ML15107A017
| ML15107A017 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/14/2015 |
| From: | Weber T Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-007032-TNW/MDD/CJS | |
| Download: ML15107A017 (29) | |
Text
Technical Specification 5.6.8 0aps Palo Verde Nuclear Generating Station 5801 S. Wintersburg Road Tonopah, AZ 85354 102-007032-TNW/MDD/CJS April 14, 2015 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Unit 1 Docket No. STN 50-528 License No. NPF-41 Steam Generator Tube Inspection Report Attached please find the PVNGS Unit 1 Steam Generator Tube Inspection Report prepared and submitted by Arizona Public Service Company (APS) pursuant to Technical Specification (TS)
Reporting Requirement 5.6.8. This report describes steam generator tube inspection and plugging results from the Unit 1 eighteenth refueling outage.
By copy of this letter, this submittal is being provided to the NRC Region IV Administrator and the PVNGS Senior Resident Inspector. No commitments are being made to the NRC by this letter.
Should you have questions regarding this submittal, please contact Michael D. Dilorenzo, Licensing Section Leader, at (623) 393-3495.
Sincerely, 62tYbý A//
'Y/"
tý-
Thomas N. Weber Nuclear Regulatory Affairs Department Leader TNW/MDD/CJS/hsc Attachment cc:
(with attachment)
M. L. Dapas M. M. Watford C. A. Peabody NRC Region IV Regional Administrator NRC NRR Project Manager for PVNGS NRC Senior Resident Inspector for PVNGS Ao 0-0 A member of the STARS (strategic Teaming and Resource Sharing) Alliance Callaway
- Diablo Canyon
- Palo Verde 0 Wolf Creek
Attachment Unit 1 -
1 8 th Refueling Outage Steam Generator Tube Inspection Report
Palo Verde Nulear Generaing Slabon UNIT1 UIR18 ARIZONA PUBLIC SERVICE P. 0. BOX 52034 PHOENIX, AZ 85072 Prepared by: Douglas B Hansen Leaverton.
Reviewed by:
Warren QV59783)
Radspinner, Mark o Approved by:
AQ77677218) l'"
ý-"
L Date: 11-3-14 Date:
Report Date:
778)
Commercial Service Date: 1-28-86
Table of Contents 1.0
SUMMARY
2.0 SCOPE OF EXAMINATIONS PERFORMED 3.0 ACTIVE DEGRADATION MECHANISMS 4.0 NDE TECHNIQUES UTILIZED 5.0 INDICATION
SUMMARY
6.0 TUBES PLUGGED 7.0 PLUG HISTORY 8.0 CONDITION MONITORING APPENDIX A - TUBE SUPPORT DIAGRAM, LEGEND, and ANALYSIS CODES APPENDIX B - SG II
SUMMARY
DATA SHEETS APPENDIX C - SG 12
SUMMARY
DATA SHEETS APPENDIX D - PLI and PLP DATA SHEETS APPENDIX E - PLUG MAPS APPENDIX F - FORM NIS - I
UNIT 1 STEAM GENERATOR EDDY CURRENT Ul R18 Refueling Outage 1.0 Summary This report is intended to satisfy the requirements of PVNGS Technical Specifications 5.6.8 for the submittal of a Steam Generator Tube Inspection Report. The steam generator (SG) eddy current examination for the 18th refueling outage in Unit 1 (U I Ri 8) was conducted during October 2014.
Mode 4 entry of Unit I was entered on November 7, 2014. The initial examination plan for both steam generators is listed in Table 1. This table summarizes the examinations performed for each of the various categories, examination types, extents, and the number of tubes or tube locations completed. This was the fifth examination performed in Unit I following steam generator replacement in UIRI2. This examination is not considered a 100% full length tubing inspection.
The examinations resulted in a total of 0 tubes being plugged in SG 11, and 0 tubes being plugged in SG 12. A description of the previous plugging history is noted in Table 2, and Appendix E provides a map of all tubes plugged.
2.0 Scope of Examinations Performed The original examination plan was developed based on the "PVNGS Steam Generator Degradation Assessment" developed per PVNGS Procedure 81DP-9RCO1 as required by NEI 97-06. In addition, possible damage mechanisms were reviewed along with the specific requirements set forth in Procedure 73TI-9RCO 1 and the PVNGS Technical Specifications. The plan was finalized to include bobbin examinations of the peripheral tubes.
This original plan, along with the examinations performed as a result of bobbin indications noted, is summarized in Table I of this report.
3.0 Active Degradation Mechanisms The only degradation noted during the examinations was determined to be wear. Section 8.0 contains further discussions relating to this mechanism. Table 2 summarizes the results into categories and sections B and C itemizes all indications reported.
4.0 NDE Techniques Utilized The following table documents the site qualified techniques utilized during this outage:
- ECs, 7UUJJ'. 1 Rev. 13 4-2010 31 11 Z QUALIFIED Wa LosPat27091.2 SITE NA Y
N Volt DIFF No Rev. 0*
QUALIFIED v1 a8-2007 0
Rev I added cautionary note, no chang:e to site qlualification.
The eddy current examinations were performed by Westinghouse Electric Company using the Core Star OMNI 200 eddy current instrument. Westinghouse Anser software was utilized to acquire the data along with the Pegasys robotic manipulator. This robot was configured with a dual guide tube in each of the hot and cold legs.
The tubing was examined with Zetec manufactured bobbin coil probes and Zetec rotating coil (RC) style probes. Probe diameters were 0.590" to 0.610". Plus Point RC probes were used for the characterization of non-quantifiable or distorted bobbin indications.
Fiber optic cable was used from containment to the data acquisition room located at the PVNGS North Annex. Primary and secondary analysis was all performed on site. The Primary and Secondary Resolution Analysts, Independent Review Analysts, and data management were also located at PVNGS in the North Annex. Westinghouse provided the data acquisition and primary data analysis. Areva provided the secondary data analysis.
Each individual from Westinghouse and Areva who performed data analysis was required to complete and pass a PVNGS site specific Eddy Current Data Analysis Course as well as an associated performance and written examination. All individuals performing data analysis were also required to have Qualified Data Analyst (QDA) certification.
5.0 Indication Summary A detailed listing of the location and measured sizes of indications recorded is included in Appendix B and C. A summary of these indication results is located in Table 2. In addition, Appendix A contains a reference drawing of steam generator support locations and report legend.
There were no indications that were identified as linear during this outage.
6.0 Tubes Plugged A summary of the tubes plugged is located in Table 2. No tubes were plugged this outage.
Appendix E contains a map that details the previously plugged tubes.
7.0 Plug History A summary of the number and percentage of tubes plugged is also located in Table 2.
8.0 Condition Monitoring Initially, no inspections were planned for U IRI 8. Experience from recent PVNGS outages indicates that there is an increasing trend in the Steam Generators associated with foreign objects and foreign object wear. In the most recent outage in all 3 units, foreign object wear has been encountered (1R17, 3R17, and 2R1 8). Prior to these findings, there were only 2 other instances of FO wear since SG replacement. As a result, a conservative decision was made to perform a foreign object inspection in PVNGS Unit I during U18RI.
The inspection verified that no foreign objects (or foreign object wear) exist in the high flow regions of the top of tubesheet (TTS) and Flow Distribution Plate areas in each SG. This area was defined as approximately the first 5 rows of the periphery in the hot leg TTS and cold leg TTS. Both primary (ECT) and secondary (FOSAR) inspections were performed in these areas. The extent of the bobbin testing was from tube end to I st eggcrate. The specific inspection plan as well as the plugging criteria was documented in the U I RI 8 Degradation Assessment.
Tube Inspections Per the Steam Generator Program, as defined in PVNGS Procedure 81DP-9RCO1, a condition monitoring evaluation was conducted by PVNGS Engineering. The results of the eddy current examinations are provided in Section 5.0. An engineering evaluation of the as-found condition of inservice tubes did not reveal any degradation exceeding the threshold values for structural and leakage integrity. As such, all steam generator performance criteria were satisfied for Unit I Cycle
- 18. No tube pulls or insitu pressure testing were required based on the results of the examinations.
Foreign Object Search and Retrieval (FOSAR)
Tubesheet FOSAR Activities Tubesheet FOSAR was conducted using a power cart mounted with a remotely operated camera, guide tubes, video probes and various retrieval tooling. The following areas were inspected:
Hot and cold leg top of tubesheet annulus region. At least 5 tube rows into the bundle were viewed from the annulus.
Hot and cold leg blowdown lanes. Approximately 5 rows deep into the tube bundle were viewed from the lane.
Also included in the scope of the FOSAR effort was an inspection of the blowdown patch plate welds that were found to be cracked in Unit I during U IRI 5. The condition was first identified in Unit 2 during U2RI5.
The inspections confirmed that the weld material in the vicinity of the cracked weld on all 4 patch plates (2 per SG) is intact, and a loose parts concern is not being created. A previous evaluation concluded that, with the presence of the cracked welds, the patch plates in the Unit 2 SGs will continue to perform their design function and that the probability of loose parts being formed is remote. This evaluation applies to the Unit I SGs as well since the design is the same. Thus, there is a very low risk that the cracked welds will affect the structural or leakage integrity of tubes in these steam generators.
SG 11 Tubesheet FOSAR Results No foreign objects were found during the inspections on the top of tubesheet in SG 11.
SG 12 Tubesheet FOSAR Results As a result of the inspections performed in SG 12, 5 items were logged as foreign objects. The inspection results were documented in PVAR 4586454. Of the 5 items logged, one foreign object was removed from the SG. Part 12-005 was found on the cold leg side in between tubes R1C6, R2C5 and R3C6 and was successfully retrieved. No wear was identified visually or by ECT in the area of these tubes. Part 12-005 is rod shaped and appears to be a dowel pin as shown in Figure 8-1.
Of the 4 objects that were not retrieved from SG 11:
" Parts12-001 and 12-002 appear to be non-metallic chips. Part 12-001 was identified lying next to tube R23C2 and in the annulus on the cold leg side and measured approximately 0.4 in X 0.2 in X 0.04 in (Figure 8-2). Part 12-002 was identified lying in the annulus near tube R170C115 on the cold leg side and measured approximately 0.35 in X 0.3 in X 0.2 in (Figure 8-3). Since these objects are likely non-metallic (ECT did not identify a part in the areas), the threat to tube integrity is considered very low. There was no wear associated with these tubes. PVNGS has historically taken the position that if a loose part is detected by ECT or FOSAR without the presence of wear, it is reasonable to conclude that the required conditions to promote wear do not exist. Per the PVNGS SG Program, trending of these locations will continue in future outages.
" Part 12-003 appears to be an extremely small sludge rock located in the cold leg annulus near tube R160C137. Part 12-003 measured approximately 0.15 in X 0.04 in X 0.15 in (Figure 8-4). There was no wear associated with these tubes. PVNGS has historically taken
the position that if a loose part is detected by ECT or FOSAR without the presence of wear, it is reasonable to conclude that the required conditions to promote wear do not exist. Per the PVNGS SG Program, trending of these locations will continue in future outages.
Part 12-004 was originally thought to be a sludge rock; however, Plus Point ECT testing did not identify an object in this location, indicating that the material may be graphite. Part 12-004 is located in between tubes R154C59 and R153C60 on the cold leg side. Part 12-004 measured approximately 0.25 in X 0.12 in X 0.12 in (Figure 8-5). Attempts to retrieve this item were unsuccessful. There was no wear associated with these tubes. PVNGS has historically taken the position that if a loose part is detected by ECT or FOSAR without the presence of wear, it is reasonable to conclude that the required conditions to promote wear do not exist. Per the PVNGS SG Program, trending of these locations will continue in future outages.
Figure 8 Part 12-005 - Rod Shaped Object (Dowel Pin) Left: In Bundle; Right: After Retrieval Figure 8 Part 12-001 - Non-Metallic Chip
Figure 8 Part 12-002 - Non-Metallic Chip Figure 8 Part 12-003 - Sludge Rock Figure 8 Part 12-004 - Sludge Rock (possibly graphite material)
Flow Distribution Plate FOSAR Activities Flow Distribution Plate (FDP) FOSAR was conducted using a series of guide tubes video probes and various retrieval tooling. The annulus region was inspected as well as looking in bundle approximately 5 tubes rows.
Note - Foreign material introduced via the feed-train is most often found on the cold leg top of tubesheet. There is a small gap (0.25 inches) in between the bottom of the feedwater box and the top
of the FDP where foreign objects could be introduced via FW onto the FDP, but this is considered a less likely flow path.
Foreign material could also enter the SG through the downcomer piping at the top of the SG. This is also a less likely flow path since only 10% of the feedflow is introduced via the downcomer piping.
This downcomer feed flow is combined with the internal SG recirculation flow and is introduced into the tube bundle at the tube sheet on the hot leg side and through the Downcomer Window on the cold leg side. This window is between the 03C and 04C eggcrate support.
SGI I FDP FOSAR Results As a result of the inspections performed on top of the FDP in SG 11, 1 item was logged as a foreign object.
The inspection results were documented in PVAR 4586212. This was the only foreign object found in SG 11. The object was successfully retrieved from the SG. The object (Part ID 11-001) measures approximately 4 in X 0.128 in X 0.01 in and is metallic and could not be picked up by a magnet (Figure 8-6). The part's origin is unknown. It was located in between tubes R68C9, R66C9, R67C10, R65C10, R66C 11, R65C12, and R63C12. No wear was detected on these tubes or in the area surrounding these tubes by bobbin or plus point ECT.
EL Figure 8 Part 11-001 - Unknown Metallic Object - Left: In Bundle; Right: After Retrieval SG 12 FDP FOSAR Results No foreign objects were found during the inspections on the FDP in SG 12.
Foreign Object Wear Discovered During U RI R8 No foreign object wear was discovered in SG 11 or 12 during FOSAR inspection or during eddy current testing.
Potential Loose Parts SGI 1 The only PLPs detected in SG II during ECT in UIRI8 were historical PLP signals from 1R17 and are shown below. These tubes (and surrounding tubes) were tested with plus point with no indications of wear. It should be noted that these tubes are located near the stay cylinder area.
FOSAR was not performed in this area because it is inaccessible due to the stay cylinder design.
This area is not a high flow region.
Row Col Location 32 79 Hot Leg 33 80 Hot Leg 32 81 Hot Leg SG12 There were no PLP calls in SG 12 detected during ECT in UIRI8. The tubes surrounding R8CI, RIOCI, and R9C2 were tested with plus point with no indications of wear.
Plug Integrity and NSAL 12-1 Inspection No tube plug inspection was required during UIR18. The EPRI Steam Generator Examination Requirements state "Visual examination shall be performed on all installed plugs when the SG is opened for scheduled primary side examinations". The U1RI8 inspection is not a scheduled examination, so there is no requirement to perform this inspection.
A channel head inspection was performed in response to Westinghouse Engineering Nuclear Safety Advisory Letter (NSAL) 12-1, dated January 5, 2012. The inspection was performed in accordance with APS Supplier Document Number 13-MN725-A0201 1. No discrepancies were found.
TABLE 1 EXAMINATION
SUMMARY
SCOPE DESCRIPTION SG II SG 12 Exam Description Extents Scope Scope COLD LEG TEC-0IC 2011 1994 BOBBIN HOT LEG TEH-01IH 1957 1940 BOBBIN HOT STRAIGHT VARIOUS 18 30 RC*
COLD STRAIGHT VARIOUS 47 77 RC*
L U &
Ea C *..
I I
I Notes:
- RC-rotating coil examinations were performed to evaluated bobbin coil examination results
TABLE 2 INDICATION
SUMMARY
DAMAGE STEAM GENERATOR STEAM GENERATOR MECHANISM I1 12 Tube Indications Tube Indications WEAR I%-19%
7 9
0 0
20%-29%
1 1
0 0
30%-39%
0 0
0 0
> 40%
0 0
0 0
PLUGGED (0)
(0)
Possible Loose Parts (RC)
PLI 0
0 PLP 3
0 PLUGGED (0) na (0) na PREVENTATIVE (0) na (0) na PLUGGED (0)
(0)
TOTAL PLUGGED/%
(88 / 0.7%)
(107 / 0.9%)
NOTES
- 1. Numbers in (X) are tubes numbers plugged in each category
- 2. The "Tube" column above represents Bobbin Coil results for the number of tubes; using the largest wear indication
- 3. The "Indications" column above represents Bobbin Coil results for the number of wear indications
APPENDIX A TUBE SUPPORT DIAGRAM, LEGEND, and ANALYSIS CODES
IVNIS Steam Generater REPLACEMENTS Typil Spacing VWI V
1 2
VS3 Vr VS5 BW2 I #11 II II A
B
'1114 IIC 36.75" 35175" 10C 1
07H 35.W 07C 10H35 0FC j 0SH 359r0C
- 04o, 36.34" I 24" 04C 03H4 36.33" ia 2V.125" 03C 0214 36.33" 02C 28125" 32.25" 01C Is.s.
FDP 01H4 20" I
I Center of OSH to 08C Row I - 17.415 Row 2 - 19.736 Row 3 - 22.056 Row 4 - 24.377 Row 5 - 26.698 Row 6 - 29.019 I
Inlet
LEGEND ROW:
COL:
VOLTS:
DEG:
IND:
PER or PCT:
CHN:
LOCN:
Indicates the row number of a given tube.
Indicates the column number of a given tube.
Indicates the peak-to-peak voltage of a given indication response.
The measured phase angle of a given indication response.
Indicates the analysis code or PCT for percent The percent through the tube wall of a given indication Indicates the channel used to make the call Gives indication location at INCH I to [NCH2 relative to known landmarks such as supports, vertical straps, and batwings. Typical location codes are as follows:
- 1 Vertical Strap...........................
VS1
- 1 Batwing....................................
BW1
- 1 Support Plate in Hot Leg............... 01H
- 7 Support Plate in Cold Leg............. 07C Top Tube Sheet Cold Leg.................. TSC Tube End Hot Leg.............................. TEH Tube End Cold Leg............................ TEC CRLEN:
CRWID:
CEG:
BEGT and ENDT:
PDIA:
PTYPE:
CAL:
L:
COM:
Indicates the flaw length, used to identify the length of a wear indication Indicates the flaw width, typically used for cracks only Indicates the flaw length, typically used for cracks only Indicates the beginning and of the test; together they document the examination extent Documents the probe diameter Documents the probe type Indicates calibration number Indicates the leg the examination was conducted from This comment field is utilized to document comments
Analysis Codes:
Absolute Drift.....................................................................
ADI Bulge..................................................................................
BLG Dented Buff M ark..............................................................
DBM Deposit.......................................
DEP Dent....................................................................................
DNT Data Quality Acceptance....................................................
DQA Distorted Support Signal W ith Indication..........................
DSI Distorted Top of Tubesheet W ith Indication......................
DTI Geometric Indication..............................
GEO History Review...............................................................
HR ID Chatter...........................................................................
IDC Indication Not Found.........................................................
INF Indication Not Reportable..................................................
INR M ultiple Axial Indication...................................................
M AI M anufacturer Burnishing M ark..........................................
M BM M ultiple Volumetric Indication..........................................
M VI No Detectable Defect.........................................................
NDD No Discontinuity Found.....................................................
NDF Non-Quantifiable Indication...............................................
NQI No Tube Sheet Expansion..................................................
NTE Obstructed..........................................................................
OBS Over Expanded...................................................................
OXP Previous Bobbin Call.........................................................
PBC Possible Deposit.................................................................
PDP Positive Identification........................................................
PID Positive Identification Verified......................................
PIV Possible Loose Part with Indication...................................
PLI Possible Loose Part............................................................
PLP Previous RC Call................................................................
PRC Possible Support Anomaly.................................................
PSA Possible Support Indication................................................
PSI Permeability Variation Noise.............................................
PVN Retest Bad Data..................................................................
RBD Retest Identification Check................................................
RIC Retest with M agnetic Bias RC Probe.................................
RM B Single Volumetric Indication.............................................
SVI Senior (Lead) Analysis Review.....................................
SR Sludge.................................................................................
SLG To Be Plugged....................................................................
TBP Volumetric Indication.........................................................
VOL Quality Codes:
Cross talk............................................................................
QCT Insufficient extent tested.....................................................
QET Sudden drift of signal base line..........................................
QDO Less than the required samples...........................................
QDR Quality issue for ADS or RTAA........................................
QDS System out of balance.........................................................
QOS Spiking or parasitic noise...................................................
QPN One or more required channels without signal................... QPS Saturated signals in the tube...............................................
QSS Probe speed varies..............................................................
QSV Historical indications not present.......................................
QPV Tube number in question....................................................
QTI
APPENDIX B STEAM GENERATOR 11
SUMMARY
DATA SHEETS
SG -
11 Bobbin Percent Calls ( 1 -
LU Pain Uerdo I UIIRIR PVNG21 281A411 1812112914 19-26-11 I ROW COL VOLTS DEG IND PER CRLEN CHN LOCN INCHI INCH2 BEUT ENOT POIA PTYPE CAL L
IOX UTIL1 UTIL21 1 168 99
.26 122 PCT 8
P2 S1C
.Ol eiC TEC
-610 NBAZI 5
C 186 171 16e
-31 73 PCT 10 P2 SIC
-02 SIC TEC
.610 NBAZ1 6
C 182 171 100
-31 73 PCT 10 P2 SIC
-05 OlC TEC
-610 NBAZI 6
C 182 168 101
.78 74 PCT 20 P2 OIC
-.93 01C TEC
.616 NBAZI 6
C 186 176 161
.39 1"6 PCT 12 P2 SIC
-. 22 SIC TEC
-610 NBAZI 6 C 181 170 101
.61 107 PCT 16 P2 01C 87 OiC TEC
-610 NBAZI 6
C 181 171 102
.33 106 PCT 12 P2 OlC 68 SIC TEC 610 NSAZI 5
C 177 168 103 32 91 PCT 12 P2 Sic 63 SlC TEC
.610 NOAZI 5
C 175 171 104 34 1I" PCT 1t P2 SIC
ý5e SIC TEC
+610 NOAZI 6
C 176 171 166 25 93 PCT 16 P2 SIC 82 SIC TEC 610 NBAZ1 5
C 171 I ROW COL VOLTS DEG IND PER CALEN CNN LOCN INCH!
INCH12 SECT ENOT POIA PTYPE CAL L
lOX UTIL1 UTIL2I I
I......v....*...
I--------
I....
Tubes: 8 Records: 10 1
ST eax
APPENDIX C STEAM GENERATOR 12
SUMMARY
DATA SHEETS (NONE IN SG 12)
APPENDIX D PLI & PLP DATA SHEETS (NONE IN SG 12)
SG -
11
- PT PLP Calls Palo Verde I UIRI8 PVNGS1 201401Qe 1612112014 16-07:55 I ROW COL VOLTS DlEG INO PER CRLEN CHN LOON INCHI INCH2 BEGI ENDT POIA PTYPE CAL L
IOX UTILl UTIIL21 4
4..
.4-.......
.4......
4.-.........
-4 I
32 79 1.83 82 PLP 8
TSH
.35 TSI TSH Gee NPSHZ 12 H
12 HR I
33 8A
.46 98 PLP 8
TSH
.78 TS4 TSH
.642 NPSHZ 12 H
7 HR 32 81 1.55 85 PLP 8
TSH 1.46 TSH TSH
.640 NPSHZ 12 H
8 HR ROW COL VOLTS DEG IND PER CRLEN GIN LOCN INCHI INCH2 BEGT ENDT POIA PTYPE CAL L
IOX UrTIL1 VTIL2I
APPENDIX E PLUG MAPS (SAME AS U1R17)
SG -11 Tubes Plugged in U1R17 PaloVerdeU1R17 PVNGS1 1RSG
- 11 Tubes Plugged in UIR17
- 53 Stay Rod a 77 Plugged Tube 170 l6o t1o 1166 6s0 ISO 14e 135 us 11o 125 120 Its 110 145 100 95 go as 6a 76 74 70 01 60 56 3S 410 45 4.
36 3o 26 20 15 15 is 6
If0IS 20 025 621540 4501 SO Of 67 76101 U6 U 08 10 US t10115 In 125 134131 144145 150 150 140 106 174 M166181961900620 X
X...
- i.
itj ti.4..
it i
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- J i~.
il-i t+
X.
i4~
!+
.ia
- ~.
- J
- ~,
L
%..L
- 4wit,
++~
6 01226014406U60101 OOU6om063162122611464161610061111X.11S2 W9060puEbd*4WWI VwUr. Ti OTw GW$WMi Or= Od 116 106 lie 106 1o 15 146 146 121 136 126 120 116 110 100 its lie 105 16 16 60 16 so as Be 66 50 46 40 35 30 2S 20 16 1
SG-12 Tubes to Plug in U1R17 PaloVerde U1R17 PVNGS1 IRSG m 27 Tubes Plugged In U1R17 0 53 Stay Rod a 81 Plugged Tube 170 105 10 166 1A6 145 140 13S 130 125 12.2 115 110 141 95 100 941 75 is 65 40 55 5,
45 4.
35 30 25 20 15 1o 5
6 10 15 20 26 3435 40 46 660 500 70 707 as6 IS O 10 10 116 n126 120 135 1" 145 16 in IS*
S 170 17V I100 1
10 16 20 174 14S 140 136
. 13 L-,- :-,,-,
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14 IS 21 26S 34 35 441 46 So
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- 16 6s 7
7 116 14 ISM aS 195
- 1952
APPENDIX F FORM NIS-1
APS NIS -1 FORM OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS
- 2. PLANT PALO VERDE NUCLEAR GENERATING STATION 2a. ADDRESS 5801 SOUTH WINTERSBURG ROAD, TONOPAH, ARIZONA 85354
- 3. UNIT NUMBER 1
- 4. OWNERS CERTIFICATE OF AUTHORIZATION NONE
- 5. COMMERCIAL SERVICE DATE 1-28-86
- 6. COMPONENTS INSPECTED:
COMPONENT OR MANUFACTURER SERIAL STATE OR NATIONAL APPURTENANCE OR INSTALLER NUMBER PROVINCE BOARD NO IMRCEEOIA Ansaldo 224 NA 173 STEAM GENERATOR 11 IMRCEEO1B Ansaldo 225 NA 174 STEAM GENERATOR 12 t
.t I
I I
4 I
I I
i i
I
APS NIS-1 BACK OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS
- 7. EXAM DATES October 2014
- 8. INSPECTION INTERVAL 7-18-08 to 7-17-18
- 9. ABSTRACT OF EXAMINATIONS. INCLUDE A LIST OF EXAMINATIONS AND A STATEMENT CONCERNING STATUS OF WORK REQUIRED FOR CURRENT INTERVAL.
Table I in the report summary section documents the number and type of each examination performed.
A summary of the tubes with indications of degradation is listed in Appendix B and C of this report for SG I I and 12 respectively. No tubes were plugged as a result of this examination.
WE CERTIFY THAT THE STATEMENTS MADE IN THIS REPORT ARE CORRECT AND THE EXAMINATIONS AND CORRECTIVE MEASURES TAKEN CONFORM TO THE RULES OF THE ASME CODE, SECTION XI.
Digitally signed by Hansen, Hansen, Douglas Douglas B(Z41530)
DN: cn=Hansen, Douglas DATE SIGNED: ARIZONA PUBLIC SERVICE COMPANY IRT'41530)
B(Z41530)
Date: 2015.03.31 09:05:41 -07'00' CERTIFICATE OF INSERVICE INSPECTION I, THE UNDERSIGNED, HOLDING A VALID COMMISSION ISSUED BY THE NATIONAL BOARD OF BOILER AND PRESSURE VESSEL INSPECTORS AND THE STATE OF PROVINCE OF ARIZONA EMPLOYED BY HSB CT OF HARTFORD, CONNECTICUT HAVE INSPECTED THE COMPONENTS DESCRIBED IN THIS OWNERS REPORT DURING THE PERIOD October2014 TO March2015, AND STATE THAT TO THE BEST OF MY KNOWLEDGE AND BELIEF, THE OWNER HAS PERFORMED EXAMINATIONS AND TAKEN CORRECTIVE MEASURES DESCRIBED IN THIS OWNERS REPORT IN ACCORDANCE WITH THE REQUIREMENTS OF THE ASME CODE, SECTION XI. BY SIGNING THIS CERTIFICATE NEITHER THE INSPECTOR NOR HIS EMPLOYER MAKES ANY
- WARRANTY, EXPRESSED OR
- IMPLIED, CONCERNING THE EXAMINATIONS AND CORRECTIVE MEASURES DESCRIBED IN THIS OWNERS REPORT.
FURTHERMORE, NEITHER THE INSPECTOR NOR HIS EMPLOYER SHALL BE LIABLE IN ANY MANNER FOR ANY PERSONAL INJURY OR PROPERTY DAMAGE OR A LOSS OF ANY KIND ARISING FROM OR CONNECTED WITH THIS INSPECTION.
Digitally signed by Hogstrom.
Robedt
- Hogstrom, (YH2450)
IN: C=Hogstrom, Robert (YH2450) 0)Reason: HSB GS Inspector INSPECTOR Robert (
Date: 2015.04.01 14:18:27 -070' COMMISSIONS N.B. 9685 "A,N,I,C", Az 264 NATL' BOARD, STATE, PROVINCE DATE