ML15223A624
| ML15223A624 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/12/2014 |
| From: | NRC/OGC |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| RAS 28143, ASLBP 07-858-03-LR-BD01, 50-247-LR, 50-286-LR | |
| Download: ML15223A624 (37) | |
Text
NRC00208D Submitted: August 10, 2015 H.B. Robinson Nuclear Plant Expansion Components Rqu Examination Coverage Examination Item. Examination Method Findings (Note 1)
Coverage Achieved Upper Internals Enhanced visual 100% of accessible N/A N/A Assembly examination (EVT-1) surfaces (Note 2).
Upper core plate Comments:
None Lower Internals Enhanced visual 100% of accessible N/A N/A Assembly examination (EVT-1) surfaces (Note 2).
Lower support forging or castings See Figure 4-33 of MRP-227-A.
72
H.B. Robinson Nuclear Plant S1)
Comments:
None Core Barrel Volumetric 100% of accessible bolts. N/A N/A Assembly examination (UT) Accessibility may be Barrel-former bolts limited by presence of thermal shields or neutron pads (Note 2).
See Figure 4-23 of MRP-227-A.
Comments:
None Lower Support Volumetric 100% of accessible bolts N/A N/A Assembly examination (UT) or as supported by plant-Lower support specific justification (Note column bolts 2).
See Figures 4-32 and 4-33 of MRP-227-A.
73
H.B. Robinson Nuclear Plant Item Examination Method Required Examination Coverag Exaination
.... Coverage Achieved Findings (Note 1)
Comments:
None Core Barrel Enhanced visual 100% of one side of the N/A N/A Assembly examination (EVT-1) accessible surfaces of the Core barrel outlet selected weld and nozzle welds adjacent base metal (Note 2).
See Figure 4-22 of MRP-227-A.
Comments:
None Core Barrel Enhanced visual 100% of one side of the N/A N/A Assembly examination (EVT-1) accessible surfaces of the Upper and lower core selected weld and barrel cylinder axial adjacent base metal (Note welds 2).
See Figure 4-22 of MRP-227-A.
74
H.B. Robinson Nuclear Plant Comments:
J Coerag AchevedFindngs(Note 1)
None Lower Support Enhanced visual 100% of accessible N/A NIA Assembly examination (EVT-1) surfaces (Note 2).
Lower support column bodies See Figure 4-34 of MRP-(non cast) 227-A.
Comments:
None Lower Support Enhanced visual 100% of accessible N/A N/A Assembly examination (EVT-1) support columns (Note 2).
Lower support column bodies See Figure 4-34 of MRP-(cast) 227-A.
Comments:
None V
75
H.B. Robinson Nuclear Plant Me Required Examination Coverage Examination Iination
___..... __....Coverage Achieved Findings (Note 1)
Bottom Mounted Visual examination 100% of BMI column N/A N/A Instrumentation (VT-3) bodies for which difficulty System is detected during flux Bottom-mounted thimble instrumentation (BMI) insertion/withdrawal.
column bodies See Figure 4-35 of MRP-227-A.
Comments:
None Notes to Westinghouse Expansion Component Table:
- 1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3 of MRP-227-A.
- 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).
76
H.B. Robinson Nuclear Plant Existing Programs Components Inspected in R027 (2012). Completed in conjunction with VT-3 Examination of Core Barrel Flange Flow Nozzles 100% None Comments:
Completed in R027 (2012). Examined the accessible areas of the Upper Support Assembly including CRD shafts for damage, wear, and abnormal conditions 77
H.B. Robinson Nuclear Plant 78
H.B. Robinson Nuclear Plant N/A
- ,UIIIIII IIILb.
None uomments:
None 79
H.B. Robinson Nuclear Plant vommens:;
Completed in R027 (2012). Examined the accessible areas of the Upper Core Plate alignment Keyways with Clevis at 0, 90,180 and 270 azimuths for damage and abnormal conditions Notes to Westinghouse Existing Programs Components Table:
- 1. XL = "Extra Long" referring to Westinghouse plants with 14-foot cores.
80
Tables for Reporting MRP-227-A Inspection Results for Westinghouse Plants Plant Name:_Shearon Harris Utility: _Duke Energy_
Date of Exams:_See Comments for each component__ Plant Age: -See Comments (years) / _See CommentsEFPY Primary Components comments:
81
Shearon Harris uomments:
N/A IUMnMnILS; 82
Shearon Harris L~ommenw:
N/A N/A Comments:
83
Shearon Harris N/A N/A uomments:
84
Shearon Harris uomments:
N/A N/A 85
Shearon Harris Notes to Westinghouse Primary Components Table:
- 1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3 of MRP-227-A.
- 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 of MRP-227-A, 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 of MRP-227-A, 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.
86
Shearon Harris Expansion Components upper internals 100% ot accessible Assembly examination (EVT-1) surfaces (Note 2).
Upper core plate Comments:
Lower Internals Enhanced visual 100% of accessible NIA N/A Assembly examination (EVT-1) surfaces (Note 2).
Lower support forging or castings See Figure 4-33 of MRP-227-A.
Comments:
87
Shearon Harris Required Examination Coverage Examination Item .
Examination Coverage Achieved Findings (Note 1)
Core Barrel Volumetric 100% of accessible bolts. N/A N/A Assembly examination (UT) Accessibility may be Barrel-former bolts limited by presence of thermal shields or neutron pads (Note 2).
See Figure 4-23 of MRP-227-A.
Comments:
Lower Support Volumetric 100% of accessible bolts NIA N/A Assembly examination (UT) or as supported by plant-Lower support specific justification (Note column bolts 2).
See Figures 4-32 and 4-33 of MRP-227-A.
Comments:
88
Shearon Harris Examination Core Barrel Enhanced visual 100% of one side of the N/A N/A Assembly examination (EVT-1) accessible surfaces of the Core barrel outlet selected weld and nozzle welds adjacent base metal (Note 2).
See Figure 4-22 of MRP-227-A.
Comments:
Core Barrel Enhanced visual 100% of one side of the N/A N/A Assembly examination (EVT-1) accessible surfaces of the Upper and lower core selected weld and barrel cylinder axial adjacent base metal (Note welds 2).
See Figure 4-22 of MRP-227-A.
Comments:
V 89
Shearon Harris It Examination Method Required Examination Coverage Examination
, eEmaoMh , Coverg Achieved Findings (Note 1)
Lower Support Enhanced visual 100% of accessible N/A N/A Assembly examination (EVT-1) surfaces (Note 2).
Lower support column bodies See Figure 4-34 of MRP-(non cast) 227-A.
Comments:
Lower Support Enhanced visual 100% of accessible N/A N/A Assembly examination (EVT-1) support columns (Note 2).
Lower support column bodies See Figure 4-34 of MRP-(cast) 227-A.
Comments:
90
Shearon Harris CoveageAchivedFindings (Note 1)
Bottom Mounted Visual examination 100% of BMI column N/A N/A Instrumentation (VT-3) bodies for which difficulty System is detected during flux Bottom-mounted thimble instrumentation (BMI) insertion/withdrawal.
column bodies See Figure 4-35 of MRP-227-A.
Comments:
Notes to Westinghouse Expansion Component Table:
- 1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3 of MRP-227-A.
- 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).
91
Shearon Harris Existing Programs Components Comments:
Date of exams: May 2012 / RFO-17 Plant age: 25.5 years / 21.7 EFPY HNP RMS Record No. 5199601 To the maximum extent practical No loss of material and within the limitation of component geometry.
%,VlIII I I I L'J.
Date of exams: May 2012 / RFO-17 Plant age: 25.5 years / 21.7 EFPY HNP RMS Record No. 5199601 To the maximum extent practical No cracking and within the limitation of component geometry.
%,,UII II I I=1 I LO.
Date of exams: May 2012 / RFO-17 Plant age: 25.5 years / 21.7 EFPY HNP RMS Record No. 5199601 92
Shearon Harris
%,OUI1111*11V LM.
Date of exams: May 2012 / RFO-17 Plant age: 25.5 years / 21.7 EFPY HNP RMS Record No. 5199601 100%, with the exception of Wear, when observed, was within Thimble No. 36 (obstruction was expectations for all thimbles except encountered, and Thimble No 36 for Thimble No. 13, in which wear was removed from service) rates were greater than predicted.
Wear predictions were determined for all thimbles except for Thimble No. 36. With the exception of Thimble No. 36, all thimbles were found to be satisfactory for continued service until the next scheduled inspection (RFO-19).
Comments:
Date of exams: October 2010 I RFO-16 Plant age: 24 years / 20.3 EFPY Thimble Nos. 1, 7, 11, 28, 29, 39, 40,41, 42, 44,48, and 50 were replaced during RFO-16.
HNP RMS Record No. 4583077 Procedure No. EPT-114 93
Shearon Harris tomments:
Date of exams: May 2012 / RFO-17 Plant age: 25.5 years / 21.7 EFPY HNP RMS Record No. 5199601 To the maximum extent practical No loss of material and within the limitation of component geometry.
uomments:
Date of exams: May 2012 / RFO-17 Plant age: 25.5 years / 21.7 EFPY HNP RMS Record No. 5199601 Notes to Westinghouse Existing Programs Components Table:
- 1. XL = "Extra Long" referring to Westinghouse plants with 14-foot cores.
94
Tables for Reporting MRP-227-A Inspection Results for Westinghouse Plants Plant Name: Surry Unit 1 Utility: Dominion Generation Date of Exams: October 27 - November 5th 2013 Plant Age: 41 (May 26 1972) years) / 30.98 EFPY Primary Components This inspection was completed during 1R24 (Spring 2012).
95
Surrv Unit 1 All accessible welds were examined, and the MRP-227-A inspection requirement was satisfied. No relevant indications were noted.
These exams were completed during 1R24 (Spring 2012) and the Inspection Results report was submitted 2/5/2013.
Lo.,omments:
This inspection was completed during IR24 (Spring 2012).
100% of the accessible The EVT - 1 examination of the one weld received an EVT - 1 upper core barrel weld was SAT; the examination, weld was examined from the ID surface as required per the MRP guidance. There were no indications.
The exam fulfilled the requirements of MRP-227-A. These exams were completed during 1R24 (Spring 2012) and the Inspection Results report was submitted 2/5/2013.
Comments:
This inspection was completed during 1R24 (Spring 2012). 100% of this weld was inspected to the EVT - 1 requirement presented in MRP - 227 - A. No issues were noted for this visual examination.
96
Surry Unit 1 I I M F-V I - I CAMI:IIIIIIIdLIUII U1 LLIV UIIt:
lower core barrel weld was SAT. The weld was inspected from the exterior of the core barrel between the core barrel and the thermal shield.
Comments:
This inspection was completed during I R25 (Fall 2013). 100% of the upper girth weld (UGW) was inspected from inside the vessel to the EVT - I requirement presented in MRP - 227 - A. No issues were noted for this visual examination. 70.4% of the lower girth weld (LGW) was inspected from inside the vessel to the EVT - I requirement presented in MRP - 227 - A. No issues were noted for this visual examination. The lower girth weld coverage was limited by obstructions between the core barrel and the thermal shield. Other limitations occurred due to the narrow gap between the core barrel and reactor cavity wall. Within Table 4-3 of MRP-227-A, the UGW and the LGW are identified as having the same effect - cracking due to stress corrosion cracking (SCC), irradiated - assisted stress corrosion cracking (IASCC) and fatigue. A minimum of 75% of the total weld length must be examined in accordance with Note 4 of the Table 4 - 3. The total combined length for the UGW and the LGW is 866.696 inches. A total of 725.86 inches was examined which results in 85.0% coverage. The requirements of MRP-227-A, Table 4-3, Note 4 have been met.
82% of the LFW was The EVT - 1 examination of the one examined during 1R25. lower core barrel weld was SAT. The See comments. weld was inspected from the exterior.
97
Surrv Unit 1 4,
Comments: This Lower Flange Weld was inspected from the exterior of the core barrel; therefore, the weld inspection length is determined from the outer core barrel diameter. Cleaning of the weld was not required. The total weld length is 433.348 inches computed from the calculated outer diameter of 137.939 inches. A total of 355.19 inches were examined resulting in 82%
coverage. Coverage limitations occurred due to the narrow gap between the core barrel and reactor cavity wall. No issues were identified.
m During 1R23 (Fall 2010), One baffle edge bolt was found to 936 accessible baffle - have a missing weld on one side of its edge bolts received VT - lock bar. This was attributed to a 3 inspection. fabrication error, not aging effects, and is acceptable for continued safe operation. Re-inspected during 1R25.
Comments: These exams were completed before EPRI had prepared a MRP - 227 reporting template. EPRI was notified of these data through a detailed narrative summary submitted to the MRP.
During 1R25 (Fall 2013), the one baffle-edge bolt with the known indication was visually re - inspected per VT-3 requirements. The visual examination was satisfactory; no changes in the condition were noted.
During 1R23 (Fall 2010), The most significant examination 1088 baffle - to - former result was detection of a likely flaw in bolts received UT one bolt, identified as "Cl 13". The examination and the depth of the flaw in C013 is not ocking bars received VT quantified; however, it is located at
- 3 examinations. the head to shank region of the bolt.
Also, some channels of the UT signals showed a significant "back wall" reflection from the end of the bolt, so the bolt is not completely severed. The lock bar for this bolt has no relevant conditions and is considered capable of performing its retention function.
98
Surry Unit 1 Comments:
These were completed during 1R23 (Fall 2010).
These exams were completed before EPRI had prepared a MRP - 227 reporting template. EPRI was notified of these data through a detailed narrative summary submitted to the MRP.
Visual re - examinations were completed during 1R25 to confirm no changes in conditions; visual examination was confirmation that lock - bar and welds remained intact.
The inspection for gaps Examinations were SAT - no relevant and distortion due to void conditions were noted.
swelling has not been done yet. The edge bolt inspection is reported above.
Comments:
During 1 R25 (Fall 2013), all of the baffle seams and plate inside the Unit I Core Barrel were inspected, and the inspections met the VT - 3 requirements. All VT - 3 inspections of the Baffle - Former Assembly Baffle Plates and Seams were Satisfactory.
During 1R25 (Fall 2013), the four baffle-former bolts with the known indications were visually re - inspected per VT-3 requirements to ensure all locking bars and locking bar welds were intact. The visual examinations were satisfactory; no changes in the conditions were noted.
99
Surry Unit 1 Comments: Because Unit I has an austenitic (304 - SS) stainless steel hold down spring, measurements of its relaxation was required per the MRP-227-A guidance. Per analysis, considering Surry Unit I as-built dimensions and the required hold down force for design conditions, the minimum acceptable height for assuring a minimum for 60 year service life was computed.
During 1R24 (Spring 2012), spring height measurements were taken at eight locations (every 450) with three individual measurements taken at each location.
The estimated average spring height was 3.6312+/-0.0002 inches. This result is greater than the minimum requirement; therefore, the final result is acceptable. This result confirms adequate hold down capability through at least 60 total years of reactor operation, and no further measurements are required.
Examination completed Examinations were SAT - no relevant during 1R25 (Fall 2013) - conditions were noted.
examination satisfactory.
comments:
The Thermal Shield Flexures were examined for evidence of cracking (fatigue) or loss of material (wear) which could result in thermal shield flexure excessive wear, fracture, or complete thermal shield flexure separation from the core barrel. The VT - 3 examinations of the thermal shield flexures are summarized in Table 2, and all visual exams were satisfactory.
100
Surry Unit 1 Notes to Westinghouse Primary Components Table:
- 1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3 of MRP-227-A.
- 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 of MRP-227-A, 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 of MRP-227-A, 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.
101
Surry Unit 1 Expansion Components IeExmntoMehd Required Examination Coverage Examination ite Eamnaio t~dCoverage Achieved Findings (Note 1)
Upper Internals Enhanced visual 100% of accessible N/A N/A Assembly examination (EVT-1) surfaces (Note 2).
Upper core plate Comments:
Lower Internals Enhanced visual 100% of accessible N/A N/A Assembly examination (EVT-1) surfaces (Note 2).
Lower support forging or castings See Figure 4-33 of MRP-227-A.
Comments:
Core Barrel Volumetric 100% of accessible bolts. N/A N/A Assembly examination (UT) Accessibility may be Barrel-former bolts limited by presence of thermal shields or neutron pads (Note 2).
See Figure 4-23 of MRP-227-A.
102
Surry Unit 1 Comments:
Lower Support Volumetric 100% of accessible bolts N/A N/A Assembly examination (UT) or as supported by plant-Lower support specific justification (Note column bolts 2).
See Figures 4-32 and 4-33 of MRP-227-A.
Comments:
Core Barrel Enhanced visual 100% of one side of the N/A N/A Assembly examination (EVT-1) accessible surfaces of the Core barrel outlet selected weld and nozzle welds adjacent base metal (Note 2).
See Figure 4-22 of MRP-227-A.
Comments:
103
Surry Unit 1 Coverage Eminaton Examination Method Required Examination Exam_____o__Metho Coverage Achieved Findings (Note 1)
Core Barrel Enhanced visual 100% of one side of the N/A N/A Assembly examination (EVT-1) accessible surfaces of the Upper and lower core selected weld and barrel cylinder axial adjacent base metal (Note welds 2).
See Figure 4-22 of MRP-227-A.
Comments:
Lower Support Enhanced visual 100% of accessible N/A N/A Assembly examination (EVT-1) surfaces (Note 2).
Lower support column bodies See Figure 4-34 of MRP-(non cast) 227-A.
Comments:
Lower Support Enhanced visual 100% of accessible N/A N/A Assembly examination (EVT-1) support columns (Note 2).
Lower support column bodies See Figure 4-34 of MRP-(cast) 227-A.
104
Surry Unit 1 Findings (Note 1)
Comments:
Bottom Mounted Visual examination 100% of BMI column N/A N/A Instrumentation (VT-3) bodies for which difficulty System is detected during flux Bottom-mounted thimble instrumentation (BMI) insertion/withdrawal.
column bodies See Figure 4-35 of MRP-227-A.
Comments:
Notes to Westinghouse Expansion Component Table:
- 1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3 of MRP-227-A.
- 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).
105
Surry Unit 1 Existing Programs Components iuommenis:
Examination completed during No findings - examination 1R25 - Fall of 2013. No issues satisfactory.
were noted. 100% coverage.
Lcomments:
Examination completed during No findings - examination 1R25 - Fall of 2013. No issues satisfactory.
were noted. 100% coverage.
L.ommenls:
106
Surry Unit 1
'ommenis:
1R24 (May 2012) 49 of 50 flux No issues were noted.
Insbmenttio exainaion ED eamiatio as thimble tubes for SPS Unit 1. 1 systm deinedin pant flux thimble tube is capped -
Fluxthibletubs res~mse o IB W removed from service (tube F-4).
Comments:
The following flux thimble tubes were replaced prior to the May 2012 inspection: B10, D12, E5, F2, HI, H13, J3, J12, L4, L5, L14, N12, &
R8.
Flux Thimble tube B7 had 43% OUTER WALL DEGRADATION.
Flux Thimble tube Ell had 10% INNER WALL DEGRADATION.
No inspection during 1R25 (Fall 2013).
Examination completed during No findings - examination 1R25 - Fall of 2013. No issues satisfactory.
Compnens frquecy.were noted. 100% coverage 107
Surry Unit 1 A
Notes to Westinghouse Existing Programs Components Table:
- 1. XL = "Extra Long" referring to Westinghouse plants with 14-foot cores.
108