ML072000405: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
Line 33: Line 33:
The staff plans to document a brief summary of the conference call as well as any  
The staff plans to document a brief summary of the conference call as well as any  


material that is provided in support of the call.  
material that is provided in support of the call.
: 1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.  
: 1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.  


PG&E Response:  In Unit 1 Cycle 14, a small leak (0.02 gpd) was detected and measured in the steam jet air ejector.
PG&E Response:  In Unit 1 Cycle 14, a small leak (0.02 gpd) was detected and measured in the steam jet air ejector.
Subsequent weekly sampling showed no increase in leak rate.  
Subsequent weekly sampling showed no increase in leak rate.
: 2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results.
: 2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results.
PG&E Response:  No secondary side pressure tests were performed.  
PG&E Response:  No secondary side pressure tests were performed.
: 3. Discuss any exceptions taken to the industry guidelines.
: 3. Discuss any exceptions taken to the industry guidelines.
PG&E Response:  There are no deviations to industry guidelines, with the exception of one minor deviation of "shall" requirement s of Revision 6 of the Secondary Water Chemistry Guidelines. Tables 5-2 and 5-3 of the Guidelines establish limits for exceeding 5% power. Diablo Canyon Units 1 and 2 apply these limits to 8% power.  
PG&E Response:  There are no deviations to industry guidelines, with the exception of one minor deviation of "shall" requirement s of Revision 6 of the Secondary Water Chemistry Guidelines. Tables 5-2 and 5-3 of the Guidelines establish limits for exceeding 5% power. Diablo Canyon Units 1 and 2 apply these limits to 8% power.
: 4. For each steam generator, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion-transition, U-bends with a rota ting probe), the scope of the inspection (e.g., 100% of dents/dings greater than 5 volts and a 20% sample between 2 and 5 volts), and the expansion criteria.
: 4. For each steam generator, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion-transition, U-bends with a rota ting probe), the scope of the inspection (e.g., 100% of dents/dings greater than 5 volts and a 20% sample between 2 and 5 volts), and the expansion criteria.
PG&E Response:  Table 1 provides a su mmary of all inspections performed, and expansion criteria.  
PG&E Response:  Table 1 provides a su mmary of all inspections performed, and expansion criteria.
: 5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications i dentified to-date of each degradation Diablo Canyon 1R14 Steam Generator Inspections  - Phone Call with NRC and PG&E 2mode (e.g., number of circumferential primary water stress corrosion cracking indications at the expansion transition). For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the  
: 5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications i dentified to-date of each degradation Diablo Canyon 1R14 Steam Generator Inspections  - Phone Call with NRC and PG&E 2mode (e.g., number of circumferential primary water stress corrosion cracking indications at the expansion transition). For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the  


voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit).
voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit).
PG&E Response:  Table 2 provides the 1R 14 Repairable indications and Tube Status Report as of 5-14-07 at 1200, and provides the number of indications identified to date of each degradation mode and steam generator tube location. Table 3 provides a list of the most significant indications of eac h damage mechanism. For SCC, the largest voltage indications are listed. Axial ODSCC in the sludge pile region was detected for the first time in Unit 1 (never detected in Unit 2).  
PG&E Response:  Table 2 provides the 1R 14 Repairable indications and Tube Status Report as of 5-14-07 at 1200, and provides the number of indications identified to date of each degradation mode and steam generator tube location. Table 3 provides a list of the most significant indications of eac h damage mechanism. For SCC, the largest voltage indications are listed. Axial ODSCC in the sludge pile region was detected for the first time in Unit 1 (never detected in Unit 2).
: 6. Describe repair/plugging plans.
: 6. Describe repair/plugging plans.
PG&E Response:  Table 2 provides the number of tubes to be plugged as of 5-14-07 at 1200. All repairs are performed by tube pl ugging at both hot and cold legs. Tubes being plugged with circumferential indicati ons are evaluated for stabilization in accordance with vendor criteria.  
PG&E Response:  Table 2 provides the number of tubes to be plugged as of 5-14-07 at 1200. All repairs are performed by tube pl ugging at both hot and cold legs. Tubes being plugged with circumferential indicati ons are evaluated for stabilization in accordance with vendor criteria.
: 7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).
: 7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).
PG&E Response:  To date, there are no indicati ons that require in-situ pressure testing or tube pull.  
PG&E Response:  To date, there are no indicati ons that require in-situ pressure testing or tube pull.
: 8. Provide the schedule for steam generator-related activities during the remainder of the current outage.
: 8. Provide the schedule for steam generator-related activities during the remainder of the current outage.
PG&E Response:  SG inspections are comple ted in SG 1-2 and 1-4, and all inspections will be completed on May 15. SG tube plugging will begin on May 14 and continue  
PG&E Response:  SG inspections are comple ted in SG 1-2 and 1-4, and all inspections will be completed on May 15. SG tube plugging will begin on May 14 and continue  


through May 16.  
through May 16.
: 9. Discuss the following regarding loose parts:
: 9. Discuss the following regarding loose parts:
* what inspections are performed to detect loose parts
* what inspections are performed to detect loose parts
Line 83: Line 83:
No tube degradation or tube wear has been detected that could have re sulted from loose parts. Detection of potential loose part wear was accomp lished using the bobbin probe. EPRI ETSS 96004.1 for detection of wear at tube suppor ts and AVB bars is extended for detection of loose part wear. A special bobbin turbo-mix evaluation at 100% of tubes at the cold leg top of tubesheet was also conducted as an augmented exam.  
No tube degradation or tube wear has been detected that could have re sulted from loose parts. Detection of potential loose part wear was accomp lished using the bobbin probe. EPRI ETSS 96004.1 for detection of wear at tube suppor ts and AVB bars is extended for detection of loose part wear. A special bobbin turbo-mix evaluation at 100% of tubes at the cold leg top of tubesheet was also conducted as an augmented exam.  


Detection of potential loose part wear is also accomplished by both analysis parties screening all three coil rotating probe data.  
Detection of potential loose part wear is also accomplished by both analysis parties screening all three coil rotating probe data.
: 10. Discuss the results of any secondary side inspections.
: 10. Discuss the results of any secondary side inspections.
PG&E Response:  The SG hand hole covers were not removed in 1R14. No secondary  
PG&E Response:  The SG hand hole covers were not removed in 1R14. No secondary  


side inspections (FOSAR) were performed, and no sludge lancing was performed.  
side inspections (FOSAR) were performed, and no sludge lancing was performed.
: 11. Discuss any unexpected or unusual results.
: 11. Discuss any unexpected or unusual results.
PG&E Response:  There were no unexpected or unusual results.  
PG&E Response:  There were no unexpected or unusual results.  

Revision as of 21:54, 12 July 2019

Ssg Tube Inspection Discussion Points Prepared by the Office of NRR for Diablo Canyon Nuclear Generating Station
ML072000405
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 05/14/2007
From:
NRC/NRR/ADES/DCI
To:
Burke, J P, NRR/DCI/CSGB, 415-1529
Shared Package
ML072000353 List:
References
TAC MD5549
Download: ML072000405 (10)


Text

Diablo Canyon 1R14 Steam Generator Inspections - Phone Call with NRC and PG&E 1 STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS

PREPARED BY THE OFFICE OF NUCLEAR REACTOR REGULATION

DIABLO CANYON NUCLEAR GENERATING STATION, DOCKET NO. 05000275

The following discussion points have been pr epared to facilitate the phone conference arranged with Pacific Gas and Electric to discu ss the results of the SG tube inspections to be conducted during the upcoming Diablo Canyon Power Plant, Unit 1 refueling

outage 13. This phone call is scheduled to occur towards the end of the planned SG

tube inspection interval, but before the unit completes the inspections and repairs.

The staff plans to document a brief summary of the conference call as well as any

material that is provided in support of the call.

1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.

PG&E Response: In Unit 1 Cycle 14, a small leak (0.02 gpd) was detected and measured in the steam jet air ejector.

Subsequent weekly sampling showed no increase in leak rate.

2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results.

PG&E Response: No secondary side pressure tests were performed.

3. Discuss any exceptions taken to the industry guidelines.

PG&E Response: There are no deviations to industry guidelines, with the exception of one minor deviation of "shall" requirement s of Revision 6 of the Secondary Water Chemistry Guidelines. Tables 5-2 and 5-3 of the Guidelines establish limits for exceeding 5% power. Diablo Canyon Units 1 and 2 apply these limits to 8% power.

4. For each steam generator, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion-transition, U-bends with a rota ting probe), the scope of the inspection (e.g., 100% of dents/dings greater than 5 volts and a 20% sample between 2 and 5 volts), and the expansion criteria.

PG&E Response: Table 1 provides a su mmary of all inspections performed, and expansion criteria.

5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications i dentified to-date of each degradation Diablo Canyon 1R14 Steam Generator Inspections - Phone Call with NRC and PG&E 2mode (e.g., number of circumferential primary water stress corrosion cracking indications at the expansion transition). For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the

voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit).

PG&E Response: Table 2 provides the 1R 14 Repairable indications and Tube Status Report as of 5-14-07 at 1200, and provides the number of indications identified to date of each degradation mode and steam generator tube location. Table 3 provides a list of the most significant indications of eac h damage mechanism. For SCC, the largest voltage indications are listed. Axial ODSCC in the sludge pile region was detected for the first time in Unit 1 (never detected in Unit 2).

6. Describe repair/plugging plans.

PG&E Response: Table 2 provides the number of tubes to be plugged as of 5-14-07 at 1200. All repairs are performed by tube pl ugging at both hot and cold legs. Tubes being plugged with circumferential indicati ons are evaluated for stabilization in accordance with vendor criteria.

7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).

PG&E Response: To date, there are no indicati ons that require in-situ pressure testing or tube pull.

8. Provide the schedule for steam generator-related activities during the remainder of the current outage.

PG&E Response: SG inspections are comple ted in SG 1-2 and 1-4, and all inspections will be completed on May 15. SG tube plugging will begin on May 14 and continue

through May 16.

9. Discuss the following regarding loose parts:
  • what inspections are performed to detect loose parts
  • a description of any loose parts detec ted and their location within the SG, and if the loose parts were removed from the SG
  • indications of tube damage associated with the loose parts
  • the source or nature of the loose parts if known

PG&E Response:

Diablo Canyon 1R14 Steam Generator Inspections - Phone Call with NRC and PG&E 3Inspections performed to detect loose parts.

There is no EPRI qualified eddy current technique for detection of loose parts. The

techniques used at Diablo Canyon, descri bed below, are consistent with industry practice and have proven effective in findi ng loose parts at Diablo Canyon and many other sites. Tubes with loose part signals are included on the site specific performance demonstration (SSPD) which all analysts are required to pass.

Detection of loose parts is accomplished usi ng the bobbin probe for 100% of the tubes.

Both groups of analysts (primary and secondary) are required to review channel 8 (15

kHz) bobbin data in the strip chart and lissaj ous looking for potential loose part (PLP) indications. In addition, designated analyst s perform a separate in-depth PLP analysis in the full length of tubes (including TSPs and top of tubesheet) in rows 1 to 3 and the three outer periphery tubes. If PLP indica tions are found, the indications require examination with a three coil rotating pr obe (0.115 pancake/+Point/0.080 pancake).

PLP detection with the three coil rotati ng probe is accomplished by screening the 15 kHz pancake coil. PLPs confirmed with the three coil rotating probe also require that the surrounding tubes be examined with the th ree coil rotating probe to bound the PLP.

Detection of potential loose parts is also accomplished by both analysis parties screening all three coil rotating probe data.

Description of any loose parts detected and t heir location within the SG, and if they were removed from the SG.

There were no PLP signals detected in 1R14.

Indications of tube damage associated with the loose parts.

No tube degradation or tube wear has been detected that could have re sulted from loose parts. Detection of potential loose part wear was accomp lished using the bobbin probe. EPRI ETSS 96004.1 for detection of wear at tube suppor ts and AVB bars is extended for detection of loose part wear. A special bobbin turbo-mix evaluation at 100% of tubes at the cold leg top of tubesheet was also conducted as an augmented exam.

Detection of potential loose part wear is also accomplished by both analysis parties screening all three coil rotating probe data.

10. Discuss the results of any secondary side inspections.

PG&E Response: The SG hand hole covers were not removed in 1R14. No secondary

side inspections (FOSAR) were performed, and no sludge lancing was performed.

11. Discuss any unexpected or unusual results.

PG&E Response: There were no unexpected or unusual results.

Diablo Canyon 1R14 Steam Generator Inspections - Phone Call with NRC and PG&E 4 Table 1 - 1R14 Eddy Current Inspection and Expansion Plan Item Area Probe Inspection Criteria Expansion Criteria Expansion Performed 1 Full Length Bobbin 100% (Except Rows 1 and 2 U-bend) N/A If a C-3 condition is identified in the hot leg TTS inspection, inspect 20%

of the cold leg TTS region in the

affected SG in the current or

subsequent outage. The 20%

inspection should be biased to an area where degradation has the

greatest potential to occur.

Not required If cold leg TTS cracking is detected, then either:

Inspect 100% of the cold leg TTS

region in the affected SG, plus 20%

cold leg sample in the other SGs. If

cracking is detected in the 20%

sample, then inspect 100% of the

cold leg TTS in the affected SGs.

OR Define a critical area (CA) and buffer

zone and inspect 100% of the tubes

in the CA and buffer zone in the

affected SG, plus 20% of the cold leg

CA sample in the other SGs.

Not required 2 +Point 100% of hot leg TTS, +2" to -

8"

Note: WEXTEX anomaly

extent is same as above, except NTE anomaly extent is

+2" to tube end.

If cold leg TTS non-crack-line indications are detected, then either:

Define a critical area (CA) and buffer

zone and inspect 100% of the tubes

in the CA and buffer zone in the

affected SG, plus 20% cold leg CA

sample in the other SGs.

OR For Category C-2 cold leg results, inspect an additional 20% cold leg

sample in the affected SG.

For Category C-3 cold leg results, inspect 100% of the cold leg TTS

region in the affected SG, plus 20%

cold leg sample in the other SGs.

Not required 3 +Point 100% of hot leg WEXTEX anomalies If crack-like indications are detected in hot leg WEXTEX anomalies, then

inspect 100% of the cold leg

WEXTEX anomalies.

Not required 4 +Point 100% of previous W* indications within the W*

length N/A N/A 5 WEXTEX TTS Region +Point Distorted tubesheet signals (DTS):

100% of DTS in the hot leg W*

length.

100% of DTS in the cold leg, independent of elevation.

N/A N/A 6 Low Row U-bends +Point 100% of Rows 1 and 2 N/A N/A Diablo Canyon 1R14 Steam Generator Inspections - Phone Call with NRC and PG&E 5Table 1 - 1R14 Eddy Current Inspection and Expansion Plan Item Area Probe Inspection Criteria Expansion Criteria Expansion Performed If circ PWSCC detected in Rows 3 to 8, expand to 100% of Rows 3 to 10 in

the affected SGs.

Not required If circ PWSCC detected in Rows 9 to 10, expand to 100% of rows 11 to 20

in the affected SGs.

Not required If circ PWSCC detected in Rows 11 through 14, redefine critical area (CA) and buffer zone based on review of

Figure 10 of WOG U-Bend report and application of a factor of two

reduction in longitudinal strain, and inspect 100% of the new CA and

buffer zone in the affected SGs.

Not required 7 High Row U-bends for Circ PWSCC +Point 20% of Rows 3 to 8 in each SG.

40% of Rows 5 and 6 in SG 1-

4. If circ PWSCC detected in Rows 15 or higher, expand to 100% of all remaining rows in the affected SGs.

Not required If axial PWSCC detected in Rows 3 to 4, expand to 100% of Rows 3 to 4 and 20% of Rows 5 to 7 in the

affected SGs.

Not required 8 High Row U-bends for Axial

PWSCC +Point 20% of Rows 3 to 4 in each SG If axial PWSCC detected in Rows 5 or greater, then review Figure 5 and

Figure 8 of the WOG U-Bend report

to define a critical area and buffer zone based on tube ovality data and

tube total strain data, and inspect

100% of the CA and buffer zone in

the affected SGs.

Not required 9 5 Volt Dented TSP +Point SG 1-1: 100% 1H to 4H; 20% 5H to 7H SG 1-2: 100% 1H to 7C; 20% 6C SG 1-3: 20% 1H to 7H SG 1-4: 100% 1H to 6H; 20% 7H For any 20% sample, a

minimum of 50 5 volt dents shall be inspected. If the

population of 5 volt dents at that TSP elevation is less than

50, then 100% of the 5 volt dents at that TSP shall be

inspected. If PWSCC (at any size dent), circumferential indications (at any

size dent), or AONDB (at >

5 volt dent) are detected at a TSP elevation where 100% inspections were not

required, expand the Plus Point inspections (in a step-wise manner, 100% to affected TSP and 20% at

next TSP) up through the hot leg side of the SG and down the cold leg side

until a 20% sample is obtained that is

free from PWSCC, circumferential

cracking, or AONDB at >

5 volt dent.

SG 1-1: Axial PWSCC at 7C (1.26 volt dent) detected by bobbin and confirmed by Plus Point, expansion required:

100% of >2 volt dents 5H

to 7C, 20% at 6C. Actual expanded scope was

more conservative and

includes 100% of >2 volt

dents in cold leg.

SG 1-3: Preliminary eval of signal at 7C was

potential axial PWSCC, which initiated an

expansion program, but signal was subsequently

dispositioned as NDD

based on tracing bobbin

signal to baseline

inspection. 100% of >2

volt cold leg dents (103

cold leg dents) and 33%

of >2 volt hot leg dents that were not originally

planned for inspection (140 hot leg dents) were

inspected as part of

expanded scope prior to

termination of the

expansion program.

Diablo Canyon 1R14 Steam Generator Inspections - Phone Call with NRC and PG&E 6Table 1 - 1R14 Eddy Current Inspection and Expansion Plan Item Area Probe Inspection Criteria Expansion Criteria Expansion Performed 10 > 2 Volt and <5 Volt Dented TSP +Point SG 1-1: 100% 1H to 4H; 20% 5H SG 1-2: 100% 1H to 7C; 20% 6C SG 1-3: 20% 1H SG 1-4: 100% 1H to 6H; 20% 7H For any 20% sample, a

minimum of 50 > 2 volt and <

5 volt dents shall be

inspected. If the population of

> 2 volt and < 5 volt dents at

that TSP elevation is less than

50, then 100% of the > 2 volt

and < 5 volt dents at that TSP

shall be inspected. If PWSCC (at any size dent), circumferential indications (at any

size dent), or >

2 inferred volt AONDB (at >2 and <5 volt dent) are detected at a TSP elevation where 100% inspections were not required, expand the Plus Point inspections (in a step-wise manner, 100% to

affected TSP and 20% at next TSP)

up through the hot leg side of the SG and down the cold leg side until a

20% sample is obtained that is free

from PWSCC, circumferential

cracking, or >

2 inferred volt AONDB.

See above expansion scope.

11 < 2 Volt Dented TSP +Point SG 1-1: 100% at 1H, 20% at 2H.

+Point inspection of <

2 volt dents is not required in SGs 1-

2, 1-3, and 1-4, unless dictated by expansion

requirements.

Note: Bobbin is used for

detection of axial PWSCC in

<2 volt dents, and +Point is used to confirm bobbin calls.

Generic criteria: On a SG-specific basis, if a circ indication or >

2 inferred volt AONDB is detected in a dent of "x" volts, where "x" is less

than or equal to 2.3 volts, then

expand Plus Point inspections to

include 100% of dents greater than "x

- 0.3" volts up to the affected TSP, plus 20% of dents greater than "x -

0.3" volts at the next higher TSP.

Note: For any 20% sample, a

minimum of 50 "x - 0.3" volt dents

shall be inspected. If the population

of "x - 0.3" volt dents at that TSP

elevation is less than 50, then 100%

of the "x - 0.3" volt dents at that TSP

shall be inspected.

Specific criteria for 1R14: If a

circumferential indication or >2

inferred volt AONDB is detected in a

dent less than 2.3 volts in SG 1-1 (at 2H or higher), or any TSP elevation

in SGs 1-2, 1-3, or 1-4, then

expansion to less than 2 volt dents would be required.

Not required 12 Repeat PWSCC ARC Indications

at Dents +Point 100% N/A N/A 13 DIS +Point 100% of distorted ID support plate bobbin signals (DIS) at

dented TSP N/A N/A Diablo Canyon 1R14 Steam Generator Inspections - Phone Call with NRC and PG&E 7Table 1 - 1R14 Eddy Current Inspection and Expansion Plan Item Area Probe Inspection Criteria Expansion Criteria Expansion Performed 14 +Point 100% of bobbin distorted OD support signals (DOS) at dented intersections (no lower

voltage cutoff)

N/A N/A 15 +Point 100% of DOS > 1.7 volt N/A N/A 16 +Point DOS with suspected TSP ligament cracking (SLC)

N/A N/A 17 +Point Any bobbin indication in the wedge region exclusion zone N/A N/A 18 +Point DOS at 7 th TSP exclusion zone N/A N/A 19 +Point DOS that extend outside the TSP crevice N/A N/A 20 +Point 100% of hot leg intersections with >2.3 volt SPR (mixed

residual signal), and minimum

of 5 largest hot leg SPR per SG. N/A N/A 21 +Point TSP with copper signals N/A N/A 22 +Point 100% of prior cycle AONDB (bounds commitment to

inspect 100% of AONDB that continue to be NDD by bobbin

in current inspection)

N/A N/A 23 TSP Inspection

for ODSCC ARC +Point 100% of prior cycle TSP SAI-OD that are NDD by bobbin in

current inspection N/A N/A 24 +Point 100% of existing baseline Plus Point confirmed TSP

ligament cracking (LIC or LIG)

indications.

N/A N/A 25 TSP Ligament Cracking +Point 100% of new bobbin SLC indications.

N/A N/A 26 +Point 20% of >5 volt dings in U-bend 20% of >5 volt dings in

straight legs, biased to cold

leg straight sections.

Note: Bobbin is credited for

detection of axial SCC in 5 volt dings If ding ODSCC is detected, then inspect 100% of > 5 volt dings in

affected SGs Not required 27 +Point 100% of paired dings that were not inspected in 1R12 or

1R13, to ensure that 100%

are inspected in 60 EFPM, and to ensure that at least

20% are inspected in 1R14.

If circumferential ODSCC is detected in a paired ding that is greater than or

equal to 2 volts (voltage cutoff for

ding calling criteria), then inspect

100% of paired dings in the affected SGs. Not required 28 Free Span Dings +Point 20% of > 2 volt dings in the U-bend that are coincident with

AVB location If ODSCC is detected at dings in the U-bend coincident with AVB

locations, then inspect 100% of >

2 volt ding indications coincident with

AVB structures.

Not required 29 Free span bobbin indications (MBI, FSI, DNI) +Point 100% of free span bobbin indications that are new or exhibit growth or change.

N/A N/A 30 Cold leg thinning at

TSP +Point 100% of new CLT indications and indications >= 40%TW.

100% of >1.5 volt repeat CLT

indications from 1R9 to 1R12, plus CLT never inspected.

If ODSCC detected at CLT TSP, inspect 100% of CLT indications in

each SG. Not required Diablo Canyon 1R14 Steam Generator Inspections - Phone Call with NRC and PG&E 8Table 1 - 1R14 Eddy Current Inspection and Expansion Plan Item Area Probe Inspection Criteria Expansion Criteria Expansion Performed 31 Possible loose parts and

loose part

damage Bobbin and

+Point Bobbin turbo mix is used to augment normal bobbin analysis techniques at cold

leg TTS for detection of loose part wear.

If possible loose part (PLP) indication is detected by eddy current, perform eddy current

inspection to bound the loose

part. N/A N/A TABLE 2 DIABLO CANYON UNIT 1 R14 Preliminary Repairable Indication and Tube Status Report TubeDegradation1-11-21-31-4 Number of DIS @ <2v DNT (Excludes known flaws)32671816 133 DIS Overcall Rate100%91%100%100%

95.5%# of Confirmed SAI in Above DIS 6 6 Axial PWSCC (New)132 15 Axial PWSCC (Repeat)2617419 219 DENTED TSP Wedge Region / 7th TSP Bending Axial ID/Axial OD 3 3 SAI ID with TSP LIC/LIG Circ ODSCC111 12 Circ PWSCC 1 1 Mixed Mode (SAI ID+SCI ID)

PWSCC Preventive Low Burst Fail PWSCC ARC OA Burst Fail PWSCC ARC DOP >=40% TW 1 1 Repairable Indications1150117 DOS > 2.0 V (Inds) 5230 10 DOS =< 2.0 V (Inds)839588285210 1922 TSP ODSCC AONDB/OD SAI @ >5 V Dent 42 6 GL 95-05 ARC Wedge Region / 7th TSP Bending 1 1 SAI OD with TSP LIC/LIG 2 2 Preventative Plugging (High +Pt Voltage)

Repairable Indications683219 Axial PWSCC (New) in W* Length 11 2 Axial PWSCC (Repeat) in W* Length 5355 18 Axial PWSCC Failed W* Criteria Tubesheet Circ PWSCC @ TTS Axial ODSCC @ TTS 2 2 Axial ODSCC in Sludge Pile 1 1 Circ ODSCC @ TTS 89 17 Repairable Indications909220 Axial PWSCC (Inds)

Axial ODSCC (Inds)

Circ PWSCC (Inds)

Innermost/Outermost Rows with DegradationHigh Row U-bendsAVB Wear >=40%213Cold Leg ThinningThinning >=40%

11TSPVolumetric OD Indication2114Misc.Non-ARC PreventiveTotalPluggable Indications172714664TotalPluggable Tubes172314660 This table shows the number of indications with each type of degradation (not the number of tubes).

  • U-bends Steam Generator Total LocationAREVA Tube Integrity EngineeringDaily Results: 5/14/2007 1:08 PM DegradationSGRowColLocationBobbin Volts Plus Point Volts Estimated Max Depth Estimated Length 1Cold Leg Thinning1131812C - 0.183.690.9845 %TW-2AVB Wear1239577H + 68.693.19-44 %TW-3Axial PWSCC @ Dented TSP1234532H - 0.11NA3.1583 %TW0.51 4559 psi Calculated B P 4Circ PWSCC @ Dented TSP1133372H - 0.03NA0.9141 %TW24 deg 5Axial ODSCC @ TSP111221H - 0.004.2TBD--

6Circ ODSCC @ Dented TSP125751H + 0.34NA0.37TBD61 deg 7Circ ODSCC @ TTS11732TSH - 0.07NDD0.52TBD36 deg 8Axial ODSCC @ TTS143049TSH - 0.07NDD0.123 %TW0.15 9Axial ODSCC in Sludge Pile112145TSH + 1.340.130.11 6%TW Bobbin 0.32 10Axial PWSCC in W* Region12187TSH - 9.31NA2.66TBD0.4 Note: Significance for SCC Indications determined by Plus-point Voltage, except for bobbin coil ARC.

Table 3 List of Most Significant Indications DCPP 1R14 (Preliminary Results)

AREVA Tube Integrity Engineering 5/14/2007