L-PI-12-078, PWR (Pressurized Water Reactor) Vessel Internals Program for Fulfillment of License Renewal Commitment 25: Difference between revisions

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| issue date = 10/01/2012
| issue date = 10/01/2012
| title = PWR (Pressurized Water Reactor) Vessel Internals Program for Fulfillment of License Renewal Commitment 25
| title = PWR (Pressurized Water Reactor) Vessel Internals Program for Fulfillment of License Renewal Commitment 25
| author name = Sorensen J P
| author name = Sorensen J
| author affiliation = Northern States Power Co, Xcel Energy
| author affiliation = Northern States Power Co, Xcel Energy
| addressee name =  
| addressee name =  
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:@ Xcel Energym U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 PWR [Pressurized Water Reactor1 Vessel lnternals Program for Fulfillment of Prairie Island Nuclear Generating Plant (PINGP) License Renewal Commitment 25 By letter dated April 11,2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081130666), the Nuclear Management Company, LLC, (NMC') submitted an Application for Renewed Operating Licenses (LRA) for PINGP, Units 1 and 2. The LRA included commitment 25 related to the submittal of the PINGP PWR Vessel lnternals Program (PVIP) for NRC review and approval. In a letter dated May 12,2009 (ML091470263), NSPM updated the LRA to incorporate information regarding the new PWR vessel internals program. Renewed operating licenses DPR-42 and DPR-60 were issued June 27,201 1 including commitment
{{#Wiki_filter:@ Xcel Energym U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 PWR [Pressurized Water Reactor1Vessel lnternals Program for Fulfillment of Prairie Island Nuclear Generating Plant (PINGP) License Renewal Commitment 25 By letter dated April 11,2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081130666), the Nuclear Management Company, LLC, (NMC') submitted an Application for Renewed Operating Licenses (LRA) for PINGP, Units 1 and 2. The LRA included commitment 25 related to the submittal of the PINGP PWR Vessel lnternals Program (PVIP) for NRC review and approval. In a letter dated May 12,2009 (ML091470263), NSPM updated the LRA to incorporate information regarding the new PWR vessel internals program. Renewed operating licenses DPR-42 and DPR-60 were issued June 27,201 1 including commitment 25.
: 25. The implementation schedule for part B of commitment 25 was August 9, 201 1 (Unit
The implementation schedule for part B of commitment 25 was August 9, 201 1 (Unit 1) and October 29,2012 (Unit 2). The NRC issued Regulatory Issue Summary (RIS) 201 1-07, "License Renewal Submittal Information for Pressurized Water Reactor lnternals Aging Management," (MLI 11990086) on July 21, 201 1. In accordance with the guidance of RIS 201 1-07, by letter dated August 8, 201 1 (MLI 12210299), NSPM revised the date for submittal of the PINGP PVlP to October 1, 2012. , "PWR Vessel lnternals Program", provides the PINGP PVlP in fulfillment of commitment 25, part B.
: 1) and October 29,2012 (Unit 2). The NRC issued Regulatory Issue Summary (RIS) 201 1-07, "License Renewal Submittal Information for Pressurized Water Reactor lnternals Aging Management," (MLI 11990086) on July 21, 201 1. In accordance with the guidance of RIS 201 1-07, by letter dated August 8, 201 1 (MLI 12210299), NSPM revised the date for submittal of the PINGP PVlP to October 1, 2012. Enclosure 1, "PWR Vessel lnternals Program", provides the PINGP PVlP in fulfillment of commitment 25, part B. The PINGP PVlP is based on ERPl Report 1016596, "Materials Reliability
The PINGP PVlP is based on ERPl Report 1016596, "Materials Reliability
* On September 22, 2008, NMC transferred its operating authority to Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM").
* On September 22, 2008, NMC transferred its operating authority to Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"). By letter dated September 3, 2008 (ML082470648), NSPM assumed responsibility for actions and commitments previously submitted by NMC.
By letter dated September 3, 2008 (ML082470648), NSPM assumed responsibility for actions and commitments previously submitted by NMC. 171 7 Wakonade Drive East e Welch, Minnesota 55089-9642 Telephone:
1717 Wakonade Drive East e Welch, Minnesota 55089-9642 Telephone: 651.388.1121
651.388.1 121 Document Control Desk Page 2 Program (MRP): Pressurized Water Reactor lnternals Inspection and Evaluation Guidelines" (MRP-227-A), which has been endorsed by the NRC (ML120270374).
 
The NRC December 16, 201 1 safety evaluation for MRP-227, Rev 0 (MLI 1308A770), contained eight licensee action items for licensees to consider. NSPM will provide the considerations of these eight licensee action items to the NRC by April I, 201 3. If there are any questions or if additional information is needed, please contact Mr. Dale Vincent, P.E., at 651-388-1 121, Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
Document Control Desk Page 2 Program (MRP): Pressurized Water Reactor lnternals Inspection and Evaluation Guidelines" (MRP-227-A), which has been endorsed by the NRC (ML120270374). The NRC December 16, 201 1 safety evaluation for MRP-227, Rev 0 (MLI 1308A770),
This letter fulfills the requirements of license renewal commitment 25, part B. L Joel P. Sorensen Acting Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (1) cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC Enclosure 1 Prairie Island Nuclear Generating Plant, Units 1 and 2 PWR Vessel lnternals Program Page 1 of 16 Enclosure 1 MRP-227-A Primary Inspection Components Page 2 of 16 Item Control Rod Guide Tube Assembly Guide plates (cards) Control Rod Guide Tube Assembly Lower flange welds Core Barrel Assembly Upper core barrel flange weld Core Barrel Assembly Upper and lower core barrel cylinder girth welds Applicability All Plants All Plants All Plants All Plants Effect (Mechanism) Loss of Material (Wear) Cracking (SCC, Fatigue) Aging Management (IE and TE) Cracking (SCC) Cracking (SCC, IASCC, Fatigue) Expansion Link (Note 1) None Bottom-mounted instrumentation (BMI) column bodies, Lower support column bodies (cast) Upper core plate Lower support forginglcasting Lower Support column bodies (non cast) Core barrel outlet nozzle welds. Upper and lower core barrel cylinder axial welds Examination MethodlFrequency (Note 1) Visual (VT-3) examination no later than 2 refueling outages from the beginning of the license renewal period, and no earlier than two refueling outages prior to the start of the license renewal period. Subsequent examinations are required on a ten-year interval. Enhanced visual (EVT-1) examination to determine the presence of crack-like surface flaws in flange welds no later than 2 refueling outages from the beginning of the license renewal period and subsequent examination on a ten- year interval.
contained eight licensee action items for licensees to consider. NSPM will provide the considerations of these eight licensee action items to the NRC by April I, 2013.
Periodic enhanced visual (EVT-1) examination, no later than 2 refueling outages from the beginning of the license renewal period and subsequent examination on a ten- year interval.
If there are any questions or if additional information is needed, please contact Mr. Dale Vincent, P.E., at 651-388-1 121, Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
Periodic enhanced visual (EVT-1) examination, no later than 2 refueling outages from the beginning of the license renewal period and subsequent examination on a ten- year interval. Examination Coverage 20% examination of the number of CRGT assemblies, with all guide cards within each selected CRGT assembly examined. 100% of outer (accessible) CRGT lower flange weld surfaces and adjacent base metal on the individual periphery CRGT assemblies. (Note 2). 100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 4). 100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 4).
This letter fulfills the requirements of license renewal commitment 25, part B.
Enclosure 1 MRP-227-A Primary Inspection Components Page 3 of 16 Examination Coverage Item Core Barrel Assembly Lower core barrel flange weld (Note
L Joel P. Sorensen Acting Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (1) cc:     Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC
: 5) Baffle-Former Assembly Baffle-edge bolts Baffle-Former Assembly Baffle-former bolts Applicability Effect (Mechanism)
 
All plants All plants with baffle-edge bolts All plants Expansion Link (Note 1) Cracking (SCC, Fatigue) Cracking (IASCC, Fatigue) that results in: Lost or broken locking devices Failed or missing bolts Protrusion of bolt heads Aging Management (IE and ISR) (Note 6) Cracking (IASCC, Fatigue) Aging Management (IE and ISR) (Note 6) Examination MethodlFrequency (Note 1) None None Lower support column bolts, Barrel-former bolts Periodic enhanced visual (EVT-1) examination, no later than refueling outages from the beginning of the license renewal period and subsequent examination on a ten- year interval.
Enclosure 1 Prairie Island Nuclear Generating Plant, Units 1 and 2 PWR Vessel lnternals Program Page 1 of 16
Visual (VT-3) examination, with baseline examination between 20 and 40 EFPY and subsequent examinations and a ten-year interval. Baseline volumetric (UT) examination between 25 and 35 EFPY, with subsequent examination on a ten- year interval. 100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 4). Bolts and locking devices on high fluence seams. 100% of components accessible from core side (Note 3). 100% of accessible bolts (Note 3). Heads accessible from the core side. UT accessibility may be affected by complexity of head and locking device designs.
 
Enclosure 1 MRP-227-A Primary Inspection Components Page 4 of 16 Item Baffle-Former Assembly Assembly (includes: Baffle plates, baffle edge bolts and indirect effects of void swelling in former plates) Alignment and Interfacing components Internals hold down spring Applicability Effect (Mechanism)
MRP-227-A Primary Inspection Components Expansion Link                      Examination Item           Applicability  Effect (Mechanism)                                                                            Examination Coverage (Note 1)              MethodlFrequency (Note 1)
All plants All plants with 304 stainless steel hold down springs Expansion Link (Note 1) Distortion (Void Swelling), or Cracking (IASCC) that results in: *Abnormal interaction with fuel assemblies
Control Rod Guide       All Plants      Loss of Material (Wear) None                        Visual (VT-3) examination no later      20% examination of the number Tube Assembly                                                                               than 2 refueling outages from the      of CRGT assemblies, with all Guide plates (cards)                                                                         beginning of the license renewal        guide cards within each period, and no earlier than two        selected CRGT assembly refueling outages prior to the start of examined.
*Gaps along high fluence baffle joint -Vertical displacement of baffle plates near high fluence joint Broken or damaged edge bolt locking systems along high fluence baffle joint Distortion (Loss of load) Note: This mechanism was not strictly identified in the original 'list of age- related degradation mechanisms'
the license renewal period.
[7]. Examination MethodlFrequency (Note 1) Examination Coverage None None Visual ((VT-3) examination to check for evidence of distortion, with baseline examination between 20 and 40 EFPY and subsequent examinations on a ten-year interval. Direct measurement of spring height within three cycles of the beginning of the license renewal period.
Subsequent examinations are required on a ten-year interval.
If the first set of measurements is not sufficient to determine life, spring height measurements must be taken during the next two outages, in order to extrapolate the expected spring height to 60 years. Core side surface as indicated. Measurements should be taken at several points around the circumference of the spring, with a statistically adequate number of measurements at each point to minimize uncertainty.
Control Rod Guide        All Plants      Cracking (SCC, Fatigue) Bottom-mounted             Enhanced visual (EVT-1)                 100% of outer (accessible)
Enclosure 1 MRP-227-A Primary Inspection Components Notes to Table 4-3: 1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3. 2. A minimum of 75%
Tube Assembly                            Aging                  instrumentation            examination to determine the            CRGT lower flange weld Lower flange welds                        Management (IE and    (BMI) column bodies,        presence of crack-like surface flaws    surfaces and adjacent base TE)                    Lower support              in flange welds no later than 2         metal on the individual column bodies (cast)        refueling outages from the beginning   periphery CRGT assemblies.
of the total identified sample population must be examined.
Upper core plate            of the license renewal period and       (Note 2).
: 3. A minimum of 75% of the total population (examined
Lower support              subsequent examination on a ten-forginglcasting            year interval.
+ unexamined), including coverage consistent with the Expansion criteria in Table 5-3, must be examined for inspection credit. 4. A minimum of 75% of the total weld length (examined  
Core Barrel Assembly    All Plants      Cracking (SCC)          Lower Support              Periodic enhanced visual (EVT-1)       100% of one side of the Upper core barrel flange                                         column bodies (non          examination, no later than 2 refueling accessible surfaces of the weld                                                            cast)                      outages from the beginning of the       selected weld and adjacent Core barrel outlet          license renewal period and              base metal (Note 4).
+ unexamined), including coverage consistent with the Expansion criteria in Table 5-3, must be examined from either the inner or outer diameter for inspection credit.
nozzle welds.              subsequent examination on a ten-year interval.
Core Barrel Assembly    All Plants      Cracking (SCC, IASCC,  Upper and lower core        Periodic enhanced visual (EVT-1)       100% of one side of the Upper and lower core                    Fatigue)                barrel cylinder axial welds examination, no later than 2 refueling accessible surfaces of the barrel cylinder girth                                                                        outages from the beginning of the       selected weld and adjacent welds                                                                                        license renewal period and             base metal (Note 4).
subsequent examination on a ten-year interval.
Page 2 of 16
 
MRP-227-A Primary Inspection Components Expansion Link                      Examination Item            Applicability    Effect (Mechanism)                                                                          Examination Coverage (Note 1)               MethodlFrequency (Note 1)
Core Barrel Assembly    All plants        Cracking (SCC, Fatigue)    None                      Periodic enhanced visual (EVT-1)      100% of one side of the Lower core barrel flange                                                                        examination, no later than refueling  accessible surfaces of the weld (Note 5)                                                                                   outages from the beginning of the    selected weld and adjacent license renewal period and            base metal (Note 4).
subsequent examination on a ten-year interval.
Baffle-Former            All plants with  Cracking (IASCC,          None                      Visual (VT-3) examination, with      Bolts and locking devices on Assembly                baffle-edge bolts Fatigue) that results in:                            baseline examination between 20      high fluence seams. 100% of Baffle-edge bolts                                    Lost or broken                            and 40 EFPY and subsequent            components accessible from locking devices                            examinations and a ten-year interval. core side (Note 3).
Failed or missing bolts Protrusion of bolt heads Aging Management (IE and ISR) (Note 6)
Baffle-Former           All plants       Cracking (IASCC,          Lower support column      Baseline volumetric (UT) examination  100% of accessible bolts (Note Assembly                                  Fatigue) Aging            bolts, Barrel-former bolts between 25 and 35 EFPY, with          3). Heads accessible from the Baffle-former bolts                       Management (IE and ISR)                               subsequent examination on a ten-      core side. UT accessibility may (Note 6)                                             year interval.                        be affected by complexity of head and locking device designs.
Page 3 of 16
 
MRP-227-A Primary Inspection Components Item                                                                Expansion Link            Examination Applicability      Effect (Mechanism)                                                                     Examination Coverage (Note 1)      MethodlFrequency (Note 1)
Baffle-Former              All plants          Distortion (Void Swelling),   None            Visual ((VT-3) examination to check      Core side surface as indicated.
Assembly                                        or Cracking (IASCC) that                      for evidence of distortion, with Assembly                                        results in:                                  baseline examination between 20 (includes: Baffle plates,                            *Abnormal                              and 40 EFPY and subsequent baffle edge bolts and                                        interaction with                examinations on a ten-year interval.
indirect effects of void                                    fuel assemblies swelling in former                                    *Gaps along high plates)                                                    fluence baffle joint
                                                      -Vertical displacement of baffle plates near high fluence joint Broken or damaged edge bolt locking systems along high fluence baffle joint Alignment and              All plants with 304  Distortion (Loss of load)     None            Direct measurement of spring height      Measurements should be taken Interfacing                stainless steel hold                                              within three cycles of the beginning of at several points around the components                down springs        Note: This mechanism                          the license renewal period. If the first circumference of the spring, Internals hold down                            was not strictly identified                  set of measurements is not sufficient    with a statistically adequate spring                                          in the original 'list of age-                to determine life, spring height        number of measurements at related degradation                          measurements must be taken during        each point to minimize mechanisms' [7].                              the next two outages, in order to        uncertainty.
extrapolate the expected spring height to 60 years.
Page 4 of 16
 
MRP-227-A Primary Inspection Components Expansion Link                        Examination Item                  Applicability      Effect (Mechanism)                                                                                  Examination Coverage (Note 1)                 MethodlFrequency (Note 1)
Thermal Shield              All plants with      Cracking (Fatigue) or Loss  None                         Visual (VT-3) no later than 2 refueling 100% of thermal shield Assembly                    thermal shields      of Material (Wear) that                                    outages from the beginning of the      flexures.
Thermal Shield                                    results in thermal shield                                  license renewal period. Subsequent Assembly                                          flexures excessive wear,                                    examinations on a ten-year interval.
fracture, or complete separation.
Notes to Table 4-3:
: 1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3.
: 2. A minimum of 75% of the total identified sample population must be examined.
: 3. A minimum of 75% of the total population (examined + unexamined), including coverage consistent with the Expansion criteria in Table 5-3, 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 Table 5-3, must be examined from either the inner or outer diameter for inspection credit.
: 5. The lower core barrel flange weld may be alternatively designated as the core barrel-to-support plate weld in some Westinghouse plant designs.
: 5. The lower core barrel flange weld may be alternatively designated as the core barrel-to-support plate weld in some Westinghouse plant designs.
: 6. Void swelling effects on this component is managed through management of void swelling on the entire baffle-former assembly.
: 6. Void swelling effects on this component is managed through management of void swelling on the entire baffle-former assembly.
Item Thermal Shield Assembly Thermal Shield Assembly Applicability Effect (Mechanism)
All plants with thermal shields Expansion Link (Note 1) Cracking (Fatigue) or Loss of Material (Wear) that results in thermal shield flexures excessive wear, fracture, or complete separation.
Examination MethodlFrequency (Note 1) Examination Coverage None Visual (VT-3) no later than 2 refueling outages from the beginning of the license renewal period. Subsequent examinations on a ten-year interval.
100% of thermal shield flexures.
Enclosure 1 MRP-227-A Primary Inspection Components Examination Coverage 100% of accessible surfaces (Note 2). 100% of accessible surfaces (Note 2). 100% of accessible bolts. Accessibility may be limited by presence of thermal shields or neutron pads (Note 2). 100% of accessible bolts or as supported by plant-specific justification (Note 2). Examination MethodlFrequency (Note 1) Enhanced visual (EVT-1) examination. Re-inspection every 10 years following initial inspection. Enhanced visual (EVT-1) examination. Re-inspection every 10 years following initial inspection.
Volumetric (UT) examination.
Re-inspection every 10 years following initial inspection.
Volumetric (UT) examination. Re-inspection every 10 years following initial inspection. Expansion Link (Note 1) CRGT lower flange weld CRGT lower flange weld Baffle-former bolts Baffle-former bolts Item Upper lnternals Assembly Upper core plate Lower lnternals Assembly Lower support forging or castings Core Barrel Assembly Barrel-former bolts Lower Support Assembly Lower support column bolts Applicability All plants All plants All plants All plants Effect (Mechanism)
Cracking (Fatigue, Wear) Cracking Aging management (TE in Casting) Cracking (IASCC, Fatigue)
Aging Management (IE. Void Swelling and ISR) Cracking (IASCC, Fatigue) Aging Management (IE and ISR)
Enclosure 1 MRP-227-A Primary Inspection Components Page 7 of 16 Item Core Barrel Assembly Core barrel outlet nozzle welds Core Barrel Assembly Upper and lower core barrel cylinder axial welds Lower Support Assembly Lower support column bodes (non cast) Lower Support Assembly Lower support column bodes (cast) Applicability All plants All plants All plants All plants Effect (Mechanism)
Cracking (SCC, Fatigue) Aging Management (IE of lower sections)
Cracking (SCC, IASCC)
Aging Management (IE)
Cracking (IASCC) Aging Management (IE)
Cracking (IASCC) including the detection of fractured support columns Aging Management (IE) Expansion Link (Note 1) Upper core barrel flange weld Upper and lower core barrel cylinder girth welds Upper core barrel flange weld Control rod guide tube (CRGT) lower flanges Examination MethodlFrequency (Note 1) Enhanced visual (Em-1) examination. Re-inspection every 10 years following initial inspection. Enhanced visual (EVT-1) examination. Re-inspection every 10 years following initial inspection. Enhanced visual (EVT-1) examination.
Re-inspection every 10 years following initial inspection.
Visual (Em-1) examination.
Re-inspection every 10 years following initial inspection. Examination Coverage 100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 2). 100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 2). 100% of accessible surfaces (Note 2). 100% of accessible support columns (Note 2).
Enclosure 1 MRP-227-A Primary Inspection Components Notes to Table 4-6: 1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3. 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).
Item Bottom Mounted Instrumentation System Bottom-mounted instrumentation (BMI) column bodies Applicability All plants Effect (Mechanism) Cracking (Fatigue) including the detection of completely fractured column Aging Management (IE). Expansion Link (Note 1) Control rod guide tube (CRGT) lower flanges Examination MethodlFrequency (Note 1) Visual (VT-3) examination of BMI column bodies as indicated by difficulty of insertion/withdrawal of flux thimbles. Re-inspection every 10 years following initial inspection. Flux thimble insertion/withdrawal to be monitored at each inspection interval. Examination Coverage 100% of BMI column bodies for which difficulty is detected during flux thimble insertionlwithdrawal.
Enclosure 1 MRP-227-A Primary Inspection Components Notes to Table 4-9: 1. XL = "Extra Long" referring to Westinghouse plants with 14-foot cores.
: 2. Bolt was screened in because of stress relaxation and associated cracking; however, wear of the clevislinsert is the issue Item Core Barrel Assembly Core barrel flange Upper lnternals Assembly Upper support ring or skirt Lower lnternals Assembly Lower core plate XL lower core plate (Note 1) Lower lnternals Assembly Lower core plate XL lower core plate (Note 1) Bottom Mounted Instrumentation System Flux thimble tubes Alignment and Interfacing Components Clevis insert bolts Alignment and Interfacing


Components Upper core plate alignment pins Applicability All plants All plants All plants All plants All plants All plants All plants Effect (Mechanism) Loss of material (Wear) Cracking (SCC, Fatigue) Cracking (IASCC, Fatigue) Aging Management (IE) Loss of material (Wear) Loss of material (Wear) Loss of material (Wear) (Note 2) Loss of material (Wear) Expansion Link (Note 1) ASME Code Section XI ASME Code Section XI ASME Code Section XI ASME Code Section XI NUREG-1801 Rev. 1 ASME Code Section XI ASME Code Section XI Examination MethodlFrequency (Note 1) Visual (VT-3) examination to determine general condition for excessive wear. Visual (VT-3) examination.
MRP-227-A Primary Inspection Components Expansion Link                  Examination Item              Applicability   Effect (Mechanism)                                                           Examination Coverage (Note 1)         MethodlFrequency (Note 1)
Visual (VT-3) examination of the lower core plates to detect evidence of distortion andlor loss of bolt integrity.
Upper lnternals          All plants      Cracking               CRGT lower flange weld Enhanced visual (EVT-1)       100% of accessible surfaces Assembly                                  (Fatigue, Wear)                               examination.                  (Note 2).
Visual (VT-3) examination Surface (ET) examination.
Upper core plate                                                                        Re-inspection every 10 years following initial inspection.
Visual (VT-3) examination Visual (VT-3) examination Examination Coverage All accessible surfaces at specified frequency All accessible surfaces at specified frequency All accessible surfaces at specified frequency All accessible surfaces at specified frequency Eddy current surface examination as defined in plant response to IEB 88-09. All accessible surfaces at specified frequency All accessible surfaces at specified frequency Enclosure 1 MRP-227-A Primary Inspection Components Page 10 of 16 Item Control Rod Guide Tube Assembly Guide plates (cards) Control Rod Guide Tube Assembly Lower flange welds Applicability All plants All plants Examination Acceptance Criteria (Note
Lower lnternals          All plants      Cracking              CRGT lower flange weld Enhanced visual (EVT-1)       100% of accessible surfaces Assembly                                  Aging management (TE                          examination.                  (Note 2).
: 1) Visual (VT-3) examination The specific relevant condition is wear that could lead to loss of control and alignment and impede control assembly insertion. Enhanced visual (EVT-1) examination The specific relevant condition is a detectable crack-like surface indication Expansion Link(s) None a. Bottom-mounted instrumentation (BMI) column bodies b. Lower support column bodies (cast), upper core plate and lower support forging or casting Expansion Criteria N/A a. Confirmation of surface- breaking indications in two or more CRGT lower flange welds, combined with flux thimble insertionlwithdrawal difficulty, shall require visual (VT-3) examination of BMI column bodies by the completion of the next refueling outage. b. Confirmation of surface- breaking indications in two or more CRGT lower flange welds shall require EVT-1 examination of cast lower support column bodies, upper core plate and lower support forginglcastings within three fuel cycles following the initial observation. Additional Examination Acceptance Criteria NIA a. For BMI column bodies, the specific relevant condition for the VT-3 examination is completely fractured column bodies. b. For cast lower support column bodies, upper core plate and lower support forginglcastings, the specific relevant condition is a detectable crack-like surface indication.
Lower support forging or                  in Casting)                                   Re-inspection every 10 years castings                                                                                following initial inspection.
Enclosure 1 MRP-227-A Primary Inspection Components Additional Examination Acceptance Criteria a and b. The specific relevant condition for the expansion core barrel outlet nozzle weld and lower support column body examination is a detectable crack-like surface indication.
Core Barrel Assembly    All plants      Cracking              Baffle-former bolts    Volumetric (UT) examination. 100% of accessible bolts.
Item Core Barrel Assembly Upper core barrel flange weld Expansion Link(s) a. Core barrel outlet nozzle welds
Barrel-former bolts                      (IASCC, Fatigue)                             Re-inspection every 10 years  Accessibility may be limited by Aging Management (IE.                        following initial inspection. presence of thermal shields or Void Swelling and ISR)                                                     neutron pads (Note 2).
: b. Lower support column bodies (non cast) Expansion Criteria
Lower Support            All plants      Cracking              Baffle-former bolts    Volumetric (UT) examination. 100% of accessible bolts or as Assembly                                  (IASCC, Fatigue)                              Re-inspection every 10 years supported by plant-specific Lower support column                      Aging Management (IE                          following initial inspection. justification (Note 2).
: a. The confirmed detection and sizing of a surface- breaking indication with a length greater than two inches in the upper core barrel flange weld shall require that the EVT-1 examination be expanded to include the core barrel outlet nozzle welds by the completion of the next refueling outage. b. If extensive cracking in the core barrel outlet nozzle welds is detected, EVT-1 examination shall be expanded to include the upper six inches of the accessible surfaces of the non-cast lower support column bodies within three fuel cycles following the initial observation.
bolts                                    and ISR)
Applicability All plants Examination Acceptance Criteria (Note
 
: 1) Periodic enhanced visual (EVT-1) examination. The specific relevant condition is a detectable crack-like surface indication.
MRP-227-A Primary Inspection Components Item                                                          Expansion Link                    Examination Applicability  Effect (Mechanism)                                                                Examination Coverage (Note 1)            MethodlFrequency (Note 1)
Enclosure 1 MRP-227-A Primary Inspection Components Lower core barrel flange weld (Note 2) Upper core barrel cylinder girth welds Applicability The specific relevant condition is a detectable crack-like All plants Periodic enhanced visual None (EVT-1) examination All plants Periodic enhanced visual Upper core barrel (EVT-1) examination cylinder axial welds Examination Acceptance Criteria (Note
Core Barrel Assembly      All plants      Cracking (SCC, Fatigue)    Upper core barrel flange Enhanced visual (Em-1)        100% of one side of the Core barrel outlet nozzle                  Aging Management (IE of    weld                    examination.                  accessible surfaces of the welds                                      lower sections)                                    Re-inspection every 10 years  selected weld and adjacent following initial inspection. base metal (Note 2).
: 1) None The specific relevant condition is a detectable crack-like surface indication.
Core Barrel Assembly      All plants      Cracking (SCC, IASCC)      Upper and lower core    Enhanced visual (EVT-1)      100% of one side of the Upper and lower core                      Aging Management (IE)     barrel cylinder girth    examination.                  accessible surfaces of the barrel cylinder axial                                                welds                    Re-inspection every 10 years  selected weld and adjacent welds                                                                                         following initial inspection. base metal (Note 2).
The confirmed detection and sizing of a surface- breaking indication with a length greater than two inches in the upper core barrel cylinder girth welds shall require that the EVT-1 examination be expanded to include the upper core barrel cylinder axial welds by the completion of the next refueling outage. Expansion Link(s) Additional Examination Acceptance Criteria Expansion Criteria None The specific relevant condition for the expansion upper core barrel cylinder axial weld examination is a detectable crack-like surface indication.
Lower Support            All plants      Cracking (IASCC)          Upper core barrel flange Enhanced visual (EVT-1)       100% of accessible surfaces Assembly                                  Aging Management (IE)     weld                    examination.                 (Note 2).
Page 12 of 16 Enclosure 1 MRP-227-A Primary Inspection Components Page 13 of 16 Item Core Barrel Assembly Lower core barrel cylinder girth welds Baffle-Former Assembly Baffle-edge bolts Applicability All plants All plants with baffle-edge bolts Examination Acceptance Criteria (Note I) Periodic enhanced visual (EVT-1) examination The specific relevant condition is a detectable crack-like surface indication.
Lower support column                                                                          Re-inspection every 10 years bodes (non cast)                                                                               following initial inspection.
Visual (VT-3) examination. The specific relevant conditions are missing or broken locking devices.
Lower Support            All plants      Cracking (IASCC)          Control rod guide tube  Visual (Em-1) examination. 100% of accessible support Assembly                                  including the detection of (CRGT) lower flanges    Re-inspection every 10 years  columns (Note 2).
failed or missing bolts, and protrusion of bolt heads. Expansion Link(s) Lower core barrel cylinder axial welds None Expansion Criteria The confirmed detection and sizing of a surface- breaking indication with a length greater than two inches in the lower core barrel cylinder girth welds shall require that the EVT-1 examination be expanded to include the lower core barrel cylinder axial welds by the completion of the next refueling outage.
Lower support column                      fractured support                                   following initial inspection.
N/A Additional Examination Acceptance Criteria The specific relevant condition for the expansion lower core barrel cylinder axial weld examination is a detectable crack-like surface indication.
bodes (cast)                              columns Aging Management (IE)
N/A Enclosure 1 MRP-227-A Primary Inspection Components Page 14 of 16 Additional Examination Acceptance Criteria a and b. The examination acceptance criteria for the UT of the lower support column bolts and the barrel-former bolts shall be established as part of the examination technical justification.
Page 7 of 16
Item Baffle-Former Assembly Baffle-former bolts Expansion Link(s) a. Lower support column bolts b. Barrel-former bolts Expansion Criteria
 
: a. Confirmation that more than 5% of the baffle- former bolts actually examined on the four baffle plates at the largest distance from the core (presumed to be the lowest dose locations) contain unacceptable indications shall require UT examination of the lower support column bolts within the next three fuel cycles. b. Confirmation that more than 5% of the lower support column bolts actually examined contain unacceptable indications shall require UT examination of the barrel- former bolts. Applicability All plants Examination Acceptance Criteria (Note
MRP-227-A Primary Inspection Components Expansion Link                        Examination Item                  Applicability        Effect (Mechanism)                                                                             Examination Coverage (Note 1)              MethodlFrequency (Note 1)
: 1) Volumetric (UT) examination.
Bottom Mounted              All plants            Cracking (Fatigue)          Control rod guide tube    Visual (VT-3) examination of BMI      100% of BMI column bodies for Instrumentation System                            including the detection of (CRGT) lower flanges      column bodies as indicated by        which difficulty is detected Bottom-mounted                                    completely fractured                                  difficulty of insertion/withdrawal of during flux thimble instrumentation (BMI)                              column                                                flux thimbles.                        insertionlwithdrawal.
The examination acceptance criteria for the UT of the baffle-former bolts shall be established as part of the examination technical justification.
column bodies                                     Aging Management                                      Re-inspection every 10 years (IE).                                                  following initial inspection.
Enclosure 1 MRP-227-A Primary Inspection Components Page 15 of 16 Additional Examination Acceptance Criteria NIA NIA Expansion Criteria NIA NIA Expansion Link@) None None Item Baffle-Former Assembly Assembly Alignment and Interfacing Components lnternals hold down spring Applicability All plants All plants with 304 stainless steel hold down springs Examination Acceptance Criteria (Note I) Visual (VT-3) examination.
Flux thimble insertion/withdrawal to be monitored at each inspection interval.
The specific relevant conditions are evidence of abnormal interaction with fuel assemblies, gaps along high fluence shroud plate joints, vertical displacement of shroud plates near high fluence joints, and broken or damaged edge bolt locking systems along high fl uence baffle plate joints. Direct physical measurement of spring height. The examination acceptance criterion for this measurement is that the remaining compressible height of the spring shall provide hold- down forces within the plant- specific design tolerance.
Notes to Table 4-6:
Enclosure 1 MRP-227-A Primary Inspection Components Notes to Table 5-3: 1. The examination acceptance criterion for visual examination is the absence of the specified relevant condition(s).
: 1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3.
: 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).
 
MRP-227-A Primary Inspection Components Expansion Link                          Examination Item                  Applicability      Effect (Mechanism)                                                                            Examination Coverage (Note 1)                MethodlFrequency (Note 1)
Core Barrel Assembly         All plants            Loss of material (Wear)    ASME Code Section XI        Visual (VT-3) examination to        All accessible surfaces at Core barrel flange                                                                                          determine general condition for      specified frequency excessive wear.
Upper lnternals              All plants            Cracking (SCC, Fatigue)   ASME Code Section XI        Visual (VT-3) examination.           All accessible surfaces at Assembly                                                                                                                                        specified frequency Upper support ring or skirt Lower lnternals              All plants            Cracking (IASCC,          ASME Code Section XI        Visual (VT-3) examination of the     All accessible surfaces at Assembly                                            Fatigue)                                                lower core plates to detect evidence specified frequency Lower core plate                                    Aging Management (IE)                                  of distortion andlor loss of bolt XL lower core plate (Note                                                                                    integrity.
1)
Lower lnternals              All plants            Loss of material (Wear)    ASME Code Section XI        Visual (VT-3) examination            All accessible surfaces at Assembly                                                                                                                                        specified frequency Lower core plate XL lower core plate (Note 1)
Bottom Mounted                All plants            Loss of material (Wear)    NUREG-1801                  Surface (ET) examination.           Eddy current surface Instrumentation System                                                        Rev. 1                                                           examination as defined in plant Flux thimble tubes                                                                                                                              response to IEB 88-09.
Alignment and                All plants            Loss of material (Wear)    ASME Code Section XI        Visual (VT-3) examination            All accessible surfaces at Interfacing                                                                                                                                      specified frequency Components                                          (Note 2)
Clevis insert bolts Alignment and                All plants           Loss of material (Wear)   ASME Code Section XI        Visual (VT-3) examination           All accessible surfaces at Interfacing                                                                                                                                      specified frequency Components Upper core plate alignment pins Notes to Table 4-9:
: 1. XL = "Extra Long" referring to Westinghouse plants with 14-foot cores.
: 2. Bolt was screened in because of stress relaxation and associated cracking; however, wear of the clevislinsert is the issue
 
MRP-227-A Primary Inspection Components Examination Acceptance                                                                    Additional Examination Item        Applicability                                Expansion Link(s)          Expansion Criteria Criteria (Note 1)                                                                      Acceptance Criteria Control Rod Guide Tube All plants      Visual (VT-3) examination     None                    N/A                              NIA Assembly Guide plates (cards)                   The specific relevant condition is wear that could lead to loss of control and alignment and impede control assembly insertion.
Control Rod Guide Tube All plants      Enhanced visual (EVT-1)        a. Bottom-mounted        a. Confirmation of surface-     a. For BMI column bodies, the Assembly                               examination                    instrumentation (BMI)   breaking indications in two      specific relevant condition for Lower flange welds                                                    column bodies            or more CRGT lower flange        the VT-3 examination is The specific relevant                                   welds, combined with flux        completely fractured column condition is a detectable     b. Lower support        thimble insertionlwithdrawal    bodies.
crack-like surface indication column bodies (cast),    difficulty, shall require visual upper core plate and    (VT-3)   examination of BMI      b. For cast lower support lower support forging or column bodies by the            column bodies, upper core plate casting                  completion of the next          and lower support refueling outage.               forginglcastings, the specific relevant condition is a
: b. Confirmation of surface-     detectable crack-like surface breaking indications in two      indication.
or more CRGT lower flange welds shall require EVT-1 examination of cast lower support column bodies, upper core plate and lower support forginglcastings within three fuel cycles following the initial observation.
Page 10 of 16
 
MRP-227-A Primary Inspection Components Examination Acceptance                                                            Additional Examination Item                Applicability                                  Expansion Link(s)      Expansion Criteria Criteria (Note 1)                                                              Acceptance Criteria Core Barrel Assembly          All plants        Periodic enhanced visual      a. Core barrel outlet a. The confirmed detection  a and b. The specific relevant Upper core barrel flange weld                  (EVT-1) examination.           nozzle welds          and sizing of a surface-   condition for the expansion core breaking indication with a barrel outlet nozzle weld and The specific relevant condition b. Lower support     length greater than two    lower support column body is a detectable crack-like    column bodies (non    inches in the upper core   examination is a detectable surface indication.            cast)                 barrel flange weld shall   crack-like surface indication.
require that the EVT-1 examination be expanded to include the core barrel outlet nozzle welds by the completion of the next refueling outage.
: b. If extensive cracking in the core barrel outlet nozzle welds is detected, EVT-1 examination shall be expanded to include the upper six inches of the accessible surfaces of the non-cast lower support column bodies within three fuel cycles following the initial observation.
 
MRP-227-A Primary Inspection Components Examination Acceptance                                                             Additional Examination Applicability                                  Expansion Link(s)      Expansion Criteria Criteria (Note 1)                                                               Acceptance Criteria All plants        Periodic enhanced visual      None                None                        None Lower core barrel flange weld                      (EVT-1) examination (Note 2)
The specific relevant condition is a detectable crack-like All plants      Periodic enhanced visual        Upper core barrel    The confirmed detection      The specific relevant condition Upper core barrel cylinder girth                  (EVT-1) examination            cylinder axial welds and sizing of a surface-     for the expansion upper core welds                                                                                                  breaking indication with a  barrel cylinder axial weld The specific relevant condition                      length greater than two      examination is a detectable is a detectable crack-like                          inches in the upper core    crack-like surface indication.
surface indication.                                  barrel cylinder girth welds shall require that the EVT-1 examination be expanded to include the upper core barrel cylinder axial welds by the completion of the next refueling outage.
Page 12 of 16
 
MRP-227-A Primary Inspection Components Examination Acceptance                                                            Additional Examination Item                  Applicability                                  Expansion Link(s)      Expansion Criteria Criteria (Note I)                                                              Acceptance Criteria Core Barrel Assembly            All plants        Periodic enhanced visual      Lower core barrel    The confirmed detection      The specific relevant condition Lower core barrel cylinder girth                    (EVT-1) examination            cylinder axial welds and sizing of a surface-    for the expansion lower core welds                                                                                                  breaking indicationwith a    barrel cylinder axial weld The specific relevant condition                      length greater than two      examination is a detectable is a detectable crack-like                          inches in the lower core    crack-like surface indication.
surface indication.                                barrel cylinder girth welds shall require that the EVT-1 examination be expanded to include the lower core barrel cylinder axial welds by the completion of the next refueling outage.
Baffle-Former Assembly          All plants with  Visual (VT-3) examination.      None                N/A                          N/A Baffle-edge bolts                baffle-edge bolts The specific relevant conditions are missing or broken locking devices.
failed or missing bolts, and protrusion of bolt heads.
Page 13 of 16
 
MRP-227-A Primary Inspection Components Examination Acceptance                                                              Additional Examination Item        Applicability                                  Expansion Link(s)        Expansion Criteria Criteria (Note 1)                                                              Acceptance Criteria Baffle-Former Assembly All plants      Volumetric (UT) examination. a. Lower support      a. Confirmation that more  a and b. The examination Baffle-former bolts                                                    column bolts          than 5 % of the baffle-    acceptance criteria for the UT of The examination acceptance                            former bolts actually      the lower support column bolts criteria for the UT of the    b. Barrel-former bolts examined on the four baffle and the barrel-former bolts shall baffle-former bolts shall be                          plates at the largest      be established as part of the established as part of the                            distance from the core      examination technical examination technical                                (presumed to be the lowest  justification.
justification.                                        dose locations) contain unacceptable indications shall require UT examination of the lower support column bolts within the next three fuel cycles.
: b. Confirmation that more than 5% of the lower support column bolts actually examined contain unacceptable indications shall require UT examination of the barrel-former bolts.
Page 14 of 16
 
MRP-227-APrimary Inspection Components Examination Acceptance                                                Additional Examination Item            Applicability                                    Expansion Link@)  Expansion Criteria Criteria (Note I)                                                Acceptance Criteria Baffle-Former Assembly    All plants            Visual (VT-3) examination. None            NIA                  NIA Assembly The specific relevant conditions are evidence of abnormal interaction with fuel assemblies, gaps along high fluence shroud plate joints, vertical displacement of shroud plates near high fluence joints, and broken or damaged edge bolt locking systems along high f l uence baffle plate joints.
Alignment and Interfacing  All plants with 304  Direct physical measurement    None            NIA                  NIA Components                stainless steel hold  of spring height.
lnternals hold down spring down springs The examination acceptance criterion for this measurement is that the remaining compressible height of the spring shall provide hold-down forces within the plant-specific design tolerance.
Page 15 of 16
 
MRP-227-A Primary Inspection Components Examination Acceptance                                                                Additional Examination Item                    Applicability                                          Expansion Link@)            Expansion Criteria Criteria (Note 1)                                                                  Acceptance Criteria Thermal Shield Assembly            All plants with        Visual (VT-3) examination.      None                      N/A                        N/A Thermal shield fixtures            thermal shields The specific relevant conditions for thermal shield flexures are excessive wear, fracture, or complete separation.
Notes to Table 5-3:
: 1. The examination acceptance criterion for visual examination is the absence of the specified relevant condition(s).
: 2. The lower core barrel flange weld may alternatively be designated as the core barrel-to-support plate weld in some Westinghouse plant designs.
: 2. The lower core barrel flange weld may alternatively be designated as the core barrel-to-support plate weld in some Westinghouse plant designs.
Page 16 of 16 Additional Examination Acceptance Criteria N/A Item Thermal Shield Assembly Thermal shield fixtures Applicability All plants with thermal shields Examination Acceptance Criteria (Note
Page 16 of 16}}
: 1) Visual (VT-3) examination.
The specific relevant conditions for thermal shield flexures are excessive wear, fracture, or complete separation.
Expansion Link@) None Expansion Criteria N/A}}

Latest revision as of 22:51, 11 November 2019

PWR (Pressurized Water Reactor) Vessel Internals Program for Fulfillment of License Renewal Commitment 25
ML12276A041
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 10/01/2012
From: Sorensen J
Northern States Power Co, Xcel Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-PI-12-078
Download: ML12276A041 (18)
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@ Xcel Energym U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 PWR [Pressurized Water Reactor1Vessel lnternals Program for Fulfillment of Prairie Island Nuclear Generating Plant (PINGP) License Renewal Commitment 25 By letter dated April 11,2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081130666), the Nuclear Management Company, LLC, (NMC') submitted an Application for Renewed Operating Licenses (LRA) for PINGP, Units 1 and 2. The LRA included commitment 25 related to the submittal of the PINGP PWR Vessel lnternals Program (PVIP) for NRC review and approval. In a letter dated May 12,2009 (ML091470263), NSPM updated the LRA to incorporate information regarding the new PWR vessel internals program. Renewed operating licenses DPR-42 and DPR-60 were issued June 27,201 1 including commitment 25.

The implementation schedule for part B of commitment 25 was August 9, 201 1 (Unit 1) and October 29,2012 (Unit 2). The NRC issued Regulatory Issue Summary (RIS) 201 1-07, "License Renewal Submittal Information for Pressurized Water Reactor lnternals Aging Management," (MLI 11990086) on July 21, 201 1. In accordance with the guidance of RIS 201 1-07, by letter dated August 8, 201 1 (MLI 12210299), NSPM revised the date for submittal of the PINGP PVlP to October 1, 2012. , "PWR Vessel lnternals Program", provides the PINGP PVlP in fulfillment of commitment 25, part B.

The PINGP PVlP is based on ERPl Report 1016596, "Materials Reliability

  • On September 22, 2008, NMC transferred its operating authority to Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"). By letter dated September 3, 2008 (ML082470648), NSPM assumed responsibility for actions and commitments previously submitted by NMC.

1717 Wakonade Drive East e Welch, Minnesota 55089-9642 Telephone: 651.388.1121

Document Control Desk Page 2 Program (MRP): Pressurized Water Reactor lnternals Inspection and Evaluation Guidelines" (MRP-227-A), which has been endorsed by the NRC (ML120270374). The NRC December 16, 201 1 safety evaluation for MRP-227, Rev 0 (MLI 1308A770),

contained eight licensee action items for licensees to consider. NSPM will provide the considerations of these eight licensee action items to the NRC by April I, 2013.

If there are any questions or if additional information is needed, please contact Mr. Dale Vincent, P.E., at 651-388-1 121, Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

This letter fulfills the requirements of license renewal commitment 25, part B.

L Joel P. Sorensen Acting Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosures (1) cc: Administrator, Region Ill, USNRC Project Manager, PINGP, USNRC Resident Inspector, PINGP, USNRC

Enclosure 1 Prairie Island Nuclear Generating Plant, Units 1 and 2 PWR Vessel lnternals Program Page 1 of 16

MRP-227-A Primary Inspection Components Expansion Link Examination Item Applicability Effect (Mechanism) Examination Coverage (Note 1) MethodlFrequency (Note 1)

Control Rod Guide All Plants Loss of Material (Wear) None Visual (VT-3) examination no later 20% examination of the number Tube Assembly than 2 refueling outages from the of CRGT assemblies, with all Guide plates (cards) beginning of the license renewal guide cards within each period, and no earlier than two selected CRGT assembly refueling outages prior to the start of examined.

the license renewal period.

Subsequent examinations are required on a ten-year interval.

Control Rod Guide All Plants Cracking (SCC, Fatigue) Bottom-mounted Enhanced visual (EVT-1) 100% of outer (accessible)

Tube Assembly Aging instrumentation examination to determine the CRGT lower flange weld Lower flange welds Management (IE and (BMI) column bodies, presence of crack-like surface flaws surfaces and adjacent base TE) Lower support in flange welds no later than 2 metal on the individual column bodies (cast) refueling outages from the beginning periphery CRGT assemblies.

Upper core plate of the license renewal period and (Note 2).

Lower support subsequent examination on a ten-forginglcasting year interval.

Core Barrel Assembly All Plants Cracking (SCC) Lower Support Periodic enhanced visual (EVT-1) 100% of one side of the Upper core barrel flange column bodies (non examination, no later than 2 refueling accessible surfaces of the weld cast) outages from the beginning of the selected weld and adjacent Core barrel outlet license renewal period and base metal (Note 4).

nozzle welds. subsequent examination on a ten-year interval.

Core Barrel Assembly All Plants Cracking (SCC, IASCC, Upper and lower core Periodic enhanced visual (EVT-1) 100% of one side of the Upper and lower core Fatigue) barrel cylinder axial welds examination, no later than 2 refueling accessible surfaces of the barrel cylinder girth outages from the beginning of the selected weld and adjacent welds license renewal period and base metal (Note 4).

subsequent examination on a ten-year interval.

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MRP-227-A Primary Inspection Components Expansion Link Examination Item Applicability Effect (Mechanism) Examination Coverage (Note 1) MethodlFrequency (Note 1)

Core Barrel Assembly All plants Cracking (SCC, Fatigue) None Periodic enhanced visual (EVT-1) 100% of one side of the Lower core barrel flange examination, no later than refueling accessible surfaces of the weld (Note 5) outages from the beginning of the selected weld and adjacent license renewal period and base metal (Note 4).

subsequent examination on a ten-year interval.

Baffle-Former All plants with Cracking (IASCC, None Visual (VT-3) examination, with Bolts and locking devices on Assembly baffle-edge bolts Fatigue) that results in: baseline examination between 20 high fluence seams. 100% of Baffle-edge bolts Lost or broken and 40 EFPY and subsequent components accessible from locking devices examinations and a ten-year interval. core side (Note 3).

Failed or missing bolts Protrusion of bolt heads Aging Management (IE and ISR) (Note 6)

Baffle-Former All plants Cracking (IASCC, Lower support column Baseline volumetric (UT) examination 100% of accessible bolts (Note Assembly Fatigue) Aging bolts, Barrel-former bolts between 25 and 35 EFPY, with 3). Heads accessible from the Baffle-former bolts Management (IE and ISR) subsequent examination on a ten- core side. UT accessibility may (Note 6) year interval. be affected by complexity of head and locking device designs.

Page 3 of 16

MRP-227-A Primary Inspection Components Item Expansion Link Examination Applicability Effect (Mechanism) Examination Coverage (Note 1) MethodlFrequency (Note 1)

Baffle-Former All plants Distortion (Void Swelling), None Visual ((VT-3) examination to check Core side surface as indicated.

Assembly or Cracking (IASCC) that for evidence of distortion, with Assembly results in: baseline examination between 20 (includes: Baffle plates, *Abnormal and 40 EFPY and subsequent baffle edge bolts and interaction with examinations on a ten-year interval.

indirect effects of void fuel assemblies swelling in former *Gaps along high plates) fluence baffle joint

-Vertical displacement of baffle plates near high fluence joint Broken or damaged edge bolt locking systems along high fluence baffle joint Alignment and All plants with 304 Distortion (Loss of load) None Direct measurement of spring height Measurements should be taken Interfacing stainless steel hold within three cycles of the beginning of at several points around the components down springs Note: This mechanism the license renewal period. If the first circumference of the spring, Internals hold down was not strictly identified set of measurements is not sufficient with a statistically adequate spring in the original 'list of age- to determine life, spring height number of measurements at related degradation measurements must be taken during each point to minimize mechanisms' [7]. the next two outages, in order to uncertainty.

extrapolate the expected spring height to 60 years.

Page 4 of 16

MRP-227-A Primary Inspection Components Expansion Link Examination Item Applicability Effect (Mechanism) Examination Coverage (Note 1) MethodlFrequency (Note 1)

Thermal Shield All plants with Cracking (Fatigue) or Loss None Visual (VT-3) no later than 2 refueling 100% of thermal shield Assembly thermal shields of Material (Wear) that outages from the beginning of the flexures.

Thermal Shield results in thermal shield license renewal period. Subsequent Assembly flexures excessive wear, examinations on a ten-year interval.

fracture, or complete separation.

Notes to Table 4-3:

1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3.
2. A minimum of 75% of the total identified sample population must be examined.
3. A minimum of 75% of the total population (examined + unexamined), including coverage consistent with the Expansion criteria in Table 5-3, 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 Table 5-3, must be examined from either the inner or outer diameter for inspection credit.
5. The lower core barrel flange weld may be alternatively designated as the core barrel-to-support plate weld in some Westinghouse plant designs.
6. Void swelling effects on this component is managed through management of void swelling on the entire baffle-former assembly.

MRP-227-A Primary Inspection Components Expansion Link Examination Item Applicability Effect (Mechanism) Examination Coverage (Note 1) MethodlFrequency (Note 1)

Upper lnternals All plants Cracking CRGT lower flange weld Enhanced visual (EVT-1) 100% of accessible surfaces Assembly (Fatigue, Wear) examination. (Note 2).

Upper core plate Re-inspection every 10 years following initial inspection.

Lower lnternals All plants Cracking CRGT lower flange weld Enhanced visual (EVT-1) 100% of accessible surfaces Assembly Aging management (TE examination. (Note 2).

Lower support forging or in Casting) Re-inspection every 10 years castings following initial inspection.

Core Barrel Assembly All plants Cracking Baffle-former bolts Volumetric (UT) examination. 100% of accessible bolts.

Barrel-former bolts (IASCC, Fatigue) Re-inspection every 10 years Accessibility may be limited by Aging Management (IE. following initial inspection. presence of thermal shields or Void Swelling and ISR) neutron pads (Note 2).

Lower Support All plants Cracking Baffle-former bolts Volumetric (UT) examination. 100% of accessible bolts or as Assembly (IASCC, Fatigue) Re-inspection every 10 years supported by plant-specific Lower support column Aging Management (IE following initial inspection. justification (Note 2).

bolts and ISR)

MRP-227-A Primary Inspection Components Item Expansion Link Examination Applicability Effect (Mechanism) Examination Coverage (Note 1) MethodlFrequency (Note 1)

Core Barrel Assembly All plants Cracking (SCC, Fatigue) Upper core barrel flange Enhanced visual (Em-1) 100% of one side of the Core barrel outlet nozzle Aging Management (IE of weld examination. accessible surfaces of the welds lower sections) Re-inspection every 10 years selected weld and adjacent following initial inspection. base metal (Note 2).

Core Barrel Assembly All plants Cracking (SCC, IASCC) Upper and lower core Enhanced visual (EVT-1) 100% of one side of the Upper and lower core Aging Management (IE) barrel cylinder girth examination. accessible surfaces of the barrel cylinder axial welds Re-inspection every 10 years selected weld and adjacent welds following initial inspection. base metal (Note 2).

Lower Support All plants Cracking (IASCC) Upper core barrel flange Enhanced visual (EVT-1) 100% of accessible surfaces Assembly Aging Management (IE) weld examination. (Note 2).

Lower support column Re-inspection every 10 years bodes (non cast) following initial inspection.

Lower Support All plants Cracking (IASCC) Control rod guide tube Visual (Em-1) examination. 100% of accessible support Assembly including the detection of (CRGT) lower flanges Re-inspection every 10 years columns (Note 2).

Lower support column fractured support following initial inspection.

bodes (cast) columns Aging Management (IE)

Page 7 of 16

MRP-227-A Primary Inspection Components Expansion Link Examination Item Applicability Effect (Mechanism) Examination Coverage (Note 1) MethodlFrequency (Note 1)

Bottom Mounted All plants Cracking (Fatigue) Control rod guide tube Visual (VT-3) examination of BMI 100% of BMI column bodies for Instrumentation System including the detection of (CRGT) lower flanges column bodies as indicated by which difficulty is detected Bottom-mounted completely fractured difficulty of insertion/withdrawal of during flux thimble instrumentation (BMI) column flux thimbles. insertionlwithdrawal.

column bodies Aging Management Re-inspection every 10 years (IE). following initial inspection.

Flux thimble insertion/withdrawal to be monitored at each inspection interval.

Notes to Table 4-6:

1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3.
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).

MRP-227-A Primary Inspection Components Expansion Link Examination Item Applicability Effect (Mechanism) Examination Coverage (Note 1) MethodlFrequency (Note 1)

Core Barrel Assembly All plants Loss of material (Wear) ASME Code Section XI Visual (VT-3) examination to All accessible surfaces at Core barrel flange determine general condition for specified frequency excessive wear.

Upper lnternals All plants Cracking (SCC, Fatigue) ASME Code Section XI Visual (VT-3) examination. All accessible surfaces at Assembly specified frequency Upper support ring or skirt Lower lnternals All plants Cracking (IASCC, ASME Code Section XI Visual (VT-3) examination of the All accessible surfaces at Assembly Fatigue) lower core plates to detect evidence specified frequency Lower core plate Aging Management (IE) of distortion andlor loss of bolt XL lower core plate (Note integrity.

1)

Lower lnternals All plants Loss of material (Wear) ASME Code Section XI Visual (VT-3) examination All accessible surfaces at Assembly specified frequency Lower core plate XL lower core plate (Note 1)

Bottom Mounted All plants Loss of material (Wear) NUREG-1801 Surface (ET) examination. Eddy current surface Instrumentation System Rev. 1 examination as defined in plant Flux thimble tubes response to IEB 88-09.

Alignment and All plants Loss of material (Wear) ASME Code Section XI Visual (VT-3) examination All accessible surfaces at Interfacing specified frequency Components (Note 2)

Clevis insert bolts Alignment and All plants Loss of material (Wear) ASME Code Section XI Visual (VT-3) examination All accessible surfaces at Interfacing specified frequency Components Upper core plate alignment pins Notes to Table 4-9:

1. XL = "Extra Long" referring to Westinghouse plants with 14-foot cores.
2. Bolt was screened in because of stress relaxation and associated cracking; however, wear of the clevislinsert is the issue

MRP-227-A Primary Inspection Components Examination Acceptance Additional Examination Item Applicability Expansion Link(s) Expansion Criteria Criteria (Note 1) Acceptance Criteria Control Rod Guide Tube All plants Visual (VT-3) examination None N/A NIA Assembly Guide plates (cards) The specific relevant condition is wear that could lead to loss of control and alignment and impede control assembly insertion.

Control Rod Guide Tube All plants Enhanced visual (EVT-1) a. Bottom-mounted a. Confirmation of surface- a. For BMI column bodies, the Assembly examination instrumentation (BMI) breaking indications in two specific relevant condition for Lower flange welds column bodies or more CRGT lower flange the VT-3 examination is The specific relevant welds, combined with flux completely fractured column condition is a detectable b. Lower support thimble insertionlwithdrawal bodies.

crack-like surface indication column bodies (cast), difficulty, shall require visual upper core plate and (VT-3) examination of BMI b. For cast lower support lower support forging or column bodies by the column bodies, upper core plate casting completion of the next and lower support refueling outage. forginglcastings, the specific relevant condition is a

b. Confirmation of surface- detectable crack-like surface breaking indications in two indication.

or more CRGT lower flange welds shall require EVT-1 examination of cast lower support column bodies, upper core plate and lower support forginglcastings within three fuel cycles following the initial observation.

Page 10 of 16

MRP-227-A Primary Inspection Components Examination Acceptance Additional Examination Item Applicability Expansion Link(s) Expansion Criteria Criteria (Note 1) Acceptance Criteria Core Barrel Assembly All plants Periodic enhanced visual a. Core barrel outlet a. The confirmed detection a and b. The specific relevant Upper core barrel flange weld (EVT-1) examination. nozzle welds and sizing of a surface- condition for the expansion core breaking indication with a barrel outlet nozzle weld and The specific relevant condition b. Lower support length greater than two lower support column body is a detectable crack-like column bodies (non inches in the upper core examination is a detectable surface indication. cast) barrel flange weld shall crack-like surface indication.

require that the EVT-1 examination be expanded to include the core barrel outlet nozzle welds by the completion of the next refueling outage.

b. If extensive cracking in the core barrel outlet nozzle welds is detected, EVT-1 examination shall be expanded to include the upper six inches of the accessible surfaces of the non-cast lower support column bodies within three fuel cycles following the initial observation.

MRP-227-A Primary Inspection Components Examination Acceptance Additional Examination Applicability Expansion Link(s) Expansion Criteria Criteria (Note 1) Acceptance Criteria All plants Periodic enhanced visual None None None Lower core barrel flange weld (EVT-1) examination (Note 2)

The specific relevant condition is a detectable crack-like All plants Periodic enhanced visual Upper core barrel The confirmed detection The specific relevant condition Upper core barrel cylinder girth (EVT-1) examination cylinder axial welds and sizing of a surface- for the expansion upper core welds breaking indication with a barrel cylinder axial weld The specific relevant condition length greater than two examination is a detectable is a detectable crack-like inches in the upper core crack-like surface indication.

surface indication. barrel cylinder girth welds shall require that the EVT-1 examination be expanded to include the upper core barrel cylinder axial welds by the completion of the next refueling outage.

Page 12 of 16

MRP-227-A Primary Inspection Components Examination Acceptance Additional Examination Item Applicability Expansion Link(s) Expansion Criteria Criteria (Note I) Acceptance Criteria Core Barrel Assembly All plants Periodic enhanced visual Lower core barrel The confirmed detection The specific relevant condition Lower core barrel cylinder girth (EVT-1) examination cylinder axial welds and sizing of a surface- for the expansion lower core welds breaking indicationwith a barrel cylinder axial weld The specific relevant condition length greater than two examination is a detectable is a detectable crack-like inches in the lower core crack-like surface indication.

surface indication. barrel cylinder girth welds shall require that the EVT-1 examination be expanded to include the lower core barrel cylinder axial welds by the completion of the next refueling outage.

Baffle-Former Assembly All plants with Visual (VT-3) examination. None N/A N/A Baffle-edge bolts baffle-edge bolts The specific relevant conditions are missing or broken locking devices.

failed or missing bolts, and protrusion of bolt heads.

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MRP-227-A Primary Inspection Components Examination Acceptance Additional Examination Item Applicability Expansion Link(s) Expansion Criteria Criteria (Note 1) Acceptance Criteria Baffle-Former Assembly All plants Volumetric (UT) examination. a. Lower support a. Confirmation that more a and b. The examination Baffle-former bolts column bolts than 5 % of the baffle- acceptance criteria for the UT of The examination acceptance former bolts actually the lower support column bolts criteria for the UT of the b. Barrel-former bolts examined on the four baffle and the barrel-former bolts shall baffle-former bolts shall be plates at the largest be established as part of the established as part of the distance from the core examination technical examination technical (presumed to be the lowest justification.

justification. dose locations) contain unacceptable indications shall require UT examination of the lower support column bolts within the next three fuel cycles.

b. Confirmation that more than 5% of the lower support column bolts actually examined contain unacceptable indications shall require UT examination of the barrel-former bolts.

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MRP-227-APrimary Inspection Components Examination Acceptance Additional Examination Item Applicability Expansion Link@) Expansion Criteria Criteria (Note I) Acceptance Criteria Baffle-Former Assembly All plants Visual (VT-3) examination. None NIA NIA Assembly The specific relevant conditions are evidence of abnormal interaction with fuel assemblies, gaps along high fluence shroud plate joints, vertical displacement of shroud plates near high fluence joints, and broken or damaged edge bolt locking systems along high f l uence baffle plate joints.

Alignment and Interfacing All plants with 304 Direct physical measurement None NIA NIA Components stainless steel hold of spring height.

lnternals hold down spring down springs The examination acceptance criterion for this measurement is that the remaining compressible height of the spring shall provide hold-down forces within the plant-specific design tolerance.

Page 15 of 16

MRP-227-A Primary Inspection Components Examination Acceptance Additional Examination Item Applicability Expansion Link@) Expansion Criteria Criteria (Note 1) Acceptance Criteria Thermal Shield Assembly All plants with Visual (VT-3) examination. None N/A N/A Thermal shield fixtures thermal shields The specific relevant conditions for thermal shield flexures are excessive wear, fracture, or complete separation.

Notes to Table 5-3:

1. The examination acceptance criterion for visual examination is the absence of the specified relevant condition(s).
2. The lower core barrel flange weld may alternatively be designated as the core barrel-to-support plate weld in some Westinghouse plant designs.

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