FW-2 45°s Component Geometry 12" Diameter R-A 2017 Elbow to Safe 14 86%

60°S Sch. 160 R1.20 End 60°L Stainless Steel to Cass Side:

CASS(CFSM)

PAUT No Recordable Indications Page 8 of 25 L-2024-129 Enclosure Comments Examination per ASME Section XI. Stainless Performed per Appendix VIII, FPL Procedure 5.4 (PDI-UT-2) Examinations performed from the CASS side in accordance Appendix Ill per FPL Procedure 5.40 Revision 0 11 Non-Encoded Phased Array Ultrasonic Examination of CASS Piping Welds (LMT-01-PAUT-014) 11

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 Table U2-14-1SI Risk-Informed Piping Examinations with Limited Coverage for the Fourth ISi Interval System Year Component ID Exam Category of Configuration Fig.

Exam Angle and Limitation Description/

Diameter-Schedule Item No.

Exam Coverage Wave Mode Results Material Reactor Coolant Component Configuration:

RC-103-FW-2003 45°s Reducer to Tee R-A 2018 Reducer to 15 84%

60°S 4" Diameter R1.11 Tee 60°L Sch. 160 Stainless Steel No Recordable Indications Chemical and Component Configuration:

Volume Control 45°s Valve to Pipe CH-148-FW-20 R-A Valve to Pipe 50%

60°S R1.11 2023 16 70°s 2" Diameter Sch. 160 Stainless Steel No Recordable Indications Page 9 of 25 L-2024-129 Enclosure Comments Examination Procedure:

NDE 5.4 {PDI -UT-2)

Single-sided exam due to downstream valve {V2432).

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 Vh

\V d m Vo m No St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#14, REVISION 0 Figure 1 Sl-151-FW-4-R Component Configuration: Pipe to Valve L-2024-129 Enclosure N

R 2.35° M

50 Cod R ulr

• V lum Ex min -

C d) th 5

Page 10 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 L-2024-129 Enclosure St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#14, REVISION 0 Figure 2: RC-153-FW-1-R Component Configuration: Valve to Pipe Weld No:

RC.. 153-FWa1*R Weld HT":

Weld Length:*

43~00';-**

Weld Width:

2.35" 50% Code Required Volume Examined (We1d)

Weld Exam Volume Dimensions:

Height 0.44'1 length 43,oo**

Width 5.82S1' Required Scans (each has a weighing factor of 100 for complete coverage)

Angle UpSt-Ax Opst-Clr~

Dnst~Ax DnSt--Circ 45.:,/60~ S 0%

0%

100%

100%

aol?RL 100%

0%

0%

0%

Code Coverage Total 50%

Best Effort Coverage(Max 25%) Total 25.. 0%

Notes:

1) Code Coverage refers to the maximum percentage of the required examination volume that is effectively examined with the qualified examination procedure.

2) Best Effort Coverage refers to the required examination volume past the weld centerline that is examined in the axial beam direction with an Appendix VIII demonstrated procedure for single sided coverage.

Page 11 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#l4, REVISION 0 Weld No:

Weld nT":

Weld Weld Width:

Weld Exam Volume Dimensions:

45~ /60° I 70° S 100%

70"' Best Effort FIGURE 3: Sl-181-FW-14 Component Configuration: Pipe to Valve Volume Examined (Weld)

Height 0.14" Length 11.00**

DnSt-Ax L-2024-129 Enclosure Width 2.00" DnSt-Circ 0%

50%

5.3%

.,...,.,,,,.,,....,.......... refers to the maximum examination volume ettectlvielv examined with the examination prc)ce~at1re

"""0 '"~,n-refers to the examination volume centerline that is exarnined in the axial beam direction with an Ao,oend1ix or<)CE~c:nsre for coverage.

Page 12 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 Weld No:

Weld 0 r*:

Weld Leng:rn:

We Id Width:

St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#l4, REVISION 0 Figure 4: Sl-191-FW-1 Component Configuration: Valve to Pipe Weld Exam Volume Dimensions:

0.14" Length 11.00..

Covera e Summa Ing factor of 100 for U St-Clrc DnSt-Ax 0%

100%

27%

0%

Code L:CJ-vf:l,ra,nA Total BestE tal Notes:

L-2024-129 Enclosure Width DnSt-Circ 50%

6.8%

1) Code refers to the maximum r-.o.r,..d.:i.nt*ono examination volume that is examined with the qu,a1n1ea Best Effort refers to the the weld centerline that is examined in the axial beam direction nr,,t:).n,ruv VIII demonstrated for sided coverage.

Page 13 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#14, REVISION 0 Weld No:

Weld "T 0

Weld Leru1t111:

Weld Width:

Figure 5 Sl-191-FW-2000 Component Configuration: Pipe to Valve 50°/o Code Required Volume Examined (Weld)

Weld Exam Volume Dimensions:

Height 0.14" Length 11.c)O" L-2024-129 Enclosure Width 2.00" Required Scans (each has a weighing factor of 100 for complete coverage)

An le U St-Ax U St-Circ DnSt-Ax DnSt-Circ 45*'/60°/ 70° s 100%

100%

0%

0%

70" Best Effort 0%

0%

29%

Code Coverage Total 60%

Best Yo Total 7.1%

t;01ven:3ae refers to the maximum examination volume P.tti~CtlVAIV examined With the QU611lf1Etct o'v!lr,ntr'"l*~tu,,n D1r0C001Jr0 co,ve1raae refers to the examination volume the weld exc1mu1e-0 in the axial beam direction with an VIII demonstrated sided coverage.

Page 14 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#14, REVISION 0 Weld No:

Weld 0 T 0

Weld Weld Width:

Figure 6 Sl-191-FW-2001 Component Configuration: Valve to Pipe SI-191-FW-200!

Valve 3527 60'% Code Required Volume Examined (Weld)

Weld Exam Volume Dimensions:

Height 0.14"'

Length 11.00" Code Coverage Total Best Effort Covera e Max 25% Total L-2024-129 Enclosure Width 2.00**

DnSt-Clrc 0%

50%

7.1%

n\lcr,:;u-u:~ refers to the maximum examination volume ettiectiVelv examined wtth the examination......,..,...,,,.ri,....,.,.

• r.,;*or~,....,,. refers to the examination volume the weld centerline that is examined in the axial beam direction with an Appendix VIII demonstrated orc,ce,am*e for sided coverage.

Page 15 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 Weld No:

Weld '*T":

Weld...,..... w""

WeldWidth:

St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#14, REVISION 0 FIGURE 7 Sl-191-FW-2003 Component Configuration: Pipe to Pipe S1-191-FW~2003 0.438" 0.80° Vnlve3527 P'

50% Code Required Volume Examined (Weld)

L-2024-129 Enclosure Weld Exam Volume Dimensions:

Height 0.14" 11.00" Width 1.80" Required Scans (each has a weighing factor of 100 for complete coverage)

Angle UpSt-Ax UpSt..Clrc DnSt-Ax Dnst.. Clrc centerline that is examined in the oroced1ure for single sided coverage.

50%

16.5%

,...,,,,.,,.,...,, examination volume the weld bearn direction with an ilt"lt'\On,ruv VIII demonstrnted Page 16 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 L-2024-129 Enclosure Valve St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#l4, REVISION 0 FIGURE 8 Sl-515-FW-2001 Component Configuration: Valve to Pipe VALVE.

SI-515-FW-2001 Coverage Plot

\./£LI) NO: S1*515

• fW*l061 WE.LDT": 0."}1q

WfLD LEN<.Tk:2o.~**

Wtll) WtDlW I. I" Ft.Ow' Pipe Coverace Summary Required Scans (eath has a weigh In: factor of 100 for complete coverage)

Antle US.Ax US.Ore OS*Ax OS*Circ 45*/60*/70* S 0%

0%

61%

100%

60* RL 42%

0%

0%

Flow.....

0%

~de coverage Total 40%

10% Required Weld Exam Volume Achieved Best Effort Covernge(Max 25%}

10%

Notes: 1) Code Coverage Refers to the maximum percentage of the required examination volume that is effectively examined with the qualified l.O" examination procedure. 2) Best Effort Coverage refers to the required examination volume p.1st the weld ce-nterline that is examined in the axial beam direction with an Appendix VIII demonstrated procedure for single 1.0" sided coverage.

Page 17 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 L-2024-129 Enclosure Weld SJ-113-12-SW-1 Pipe St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#l4, REVISION 0 FIGURE 9 SI-113-FW-2000 Component Configuration: Pipe to Pipe LlMI\ 14N:

Will> tfo: S'l *IIJ* lt*SW*f *\ ~

~~

PIPE.

v/H~ NO: Sf.llHW* 1000 Wf.LD 'T": D.Wf'

\vtLO l~NGTH: 20.S" wuo w1oni:r.1**

~

~

()*

<t

~

FLOW PIP£.

SI-113-FW-2000 overage Plot WCL

' \

\

Pipe Flow

. 0% Required Weld *xam Volume Achic cd 1.0" 1.0" Not~: 11 Code covor;,gc Rotcrs to the m.iidmum pcrccnt c of the required cx;,mtna 'on volume thilt Is cffccttvcly cx~mlncd with the qu~llflcd cx.,minatlon procedure. 2} SCst Effort Cover g refer to th r qulrcd exam111 t on volume p st the weld c nterlln that Is examin d In the axia1 be m direction w'th M Appendix VIII demonstmcd proc dur for $ll'ltl sided eovoroso.

Page 18 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 L-2024-129 Enclosure Pipe LO" St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#l4, REVISION 0 FIGURE 10 SI-113-FW-2001 Component Configuration: Pipe to Valve w'Ell> NO: J H/ 3~ F\../*2.001 Wf:LD..,.. : D.iti" Wun L.eNc..rn: za.s" WfLO W10TH: I.I

---

=----...-_....<t._ /

l>H'f.

FLO\./

VALVE.

SI-113-FW-2001 Co\'erage Plot 45° WCL Valve Coverage Summary Required Scans (each ha5 a weighing factor of 100 for complete coverage}

Flow Angle US*Ax US-Clrc:

OS-Ax DS*Circ 45*/60*110* S 100%

100%

0%

0 ro* Rt 0%

0%

8%

0%

50% Code Required Volume Examined (Weld)

Code Covuage Total 50%

Best Effort Cover.ige(Max 25%)

2%

Notes: 1) Code Coverage Refers to the maximum pmentage of the required examination volume that Is effectively examined with the qualified examination procedure. 2) Best Effort Coverage refer$ to the required examination volume past the weld centerline that is examined in the al<ial beam direction with an Appendix Viti demonstrated procedure fot single 1.0" sided coverage.

Page 19 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#14, REVISION 0 FIGURE 11 RC-151-FW-2 Component Configuration: Elbow to Safe End Page 20 of 25 L-2024-129 Enclosure

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#14, REVISION 0 FIGURE 12 RC-152-FW-2 Component Configuration: Elbow to Safe End Page 21 of 25 L-2024-129 Enclosure

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#14, REVISION 0 FIGURE 13 RC-153-FW-2 Component Configuration: Elbow to Safe End Page 22 of 25 L-2024-129 Enclosure

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#l4, REVISION 0 FIGURE 14 RC-154-FW-2 Component Configuration: Elbow to Safe End Page 23 of 25 L-2024-129 Enclosure

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#l4, REVISION 0 Figure 15 RC-103-FW-2003 Component Configuration: Elbow to Safe En'!_

L-2024-129 Enclosure We Id No:

RC~103*FW-2003

---

..... ~----

Weld "T":

0.531° Weld Length:

14.50" Weld Width:

o.90" 0

Expander 90", 27CI' l

/

45 S 84.2% Code Required Volume Examined (Weld) rJeld Exam Volume Dimensions:

Height 0.20" length 14.50" Coverage Summar Tee Width 1.90..

Required Scans (each has a weighing factor of 100 for complete coverage)

An le U St*Ax U St-Circ DnSt-Ax DnSt-Clrc 45° s 100%

100%

0%

100%

60°RL 0%

0%

29.3%

0%

Code Coverage Total 84.2%

Best Effort Covera e Max 25% Total 29.3%

otes:

1 ) Code Coverage refers to the maximum percentage of the required examination volume that is effectively examined with the qualified examination procedure.

2) Best Effort Coverage refers to the required examination volume past the weld centerline that is examined in the axial beam direction with an Appendix VIII demonstrated procedure for single sided coverage.

Page 24 of 25

St. Lucie Nuclear Plant, Unit 2 Docket No. 50-389 L-2024-129 Enclosure Sketch or Photo:

St. Lucie Unit 2 FOURTH INSPECTION INTERVAL RELIEF REQUEST NUMBER RR#14, REVISION 0 FIGURE 16 CH-148-FW-20 Component Configuration: Elbow to Safe End Flow >>

Valve Pipe

~

Required Exam Volume-.t8Sq.Jnches Upstream Required Exam Volume.08 Sq. Jnches Volume Examined on Upstream side*.06 Sq. Inches (Best Effort)

EN1mln1tlon Volume Dimensions: Length UC 11 Width ~

x Helaht J1!

Weld Thickness*,992n Weld lonath* 1.15*

Weld Width=

,&0 11 Coverage Summary-Weld # CH*148*FW*20 Reaulred Scans* each has a wel1hln2 fector of 100" for complete covereae Antle Uo,trnm *Axlal Uostrtam* Clrc.

Downstream Axial Downstream Clrc.

45/60/70 o"

o" 100" 100" 70 75" Code coverage Total so"

&est Effort Comtae (Max 25") Total 18.15%

Notes:

t. Code coverese refers to the mulmum percentace of the required examination volume that b eff1ctlve1v examined with the qualified mmln1tlon procedure

z. Best Effort Covera1e refers to the required examination volume past the centerline that 1s examined In the a>clal beam direction with an Appendix VIII demonstrated procedure for single sided coverage Page 25 of 25