ML11294A300

2011/10/06 Davis-Besse Lr - FW: NRC-FENOC Telecon Notes -- September 29, 2011

ML11294A300
Person / Time
Site:	Davis Besse
Issue date:	10/06/2011
From:	Office of Nuclear Reactor Regulation
To:	Division of License Renewal
References
Download: ML11294A300 (8)

Text

1 Davis-BesseNPEm Resource From: CuadradoDeJesus, Samuel Sent: Thursday, October 06, 2011 3:27 PM To: dorts@firstenergycorp.com Cc: Davis-BesseHearingFile Resource

Subject:

FW: NRC-FENOC Telecon Notes -- September 29, 2011 Attachments:

NRC telecon 092911.pdf Thanks From: dorts@firstenergycorp.com

[1]

Sent: Thursday, October 06, 2011 10:15 AM To: CuadradoDeJesus, Samuel Cc: custerc@firstenergycorp.com

Subject:

NRC-FENOC Telecon Notes -- September 29, 2011 Sam..... attached are the telephone conference call notes from our discussion on September 29, 2011, for your information.

Regarding the numbering of [potential] RAI 4.7.4-1, will this RAI be a Supplemental RAI 4.7.4-1 since RAI 4.7.4-1 has already been issued and responded to in FENOC letter dated 4/15/11, or will it be issued as new RAI 4.7.4-3 since 4.7.4-2 was also issued /responded to in the April 15 letter?

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Steve Dort DBNPS License Renewal 419.321.7662 work 412.974.3369 cell

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Hearing Identifier: Davis_BesseLicenseRenewal_Saf_NonPublic Email Number: 1820 Mail Envelope Properties (377CB97DD54F0F4FAAC7E9FD88BCA6D0806D230B66)

Subject:

FW: NRC-FENOC Telecon Notes -- September 29, 2011 Sent Date: 10/6/2011 3:26:38 PM Received Date: 10/6/2011 3:26:41 PM From: CuadradoDeJesus, Samuel Created By: Samuel.CuadradoDeJesus@nrc.gov Recipients: "Davis-BesseHearingFile Resource" <Davis-BesseHearingFile.Resource@nrc.gov> Tracking Status: None "dorts@firstenergycorp.com" <dorts@firstenergycorp.com> Tracking Status: None Post Office: HQCLSTR01.nrc.gov

Files Size Date & Time MESSAGE 1344 10/6/2011 3:26:41 PM NRC telecon 092911.pdf 34440 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:

Doc No. 092911 TO: File DATE: September 29, 2011 FROM: Larry Hinkle

SUBJECT:

NRC Telecon Regarding Davis-Besse License Renewal NRC Attendees: Sam Cuadrado de Jesus, John Klos, Christopher Sydnor FENOC Attendees: Cliff Custer, Allen McAllister, Larry Hinkle, John Hartigan This telephone conference call was initiated by Sam Cuadrado de Jesus, NRC Project Manager for Davis-Besse License Renewal. The telecon took place at 2:30 PM on September 29, 2011. The purpose of the call was to discuss Davis-Besse License

Renewal Application (LRA) topics related to previous responses to NRC requests for

additional information (RAIs) and to new questions. The topics, discussion summary

and action items are as follows:

RAI 3.2.2.2.3.6-2 In its response dated September 16, 2011, the applicant provided the following.

"Furthermore, the LRA is revised to define the moist air (internal) environment to encompass both the air-water interface and the air environment above the interface.

In conclusion, the Inspection of Internal Surfaces in Miscellaneous Piping and

Ducting Program manages loss of material (except for selective leaching) and

cracking for all in scope components subject to a moist air environment."

Discussion

The NRC reviewer noted that changes to the associated aging management review rows seemed to be as expected. However, the reviewer had a question on rows 25 and 32 of LRA Table 3.3.2-27. The rows are for the environment of air-indoor

uncontrolled (internal) and the reviewer requested that FENOC confirm that these

rows are not associated with an air-water interface and that no changes to these

rows are needed.

Action Item: FENOC to provide a supplemental response to RAI 3.2.2.2.3.6-2. If possible, include in the next letter scheduled for submittal. Otherwise, provide in the

letter due on 10/24/2011.

RAI 4.7.3-1

Background

LRA Section 4.7.3 discusses a fracture mechanics analysis for evaluating the integrity of the RV during the pressurized thermal shock (PTS) event associated with

low-temperature (35 ºF) water injection from the BWST following a small steam line

break. LRA Section 4.7.3 states that the current licensing basis (CLB) analysis for

this event is addressed in the Davis-Besse Updated Safety Analysis Report (USAR),

2 Section 5.2 and that the subject analysis was revised to consider the period of extended operation (52 EFPY).

Issue The staff reviewed USAR Section 5.2 and could not locate the CLB analysis for evaluating RV integrity under the subject PTS conditions. Furthermore, the staff

found no references in LRA Section 4.8 for reports documenting the analysis of RV

integrity under these PTS conditions for the period of extended operation, based on

the 52 EFPY RT PTS values. Requesta. Please state the USAR section and page number where the summary of the CLB analysis of the subject PTS event is located. If a summary of the CLB analysis is not located in the USAR, please state where it can be found. b. Please provide the reports documenting the projected 52 EFPY analysis of RV integrity under the subject PTS conditions Discussion

FENOC responded by stating that the response to RAI 4.7.3-1 will include docketing of the PTS analysis and the approved USAR change notice that updates the Section

5.2 pressurized thermal shock analysis information. The NRC found this acceptable.

Action Item: NRC to issue RAI.

RAI 4.7.4-1

Background

By letter dated June 3, 2011, the applicant provided Amendment 8 to Davis-Besse LRA. LRA Amendment 8 revised the disposition for the analysis of the HPI/Makeup

Nozzle Thermal Sleeves in LRA Section 4.7.4 from "10 CFR 54.21(c)(1)(iii)" to "Not a

TLAA." As an explanation for the revised disposition, LRA Section 4.7.4, as amended, now states that "[b]ased on the [USAR Supplement] commitment [to

replace the subject thermals sleeves], the HPI/Makeup nozzle thermal sleeves are

short-lived (not 40-year) parts and therefore this analysis is not a TLAA." Similarly, LRA Amendment 8 revised the corresponding USAR Supplement section in LRA

Section A.2.7.4 to reflect the changed disposition. LRA Section A.2.7.4, as revised by LRA Amendment 8, now states that, "[b]ased on the commitment [to replace the

subject thermal sleeves], the HPI/makeup nozzle thermal sleeves are short lived (not

40-year) parts and therefore this analysis is not a TLAA." Finally, LRA Section 4.1, Table 4.1-1, was amended per LRA Amendment 8 to state that the evaluation of the

subject thermal sleeves is "Not a TLAA."

Issue The staff determined that aging of the subject thermal sleeves, as discussed in LRA Section 4.7.4, should be identified as a TLAA in LRA Sections 4.1, 4.7.4, and the

USAR Supplement, because the aging mechanism is time dependent (i.e., it is dependent on the number of transient cycles incurred), and the staff cannot accept 3 future commitments to replace components as a means for disposition of the currently-installed components undergoing time-dependent aging processes, without

a TLAA of the currently-installed components.

Request Based on the above, the staff requests that the applicant amend LRA Sections 4.1, 4.7.4, and A.2.7.4 to identify HPI/makeup thermal sleeve aging as a TLAA. The staff

also requests that the applicant select an appropriate disposition under 10 CFR

54.21(c)(1). If the applicant proposes a 10 CFR 54.21(c)(1)(iii) disposition for this

analysis, then the staff requests that the applicant amend LRA Sections 4.7.4 and

A.2.7.4 to propose an appropriate aging management program (AMP) for managing

the effects of aging on the intended function of the thermal sleeves. Any AMP

identified in LRA Sections 4.7.4 and A.2.7.4 for a 10 CFR 54.21(c)(1)(iii) disposition

of this analysis should ensure that the effects of aging on the subject thermal sleeves

are appropriately managed for the period of extended operation.

Discussion

FENOC responded by stating the request is understood. Also, FENOC stated that the TLAA is only applicable to the HPI nozzle used for makeup duty and that periodic

inspection of the HPI/makeup nozzle thermal sleeve is conducted under the ISI Program. Therefore, FENOC plans to use the ISI Program to manage the effects of

aging for the HPI/makeup nozzle thermal sleeve. The NRC found this to be

acceptable. Also, the NRC wanted to know if this inspection requires an

enhancement to the ISI Program. FENOC responded that the program description

would be revised to show that the ISI Program manages the subject TLAA but did not

plan to identify the inspection as an enhancement since the inspection is already included in the existing ISI Program. Relative to the enhancement issue, the NRC reviewer was not sure if the FENOC response was acceptable and would follow-up

with NRC management.

Action Items:1) NRC to determine if an ISI Program enhancement is needed to address the HPI/makeup nozzle thermal sleeve inspection.2) NRC to issue RAI.

RAI 4.7.5.2-2 BackgroundLRA Section 4.7.5.2 addresses the TLAA related to the Steam Generator 1-2 flaw evaluations. LRA Section 4.7.5.2 states that the subject flaws were analytically

evaluated using the ASME Code,Section XI, IWB-3612 acceptance criteria. LRA

Section 4.7.5.2 further states that the IWB-3612 analysis of the subject flaws

determined that the steam generator shell components containing the flaws would

remain acceptable for continued service during the period of extended operation, accounting for flaw growth due to fatigue based on 240 heat-up and cool-down

cycles.

4 By letter dated March 17, 2011 (ADAMS Accession No. ML110680172) the NRC staff submitted a request for additional information (RAI) concerning the plant-

specific time-limited aging analyses (TLAAs) in the Davis-Besse License Renewal Application (LRA), Sections 4.7.4, 4.7.5.1, and 4.7.5.2. RAI Question No. 4.7.5.2-1 (RAI 4.7.5.2-1) was issued to request clarification on a number of issues concerning

the subject steam generator shell flaws and the ASME Code,Section XI, IWB-3612

analytical evaluations of these flaws.In RAI 4.7.5.2-1, part (b), the staff requested that the applicant state whether the subject flaws were found to be the result of service-induced degradation or

fabrication defects. In RAI 4.7.5.2-1, part (e) the staff requested that the applicant

state whether the flaw dimensions have increased since discovery in 1988. The staff also requested that, if the flaw dimensions have increased, the applicant state

whether the subject flaws were re-analyzed in accordance with ASME Code, Section

XI, IWB-3612 requirements based on the new flaw dimensions. In RAI 4.7.5.2-1, part (g), the staff requested that the applicant provide references for all reports documenting IWB-3612 analytical evaluations of the subject flaws.

Issue By letter dated April 15, 2011, the applicant submitted its responses to the staff's RAIs. In its response to RAI 4.5.2.1, part (b), the applicant stated that the subject flaws "were analyzed in accordance with IWB-3612, as required by the ASME

[Code],Section XI acceptance standards, and found to be acceptable for continued

operation." The staff reviewed the applicant's response to RAI 4.7.5.2-1, part (b) and

noted that the applicant did not state whether the subject flaws were determined to

be service-induced or caused by fabrication. In its response to RAI 4.7.5.2-1, part (e), the applicant stated that "[t]he subject components were reexamined during Cycle 6 (year 1990) and no flaw growth was

noted. The subject components, with the exception of the W axis longitudinal seam

weld intersection with the shell to lower tubesheet weld, were also reexamined during

Cycle 7 (year 1991) and no flaw growth was noted." The staff reviewed the applicant's response to RAI 4.7.5.2-1, part (e), and noted that the RAI response only

stated that no flaw growth was noted during the ASME Code, Section IWC-2420(b)-

required successive inspections performed in 1990 and the subsequent inspections performed in 1991. The staff noted that the applicant did not state whether any flaw

growth was noted for the subject components as a result of any examinations

performed on the flawed regions after 1991. In its response to RAI 4.7.5.2-1, part (g), the applicant stated that the subject flaw evaluations are documented in the following Babcock & Wilcox (B&W) Reports from

1988:1. Report No. 32-1172294-00, "Davis-Besse 1 SG Flaw Evaluation," dated June 9, 1988 2. Report No. 32-1172294-01, "Davis-Besse 1 SG Flaw Evaluation," dated July 18, 1988

53. Report No. 32-1172523-00, "DB-1 SG Flaw Evaluation," dated July 18, 1988 The above flaw evaluation reports were provided in an enclosure to the April 15, 2011 RAI response. These flaw evaluation reports reference the 1977 Edition of the

ASME Code,Section XI, IWB-3612 analytical acceptance standard. The flaw

evaluation report summaries state that the subject flaws were found to be

acceptable, in accordance with the ASME Code,Section XI, IWB-3612 analytical

acceptance standard.

In reviewing the above flaw evaluation reports, the staff determined that the subject flaw evaluations were only performed for normal conditions, and only demonstrated

acceptability based on the analytical acceptance criterion for normal (including upset

and test) operating conditions, as specified in the ASME Code,Section XI, IWB-

3612, paragraph (a). The staff determined that the applicant had not specifically

evaluated the subject flaws for emergency and faulted conditions, as required by the

1977 Edition of the ASME Code,Section XI, IWB-3612, paragraph (b).

Request Based on the above, the staff requests that the applicant provide the following information concerning the subject steam generator flaws and the analytical

evaluations performed for these flaws: 1) Taking into consideration the steam generator shell materials containing the flaws, the secondary side water and steam environment, and the secondary side

thermal and pressure stresses to which these shell components are subjected, please state whether any of the surface-breaking indications were believed to

have been caused by stress corrosion cracking, or any other service-induced

aging effect. 2) For any inservice examinations performed on the flawed regions of the steam generator shell after 1991, in particular the examinations performed for the steam

generator X/Y axis outlet nozzle to shell weld and the lower tubesheet to shell

weld during the first and second periods of the third 10-year ISI interval, please

state whether these examinations detected any increase in the flaw dimensions, relative to the 1988 flaw dimensions. (The staff notes that any measured

increase in flaw dimensions would likely invalidate the analyses performed in the

1988 flaw evaluation reports.) 3) Please state whether the subject flaws were analyzed for emergency and faulted conditions, as required by the ASME Code,Section XI, IWB-3612, paragraph (b).

If the subject flaws were analyzed for emergency and faulted conditions, as

required by IWB-3612, paragraph (b), please provide the flaw analyses for these

conditions, or explain how the IWB-3612, paragraph (a) analyses, as documented

in the 1988 flaw evaluation reports, for normal, upset, and test conditions, would

bound the flaw analyses for emergency and faulted conditions. If the subject

flaws were not analyzed for emergency and faulted conditions, please provide

these analyses, as required by IWB-3612, paragraph (b).

6 DiscussionThe NRC reviewer wanted to know whether any of the surface-breaking indications were believed to have been caused by stress corrosion cracking, or any other service-induced aging effect. After some discussion, it was agreed that in the RAI response FENOC would provide an assessment to support the position that the

subject flaws were most likely caused by fabrication defects.The NRC reviewer wanted to know whether any inservice examinations performed on the flawed regions of the steam generator shell after 1991 have increased in the flaw dimensions, relative to the 1988 flaw dimensions. FENOC responded that there

has been no increased in the flaw dimensions, relative to the 1988 flaw dimensions and that the only steam generator flaw location still scheduled for examination in the current ISI interval is the SG 1-2 W/X axis outlet nozzle to shell weld; scheduled for

the 17Mid cycle outage that starts on October 1, 2011.

The NRC reviewer wanted to know whether the subject flaws were analyzed for emergency and faulted conditions, as required by the ASME Code,Section XI, IWB-

3612, paragraph (b). FENOC responded that the flaw analyses were conducted in

accordance with the 1977 edition of the ASME Code and that this edition did not

require consideration of emergency and faulted conditions. The NRC reviewer found

this response acceptable but would need to verify that the 1977 edition did not

require analysis of emergency and faulted conditions.

Action Items: NRC to issue RAI There was no further discussion, and the call was concluded.