L-2017-216, License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 6

License Renewal Commitments: Reactor Vessel Internals Aging Management Plan, Clarification of Responses to RAI 1 and RAI 6

ML17354A061
Person / Time
Site:	Saint Lucie
Issue date:	12/19/2017
From:	Deboer D Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2017-216
Download: ML17354A061 (16)

Text

DEC 1 9 2017 L-2017-216 10 CFR 54 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001 St Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 License Renewal Commitments Reactor Vessel Internals Aging Management Plan

• " Clarification of Responses to RA.I 1 and RAI 6

References:

1. NUREG 1779, Safety Eval-µation Report Related to License Renewal of St Lucie Nuclear Plant, Units 1 and 2, September 2003.

2. Safety Evaluation by the Office of Nuclear Reactor Regulation related to Amendment No. 213 to Facility Operating License No. DPR-67, Florida Power and Light Company, St. Lucie Plant Unit No.

1, Docket No. 50-335.

3. Safety Evaluation by the Office of Nuclear Reactor Regulation related to Amendment No. 163 to Facility Operating License No. NPF-16, Florida Power and Light Company, St. Lucie Plant Unit No.

2, Docket No. 50-389.

4. Electric Power Research Institute (EPRI) Materials Reliability Program Report 1022863 (MRP-227-A), "Pressurized Water Reactor Internals Inspection and Evaluation Guidelines," ADAMS Accession Nos.ML12017A194,ML12017A196,ML12017A197,ML12017A191,ML12017A192, ML12017A195, andML12017A199.

5. FPL Letter from Joseph Jensen to U.S. Nuclear Regulatory Commission (L-2014-192) "St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389, Reactor Vessel Internals Inspection Program Plans and Inspection Dates," June 25, 2014.

6. FPL Letter from Christopher Costanzo to U.S. Nuclear Regulatory Commission (L-2015-229) "St Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389, License Renewal Commitments - Reactor Vessel Internals Aging Management Plan," Dated September 28, 2015.

7. NRC e-Mail from Perry Buckberg to Ken Frehafer, Request for Additional Information, St. Lucie Plant Units 1 and 2, Reactor Vessel Internals Aging Management Plan, Docket Nos. 50-335 and 50-389, TAC Nos ..MF6777 and MF6778. ADAMS Accession No. ML16013A215.

8. FPL Letter from Christopher Costanzo to U.S. Nuclear Regulatory Commission (L-2016-040) "St.

Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389, License Renewal Commitments - Reactor Vessel Internals Aging Management Plan," Dated February 26, 2016.

Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957

L-2017-216 Page2

9. FPL Letter from Daniel DeBoer to U.S. Nuclear Regulatory Commission (L-2017-015) "St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389, License Renewal Commitments - Reactor Vessel Internals Aging Management Plan Response to Request for Additional Information," Dated March 7, 2017.

10. NRC E-mail, 11-28-2017, Perry Buckberg to Ken Frehafer, "LR Commitments - Reactor Vessel Internals (RVI) Aging Management Plan (MF6777 & MF6778)", Clarification of RAI Responses RAI-MF6777 /MF6778-EVIB-01 and RAI-MF6777 /MF6778-EVIB-06. ADAMS Accession No. ML17335A103.

By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 28, 2015 (Reference 6), Florida Power & Light Company (FPL) submitted its License Renewal Reactor Internals Program MRP-227-A (Reference 4) at St. Lucie Nuclear Plants Units 1 and 2 for NRC staff review.

The NRC staff reviewed the information provided by FPL in its submittal and requested additional information to complete their review (Reference 7). The responses to RAI-1 through RAI-4 and RAI-7 through RAI-10 were previously submitted to the NRC on February 26, 2016 (Reference 8). The responses to RAI-5 and RAI-6 were previously submitted to the NRC on February 7, 2017 (Reference 9).

The NRC staff reviewed the information provided by FPL in the responses to RAI-1 through 10 and asked for clarifications to the responses to RAI-1 and RAI-6 (Reference 10).

The clarifications to RAI 1 & 6 are included in Attachment 1. The revised pages of the Reactor Vessel Internals Aging Management Plan with changes incorporated from the clarifications to RAI-1 and RAI-6 are contained in Attachment No. 2.

Should you have any questions, please contact Mr. Michael Snyder, Licensing Manager, at 772-467-7036.

Very truly yours, Daniel DeBoer Site Director St. Lucie Plant Attachments:

1) St Lucie Units 1and2, Clarifications to RAI-1 and RAI-6

2) St Lucie Units 1 and 2, Reactor Vessel Internals Aging Management Plan, changes pages cc: NRC Region II Administrator NRC Project Manager, St Lucie Nuclear Plant NRC Senior Resident Inspector, St Lucie Nuclear Plant

L-2017-216 Attachment 1 Page 1 of 3 Attachment 1 St. Lucie Units 1 and 2 Clarifications to RAI-1 and RAI-6

L-2017-216 Attachment 1 Page 2 of 3 The staff is requesting clarification on two RAI responses related to the subject review. Questions are below:

RAI-MF6777/MF6778-EVIB-01 (2/26/16 FPL Response - ML16063A006) - The information in the response related to the components for which inspections are waived due to having a fatigue time-limited aging analysis (TLAA) is inconsistent with the License Renewal Application (LRA). The only RVI component with a fatigue TLAA is the core barrel cylinder in LRA Section 4.6.3. However, the RAI response includes that a fatigue evaluation was performed for other RVI components which were not in the LRA. Was the analysis performed at a later time and not a part of the LRA Licensing Basis (at the time), or it did not meet the criteria for a TLAA?

FPL Response:

Fatigue evaluations of reactor vessel internal components were performed and were documented in the Extended Power Uprate (EPU) LAR submittal sent in FPL Letters: L-2010-259 and L-2011-021, Ref. 1 and 2 defined below. Attachment 5 Licensing Report of each letter documented that the following reactor vessel internals components were evaluated for PSL Units 1 and 2:

• Core Support Barrel (CSB)

• Core Support Plate (CSP)

• Lower Support Structure (LSS) Beams and Columns

• Core Shroud

• Upper Guide Structure (UGS)

• Fuel Alignment Plate (FAP)

• Control Element Assembly (CEA) Shrouds

• Instrument Tube Supports

• Reactor Vessel Level Monitoring System Support Tube

• Thimble Support Plate (TSP)

The results of these evaluations demonstrated that the above listed components were structurally adequate for the EPU conditions and the fatigue usage factors were less than 1.0. In Section 2.2.2.1.3 of Attachment 5 of each letter, it confirmed the fatigue analyses performed remain valid for the period of extended operation. This response updates FPLs response to RAI #1 in FPL Letter No. L-2016-040 with the fatigue evaluation references for the PSL Unit 1 and 2 reactor vessel internals.

L-2017-216 Attachment 1 Page 3 of 3 RAI-MF6777/MF6778-EVIB-06 (3/6/17 FPL Response - ML17075A194) - In the response, FPL proposed plant-specific modifications to MRP-227-A for components at St. Lucie which experience higher fluence than what was analyzed in MRP-227-A. The core barrel cylinder is an expansion component that FPL determined to be susceptible to irradiation assisted stress corrosion cracking (IASCC). Expansion components are linked to other primary components which are examined to ensure that degradation due to certain mechanisms are non-existent. The primary component that the core barrel cylinder is linked to does not have IASCC as a mechanism, which means that it will never be examined for IASCC. Shouldnt the primary link be something for which IASCC is a possible degradation mechanism?

FPL Response:

The Expansion Component Core Support Barrel (CSB) upper cylinder exceeded the fluence criteria for IASCC. IASCC was added as a Degradation Mechanism in the Expansion Components Table in the St. Lucie Units 1 & 2 RVI AMP. The Primary Component core support barrel (CSB) upper flange weld did not require a change, because IASCC did not screen in as applicable. The Primary Component Core Shroud Plate-Former Plate Weld experiences higher fluence than the CSB upper cylinder, and it is susceptible to IASCC. FPL has added the CSB upper cylinder as an Expansion Link to the Core Shroud Plate-Former Plate Weld in the Primary Components Table. Degradation meeting Expansion Criteria of the Core Shroud Plate-Former Plate will trigger an Expansion Component inspection of the CSB upper cylinder.

References:

1. FPL Letter, L-2010-259, R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2010-259), "St. Lucie Plan Unit 1 License Amendment Request for Extended Power Uprate,"

November 22, 2010, ADAMS Accession No. ML103560419.

2. FPL Letter, L-2011-021, R. L. Anderson (FPL) to U.S. Nuclear Regulatory Commission (L-2011-021), "St. Lucie Plant Unit 2 License Amendment Request for Extended Power Uprate,"

February 25, 2011, ADAMS Accession No. ML110730116.

L-2017-216 Attachment 2 Page 1 of 11 Attachment 2 St. Lucie Units 1 and 2 Reactor Vessel Internals Aging Management Plan Changes

L-2017-216 Attachment 2 Page 2 of 11 CE Plants Primary Components St. Lucie Units 1 and 2 Effect Expansion Link Examination Item Applicability Examination Coverage (Mechanism) (Note 1) Method/Frequency (Note 1)

Core Shroud Assembly Bolted plant Cracking Core support Baseline volumetric (UT) 100% of accessible bolts (see Note 3).

(Bolted) designs (IASCC), Fatigue column bolts, examination between 25 and 35 Heads are accessible from the core Core shroud bolts NA for PSL Aging Barrel-shroud EFPY, with subsequent examination side. UT accessibility may be Management (IE bolts on a ten-year interval. affected by complexity of head and and ISR) locking device designs.

(Note 2)

See Figure 4-24, MRP-227-A.

Core Shroud Assembly Plant designs with Cracking (IASCC) Remaining axial Enhanced visual (EVT-1) Axial and horizontal weld seams at (Welded) core shrouds Aging welds examination no later than 2 refueling the core shroud re-entrant corners as Core shroud plate-former assembled in two Management (IE) outages from the beginning of the visible from the core side of the plate weld vertical sections (Note 2) Core support license renewal period and shroud, within six inches of central Applicable for barrel assembly subsequent examination on a ten-year flange and horizontal stiffeners.

PSL upper cylinder interval.

See Figures 4-12 and 4-14, MRP-227-A.

Core Shroud Assembly Plant designs with Cracking (IASCC) Remaining axial Enhanced visual (EVT-1) Axial weld seams at the core shroud (Welded) core shrouds Aging welds, ribs and examination no later than 2 refueling re-entrant corners, at the core Shroud plates assembled with Management (IE) rings outages from the beginning of the mid-plane (+/-three feet in height) as full-height shroud (Note 2) license renewal period and visible from the core side of the plates subsequent examination on a ten-year shroud.

NA for PSL interval.

See Figure 4-13, MRP-227-A.

L-2017-216 Attachment 2 Page 3 of 11 CE Plants Primary Components St. Lucie Units 1 and 2 Effect Expansion Link Examination Item Applicability Examination Coverage (Mechanism) (Note 1) Method/Frequency (Note 1)

Core Shroud Assembly Bolted plant Distortion None Visual (VT-3) examination no later Core side surfaces as indicated.

(Bolted) designs (Void Swelling), than 2 refueling outages from the Assembly NA for PSL including: beginning of the license renewal See Figures 4-25 and 4-26, MRP-227-Abnormal period. Subsequent examinations on A.

interaction a ten-year interval.

with fuel assemblies Gaps along high fluence shroud plate joints Vertical displacement of shroud plates near high fluence joint Aging Management (IE)

Core Shroud Assembly Plant designs with Distortion None Visual (VT-1) examination no later If a gap exists, make three to five (Welded) core shrouds (Void Swelling), than 2 refueling outages from the measurements of gap opening from Assembly assembled in two as evidenced by beginning of the license renewal the core side at the core shroud re-vertical sections separation between period. Subsequent examinations on a entrant corners. Then, evaluate the Applicable for the upper and ten-year interval. swelling on a plant-specific basis to PSL lower core shroud determine frequency and method for segments additional examinations.

Aging Management (IE) See Figures 4-12 and 4-14, MRP-227-A.

Core Support Barrel All plants Cracking (SCC) Lower core Enhanced visual (EVT-1) 100% of the accessible surfaces of the Assembly Applicable for support beams. examination no later than 2 refueling upper flange weld.

Upper (core support barrel) PSL Core support outages from the beginning of the flange weld barrel assembly license renewal period. Subsequent See Figure 4-15, MRP-227-A.

upper cylinder examinations on a ten-year interval.

Upper core barrel flange

L-2017-216 Attachment 2 Page 4 of 11 CE Plants Primary Components St. Lucie Units 1 and 2 Effect Expansion Link Examination Item Applicability Examination Coverage (Mechanism) (Note 1) Method/Frequency (Note 1)

Core Support Barrel All plants Cracking (SCC, Lower Cylinder Enhanced visual (EVT-1) 100% of the accessible surfaces of the Assembly Applicable for IASCC) Axial Welds examination no later than 2 refueling lower cylinder welds. (Note 4)

Lower cylinder girth welds PSL Aging outages from the beginning of the Management (IE) license renewal period. Subsequent See Figure 4-15, MRP-227-A.

examinations on a ten-year interval.

Lower Support Structure All plants Cracking (SCC, None Visual (VT-3) examination no later 100% of the accessible surfaces of the Core support column welds) Applicable for IASCC) than 2 refueling outages from the core support column welds. (Note 5)

PSL Aging beginning of the license renewal Management (IE) period. Subsequent examinations on a See Figure 4-16 and 4-31, MRP-227-ten-year interval. A.

Core Support Barrel All plants Cracking (Fatigue) None If fatigue life cannot be demonstrated Examination coverage to be defined Assembly No inspections by time-limited aging analysis by plant-specific fatigue analysis.

Lower flange weld required for PSL (TLAA), enhanced visual (EVT-1)

Units 1 and 2 as examination, no later than 2 refueling See Figure 4-15 and 4-16, MRP-227-TLAA exists. outages from the beginning of the A.

(10.19) license renewal period. Subsequent examination on a ten-year interval.

Core Support Barrel PSL Unit 1 Only Cracking None Enhanced visual (EVT-1) Repair region of core support barrel Assembly (IASCC, SCC, examination no later than 2 refueling Expandable plugs and Fatigue) outages from the beginning of the patches license renewal period. Subsequent examinations on a ten-year interval Lower Support Structure All plants with a Cracking (Fatigue) None If fatigue life cannot be demonstrated Examination coverage to be defined Core support plate core support plate Aging by time-limited aging analysis by evaluation to determine the No inspections Management (IE) (TLAA), enhanced visual (EVT-1) potential location and extent of fatigue required for PSL examination, no later than 2 refueling cracking.

Units 1 and 2 as outages from the beginning of the TLAA exists. license renewal period. Subsequent See Figure 4-16, MRP-227-A.

(10.19) examination on a ten-year interval.

L-2017-216 Attachment 2 Page 5 of 11 CE Plants Primary Components St. Lucie Units 1 and 2 Effect Expansion Link Examination Item Applicability Examination Coverage (Mechanism) (Note 1) Method/Frequency (Note 1)

Upper Internals Assembly All plants with Cracking (Fatigue) None If fatigue life cannot be demonstrated Examination coverage to be defined Fuel alignment plate core shrouds by time-limited aging analysis by plant-specific fatigue analysis.

assembled with (TLAA), enhanced visual (EVT-1) full-height shroud examination, no later than 2 refueling See Figure 4-17, MRP-227-A.

plates outages from the beginning of the NA for PSL license renewal period. Subsequent examination on a ten-year interval.

Control Element Assembly All plants with Cracking (SCC, Remaining Visual (VT-3) examination, no later 100% of tubes in peripheral CEA Instrument guide tubes instrument guide Fatigue) that instrument guide than 2 refueling outages from the shroud assemblies (i.e., those adjacent tubes in the CEA results in missing tubes within the beginning of the license renewal to the perimeter of the fuel alignment shroud assembly supports or CEA shroud period. Subsequent examination on a plate).

Applicable for separation at the assemblies ten-year interval.

PSL welded joint See Figure 4-18, MRP-227-A.

between the tubes Plant-specific component integrity and supports assessments may be required if degradation is detected and remedial Aging action is needed.

Management (IE)

Lower Support Structure All plants with Cracking (Fatigue) None Enhanced visual (EVT-1) Examine beam-to-beam welds, in the Deep beams core shrouds that results in a examination, no later than 2 refueling axial elevation from the beam top assembled with detectable surface- outages from the beginning of the surface to four inches below.

full-height shroud breaking license renewal period. Subsequent plates indication in the examination on a ten-year interval, if See Figure 4-19, MRP-227-A.

NA for PSL welds or beams adequacy of remaining fatigue life Aging cannot be demonstrated.

Management (IE)

NOTE:

1) Examination acceptance criteria and expansion criteria are in the CE Plants Examination Acceptance and Expansion Criteria Table.

2) Void swelling effects on this component is managed through management of void swelling on the entire core shroud assembly.

3) A minimum of 75% of the total population (examined + unexamined), including coverage consistent with the Expansion criteria in Attachment 4, must be examined for inspection credit.

4) A minimum of 75% of the total weld length (examined + unexamined), including coverage consistent with the Expansion criteria in Attachment 4, must be examined from either the inner or outer diameter for inspection credit.

5) A minimum of 75% of the total population of core support column welds

L-2017-216 Attachment 2 Page 6 of 11 CE Plants Expansion Components St. Lucie Units 1 and 2 Item Applicability Effect (Mechanism) Primary Link Examination Method Examination Coverage (Note 1) (Note 1)

Core Shroud Assembly Bolted plant designs Cracking (IASCC, Core shroud Volumetric (UT) examination. 100% (or as supported by plant-(Bolted) NA for PSL Fatigue) bolts Re-inspection every 10 years specific justification; Note 2) of Barrel-shroud bolts Aging Management following initial inspection. barrel-shroud and guide lug insert (IE and ISR) bolts with neutron fluence exposures

> 3 displacements per atom (dpa).

See Figure 4-23, MRP-227-A.

Core Support Barrel All plants Cracking (SCC, Upper (core Enhanced visual (EVT-1) 100% of accessible welds and Assembly Applicable for PSL Fatigue) support barrel) examination Re-inspection adjacent base metal (Note 2).

Lower core barrel flange flange weld every 10 years following the initial inspection. .

See Figure 4-15, MRP-227-A.

Core Support Barrel All plants Cracking (SCC, Upper (core Enhanced visual (EVT-1) 100% of accessible surfaces of the Assembly Applicable for PSL IASCC) support barrel) examination. Re-inspection welds and base metal (Note 2).

Upper cylinder (including Aging Management flange weld every 10 years following initial welds) (IE) inspection. See Figure 4-15, MRP-227-A.

Core shroud plate-former plate weld Core Support Barrel All plants Cracking (SCC) Upper (core Enhanced visual (EVT-1) 100% of accessible bottom surface of Assembly Applicable for PSL support barrel) examination. Re-inspection the flange (Note 2).

Upper core barrel flange flange weld every 10 years following initial inspection. See Figure 4-15, MRP-227-A.

Core Support Barrel All plants Cracking (SCC) Core barrel Enhanced visual (EVT-1) 100% of one side of the accessible Assembly Applicable for PSL assembly girth examination, with initial and weld and adjacent base metal surfaces Core barrel assembly axial welds subsequent examinations for the weld with the highest welds dependent on the results of core calculated operating stress.

barrel assembly girth weld examinations. . See Figure 4-15, MRP-227-A.

Lower Support Structure All plants except those Cracking (SCC, Upper (core Enhanced visual (EVT-1) 100% of accessible surfaces (Note 2).

Lower support column with core shrouds fatigue) including support barrel) examination. Re-inspection beams assembled with damaged or flange weld every 10 years following initial See Figure 4-16 and 4-31, MRP-227-full-height shroud fractured material. inspection. A.

plates. Aging Management Applicable for PSL (IE)

L-2017-216 Attachment 2 Page 7 of 11 CE Plants Expansion Components St. Lucie Units 1 and 2 Item Applicability Effect (Mechanism) Primary Link Examination Method Examination Coverage (Note 1) (Note 1)

Core Shroud Assembly Bolted plant designs Cracking (IASCC, Core shroud Ultrasonic (UT) examination. 100% (or as supported by plant-(Bolted) NA for PSL Fatigue) bolts Re-inspection every 10 years specific analysis) of core support Core support column bolts Aging Management following initial inspection. column bolts with neutron fluence (IE) exposures > 3 dpa. (Note 2)

See Figures 4-16 and 4-33, MRP-227-A.

Core Shroud Assembly Plant designs with core Cracking (IASCC) Core shroud Enhanced visual (EVT-1) Axial weld seams other than the core (Welded) shrouds assembled in plate-former examination. shroud re-entrant corner welds at the Remaining axial welds two vertical sections plate weld Re-inspection every 10 years core mid-plane.

Applicable for PSL following initial inspection.

See Figure 4-12, MRP-227-A.

Core Shroud Assembly Plant designs with core Cracking (IASCC) Shroud plates of Enhanced visual (EVT-1) Axial weld seams other than the core (Welded) shrouds assembled with welded core examination, with initial and shroud re-entrant corner welds at the Remaining axial welds, full-height shroud plates shroud subsequent examination core mid-plane, plus ribs and rings.

Ribs and rings NA for PSL assemblies frequencies dependent on the results of the core shroud weld See Figure 4-13, MRP-227-A.

examinations.

Control Element Assembly All plants with Cracking (SCC, Peripheral Visual (VT-3) examination, 100% of tubes in CEA shroud Remaining instrument guide instrument guide tubes Fatigue) that results instrument guide with initial and subsequent assemblies.

tubes in the CEA shroud in missing supports tubes within the examinations dependent on the assembly or separation at the CEA shroud results of the instrument guide welded joint assemblies tubes examinations. See Figure 4-18, MRP-227-A.

Applicable for PSL between the tubes and supports.

Aging Management (IE)

NOTE:

1) Examination acceptance criteria and expansion criteria are in the CE Plants Examination Acceptance and Expansion Criteria Table.

2) A minimum of 75% coverage of the entire examination area or volume, or a minimum sample size of 75% of the total population of like components of the examination is required (including both the accessible and inaccessible portions)

L-2017-216 Attachment 2 Page 8 of 11 CE Plants Examination Acceptance and Expansion Criteria St. Lucie Units 1 and 2 Examination Acceptance Expansion Additional Examination Item Applicability Expansion Criteria Criteria (Note 1) Link(s) Acceptance Criteria Core Shroud Assembly Bolted plant Volumetric (UT) examination. a. Core support a. Confirmation that >5% of the core shroud a and b. The examination (Bolted) designs column bolts bolts in the four plates at the largest distance acceptance criteria for the Core shroud bolts NA for PSL b. Barrel- from the core contain unacceptable indications UT of the core support The examination acceptance shall require UT examination of the lower column bolts and barrel-criteria for the UT of the core shroud bolts support column bolts barrel within the next 3 shroud bolts shall be shroud bolts shall be refueling cycles. established as part of the established as part of the examination technical examination technical justification.

justification. b. Confirmation that >5% of the core support column bolts contain unacceptable indications shall require UT examination of the barrel-shroud bolts within the next 3 refueling cycles.

Core Shroud Assembly Plant designs Visual (EVT-1) examination. Remaining Confirmation that a surface-breaking indication The specific relevant (Welded) with core axial welds > 2 inches in length has been detected and sized condition is a detectable Core shroud plate-former plate shrouds in the core shroud plate-former plate weld at the crack-like surface weld assembled in The specific relevant core shroud re-entrant corners (as visible from indication.

two vertical condition is a detectable Core support the core side of the shroud), within 6 inches of sections crack-like surface indication. barrel assembly the central flange and horizontal stiffeners, shall upper cylinder require EVT-1 examination of all remaining Applicable for PSL axial welds by the completion of the next refueling outage.

Core Shroud Assembly Plant designs Visual (EVT-1) examination. a. Remaining a. Confirmation that a surface-breaking The specific relevant (Welded) with core axial welds indication > 2 inches in length has been detected condition is a detectable Shroud plates shrouds The specific relevant b. Ribs and and sized in the axial weld seams at the core crack-like surface assembled with condition is a detectable rings shroud re-entrant corners at the core mid-plane indication.

full-height crack-like surface indication. shall require EVT-1 or UT examination of all shroud plates remaining axial welds by the completion of the NA for PSL next refueling outage.

b. If extensive cracking is detected in the remaining axial welds, an EVT-1 examination shall be required of all accessible rib and ring welds by the completion of the next refueling outage.

L-2017-216 Attachment 2 Page 9 of 11 CE Plants Examination Acceptance and Expansion Criteria St. Lucie Units 1 and 2 Examination Acceptance Expansion Additional Examination Item Applicability Expansion Criteria Criteria (Note 1) Link(s) Acceptance Criteria Core Shroud Assembly Bolted plant Visual (VT-3) examination. None N/A N/A (Bolted) designs Assembly NA for PSL The specific relevant conditions are evidence of abnormal interaction with fuel assemblies, gaps along high fluence shroud plate joints, and vertical displacement of shroud plates near high fluence joints.

Core Shroud Assembly Plant designs Visual (VT-1) examination. None N/A N/A (Welded) with core Assembly shrouds assembled in The specific relevant two vertical condition is evidence of sections physical separation between the upper and lower core Applicable for shroud sections.

PSL Core Support Barrel All plants Visual (EVT-1) examination. Lower core Confirmation that a surface-breaking indication The specific relevant Assembly Applicable to support beams >2 inches in length has been detected and sized condition is a detectable Upper (core support barrel) PSL Upper core in the upper flange weld shall require that an crack-like surface The specific relevant flange weld barrel cylinder EVT-1 examination of the lower core support indication.

condition is a detectable (including beams, upper core barrel cylinder and upper core crack-like surface indication.

welds) barrel flange be performed by the completion of the next refueling outage.

Upper core barrel flange (cast)

Core Support Barrel All plants Visual (EVT-1) examination. Lower cylinder a. Confirmation that a surface-breaking The specific relevant Assembly Applicable to axial welds indication >2 inches in length has been detected condition for the expansion Lower cylinder girth welds PSL The specific relevant and sized in the lower cylinder girth weld shall lower cylinder axial welds is condition is a detectable require an EVT-1 examination of all accessible a detectable crack-like crack-like surface indication. lower cylinder axial welds by completion of the surface indication.

next refueling outage.

L-2017-216 Attachment 2 Page 10 of 11 CE Plants Examination Acceptance and Expansion Criteria St. Lucie Units 1 and 2 Examination Acceptance Expansion Additional Examination Item Applicability Expansion Criteria Criteria (Note 1) Link(s) Acceptance Criteria Lower Support Structure All plants Visual (VT-3) examination. None None Core support column welds Applicable to PSL The specific relevant condition is missing or separated welds.

Core Support Barrel All plants Visual (EVT-1) examination. None N/A N/A Assembly Applicable to Lower flange weld PSL The specific relevant condition is a detectable crack-like indication.

Core Support Barrel PSL Unit 1 Visual (EVT-1) examination. None N/A Assembly Only Expandable plugs and patches The specific relevant condition is a detectable crack-like surface indication.

Lower Support Structure All plants with Visual (EVT-1) examination. None N/A N/A Core support plate a core support plate The specific relevant Applicable to condition is a detectable PSL crack-like surface indication.

Upper Internals Assembly All plants with Visual (EVT-1) examination. None N/A N/A Fuel alignment plate core shrouds assembled with The specific relevant full-height condition is a detectable shroud plates crack-like surface indication.

NA for PSL Control Element Assembly All plants with Visual (VT-3) examination. Remaining Confirmed evidence of missing supports or The specific relevant Instrument guide tubes instruments instrument separation at the welded joint between the tubes conditions are missing tubes in the tubes within and supports shall require the visual (VT-3) supports and separation at The specific relevant CEA shroud the CEA examination to be expanded to the remaining the welded joint between the conditions are missing assembly shroud instrument tubes within the CEA shroud tubes and the supports.

supports and separation at the Applicable to assemblies assemblies by completion of the next refueling welded joint between the PSL outage.

tubes and the supports.

L-2017-216 Attachment 2 Page 11 of 11 CE Plants Examination Acceptance and Expansion Criteria St. Lucie Units 1 and 2 Examination Acceptance Expansion Additional Examination Item Applicability Expansion Criteria Criteria (Note 1) Link(s) Acceptance Criteria Lower Support Structure All plants with Visual (EVT-1) examination. None N/A N/A Deep beams core shrouds assembled with The specific relevant full-height condition is a detectable shroud plates crack-like indication.

NA for PSL NOTE

1. The examination acceptance criterion for visual examination is the absence of the specified relevant condition(s).