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=Text=
=Text=
{{#Wiki_filter:From:             Mahesh Chawla To:               llahti@entergy.com Date:             08/23/2007 1:24:24 PM
{{#Wiki_filter:From:
Mahesh Chawla To:
llahti@entergy.com Date:
08/23/2007 1:24:24 PM  


==Subject:==
==Subject:==
MD 6564 - STEAM GENERATOR TUBE INSPECTION DISCUSSION DURING UPCOMING PALISADES OUTAGE The NRC staff would like to discuss the results of the SG tube inspections to be conducted during the upcoming Palisades Nuclear Generating Station refueling outage. This phone call shall be scheduled towards the end of the planned SG tube inspection interval, but before the unit completes the inspections and repairs. Please inform me when you get to that point so I can arrange a teleconference with the staff. Following are the points of discussion:
MD 6564 - STEAM GENERATOR TUBE INSPECTION DISCUSSION DURING UPCOMING PALISADES OUTAGE The NRC staff would like to discuss the results of the SG tube inspections to be conducted during the upcoming Palisades Nuclear Generating Station refueling outage. This phone call shall be scheduled towards the end of the planned SG tube inspection interval, but before the unit completes the inspections and repairs. Please inform me when you get to that point so I can arrange a teleconference with the staff. Following are the points of discussion:
: 1.       Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.
: 1.
: 2.       Discuss whether any secondary side pressure tests were performed during the outage and the associated results.
Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.
: 3.       Discuss any exceptions taken to the industry guidelines.
: 2.
: 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 rotating 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.
Discuss whether any secondary side pressure tests were performed during the outage and the associated results.
: 5.       For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications identified to-date of each degradation mode (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).
: 3.
: 6.       Describe repair/plugging plans.
Discuss any exceptions taken to the industry guidelines.
: 7.       Describe in-situ pressure test and tube pull plans and results (as applicable and if available).
: 4.
: 8.       Provide the schedule for steam generator-related activities during the remainder of the current outage.
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 rotating 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.
: 9.       Discuss the following regarding loose parts:
: 5.
!        what inspections are performed to detect loose parts
For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications identified to-date of each degradation mode (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).
!        a description of any loose parts detected and their location within the SG
: 6.
!        if the loose parts were removed from the SG
Describe repair/plugging plans.
!        indications of tube damage associated with the loose parts
: 7.
!        the source or nature of the loose parts if known
Describe in-situ pressure test and tube pull plans and results (as applicable and if available).
: 10. Discuss the results of any secondary side inspections.
: 8.
: 11. Discuss any unexpected or unusual results.
Provide the schedule for steam generator-related activities during the remainder of the current outage.
CC:         Allen Hiser; John Burke; Justin Poole; Kenneth Karwoski
: 9.
Discuss the following regarding loose parts:
what inspections are performed to detect loose parts a description of any loose parts detected and their location within the SG 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
: 10.
Discuss the results of any secondary side inspections.
: 11.
Discuss any unexpected or unusual results.
CC:
Allen Hiser; John Burke; Justin Poole; Kenneth Karwoski  


Mail Envelope Properties       (46CDC2C8.DA0 : 2 : 35476)
Mail Envelope Properties (46CDC2C8.DA0 : 2 : 35476)  


==Subject:==
==Subject:==
MD 6564 - STEAM GENERATOR TUBE INSPECTION DISCUSSION DURING UPCOMING PALISADES OUTAGE Creation Date                 08/23/2007 1:24:24 PM From:                         Mahesh Chawla Created By:                   MLC@nrc.gov Recipients                                               Action               Date & Time entergy.com                                               Transferred           08/23/2007 1:24:46 PM llahti (llahti@entergy.com) nrc.gov OWGWPO01.HQGWDO01                                       Delivered             08/23/2007 1:24:27 PM JPB3 CC (John Burke) nrc.gov OWGWPO04.HQGWDO01                                       Delivered             08/23/2007 1:24:27 PM ALH1 CC (Allen Hiser)
MD 6564 - STEAM GENERATOR TUBE INSPECTION DISCUSSION DURING UPCOMING PALISADES OUTAGE Creation Date 08/23/2007 1:24:24 PM From:
KJK1 CC (Kenneth Karwoski) nrc.gov TWGWPO03.HQGWDO01                                       Delivered             08/23/2007 1:24:28 PM JCP5 CC (Justin Poole)
Mahesh Chawla Created By:
Post Office                                               Delivered           Route entergy.com OWGWPO01.HQGWDO01                                       08/23/2007 1:24:27 PM nrc.gov OWGWPO04.HQGWDO01                                       08/23/2007 1:24:27 PM nrc.gov TWGWPO03.HQGWDO01                                       08/23/2007 1:24:28 PM nrc.gov Files                                   Size               Date & Time MESSAGE                               4265               08/23/2007 1:24:24 PM Options Auto Delete:                           No Expiration Date:                       None Notify Recipients:                     Yes Priority:                             Standard ReplyRequested:                       No Return Notification:                   None Concealed  
MLC@nrc.gov Recipients Action Date & Time entergy.com Transferred 08/23/2007 1:24:46 PM llahti (llahti@entergy.com) nrc.gov OWGWPO01.HQGWDO01 Delivered 08/23/2007 1:24:27 PM JPB3 CC (John Burke) nrc.gov OWGWPO04.HQGWDO01 Delivered 08/23/2007 1:24:27 PM ALH1 CC (Allen Hiser)
KJK1 CC (Kenneth Karwoski) nrc.gov TWGWPO03.HQGWDO01 Delivered 08/23/2007 1:24:28 PM JCP5 CC (Justin Poole)
Post Office Delivered Route entergy.com OWGWPO01.HQGWDO01 08/23/2007 1:24:27 PM nrc.gov OWGWPO04.HQGWDO01 08/23/2007 1:24:27 PM nrc.gov TWGWPO03.HQGWDO01 08/23/2007 1:24:28 PM nrc.gov Files Size Date & Time MESSAGE 4265 08/23/2007 1:24:24 PM Options Auto Delete:
No Expiration Date:
None Notify Recipients:
Yes Priority:
Standard ReplyRequested:
No Return Notification:
None Concealed  


==Subject:==
==Subject:==
No Security:                             Standard
No Security:
Standard  


To Be Delivered: Immediate Status Tracking: Delivered & Opened}}
To Be Delivered:
Immediate Status Tracking:
Delivered & Opened}}

Latest revision as of 22:15, 14 January 2025

Steam Generator Tube Inspection Discussion During Upcoming Palisades Outage
ML072360280
Person / Time
Site: Palisades Entergy icon.png
Issue date: 08/23/2007
From: Mahesh Chawla
NRC/NRR/ADRO/DORL/LPLIII-1
To: Lahti L
Entergy Corp
Chawla M, NRR/DORL/LPL3-1, 301-415-8371
References
TAC MD6564
Download: ML072360280 (4)


Text

From:

Mahesh Chawla To:

llahti@entergy.com Date:

08/23/2007 1:24:24 PM

Subject:

MD 6564 - STEAM GENERATOR TUBE INSPECTION DISCUSSION DURING UPCOMING PALISADES OUTAGE The NRC staff would like to discuss the results of the SG tube inspections to be conducted during the upcoming Palisades Nuclear Generating Station refueling outage. This phone call shall be scheduled towards the end of the planned SG tube inspection interval, but before the unit completes the inspections and repairs. Please inform me when you get to that point so I can arrange a teleconference with the staff. Following are the points of discussion:

1.

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

2.

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

3.

Discuss any exceptions taken to the industry guidelines.

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 rotating 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.

5.

For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications identified to-date of each degradation mode (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).

6.

Describe repair/plugging plans.

7.

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

8.

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

9.

Discuss the following regarding loose parts:

what inspections are performed to detect loose parts a description of any loose parts detected and their location within the SG 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

10.

Discuss the results of any secondary side inspections.

11.

Discuss any unexpected or unusual results.

CC:

Allen Hiser; John Burke; Justin Poole; Kenneth Karwoski

Mail Envelope Properties (46CDC2C8.DA0 : 2 : 35476)

Subject:

MD 6564 - STEAM GENERATOR TUBE INSPECTION DISCUSSION DURING UPCOMING PALISADES OUTAGE Creation Date 08/23/2007 1:24:24 PM From:

Mahesh Chawla Created By:

MLC@nrc.gov Recipients Action Date & Time entergy.com Transferred 08/23/2007 1:24:46 PM llahti (llahti@entergy.com) nrc.gov OWGWPO01.HQGWDO01 Delivered 08/23/2007 1:24:27 PM JPB3 CC (John Burke) nrc.gov OWGWPO04.HQGWDO01 Delivered 08/23/2007 1:24:27 PM ALH1 CC (Allen Hiser)

KJK1 CC (Kenneth Karwoski) nrc.gov TWGWPO03.HQGWDO01 Delivered 08/23/2007 1:24:28 PM JCP5 CC (Justin Poole)

Post Office Delivered Route entergy.com OWGWPO01.HQGWDO01 08/23/2007 1:24:27 PM nrc.gov OWGWPO04.HQGWDO01 08/23/2007 1:24:27 PM nrc.gov TWGWPO03.HQGWDO01 08/23/2007 1:24:28 PM nrc.gov Files Size Date & Time MESSAGE 4265 08/23/2007 1:24:24 PM Options Auto Delete:

No Expiration Date:

None Notify Recipients:

Yes Priority:

Standard ReplyRequested:

No Return Notification:

None Concealed

Subject:

No Security:

Standard

To Be Delivered:

Immediate Status Tracking:

Delivered & Opened