ML103000479

Summary of Telephone Conference Call Between the USNRC and Energy Northwest, Concerning the Draft Request for Additional Information Pertaining to the Columbia Generating Station, LRA

ML103000479
Person / Time
Site:	Columbia
Issue date:	11/19/2010
From:	Gettys E License Renewal Projects Branch 1
To:
Gettys E, NRR/DLR, 415-4029
References
TAC ME3058
Download: ML103000479 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 19,2010 LICENSEE: Energy Northwest FACILITY: Columbia Generating Station

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 26, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENERGY NORTHWEST, CONCERNING THE DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE COLUMBIA GENERATING STATION, LICENSE RENEWAL APPLICATION (TAC NO. ME3058)

The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Energy Northwest (the applicant), held a telephone conference call on October 26, 2010, to discuss and clarify the NRC's draft request for additional information (D-RAI) concerning the Columbia Generating Station, license renewal application. provides a listing of the participants and Enclosure 2 contains a listing of the D-RAls discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

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Evelyn Gettys, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-397

Enclosures:

As stated cc w/encls: Distribution via Listserv

TELEPHONE CONFERENCE CALL COLUMBIA GENERATING STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS October 26, 2010 PARTICIPANTS AFFILIATIONS Evelyn Gettys U.S. Nuclear Regulatory Commission (NRC)

Ching Ng NRC Bill Holston NRC Omesh Chopra ANL Abbas Mostala Energy Northwest (EN)

Scott Wood EN Marsh Eades EN David Lee AREVA Mike Carter AREVA ENCLOSURE 1

TELEPHONE CONFERENCE CALL COLUMBIA GENERATING STATION LICENSE RENEWAL APPLICATION October 26, 2010 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Energy Northwest (the applicant), held telephone conference calls on October 26, 2010, to discuss the following draft requests for additional information (D-RAls) concerning the Columbia Generating Station (Columbia), license renewal application (LRA).

D-RAI 4.3-02 In its review the staff noted that the applicant had listed the generic incore housing penetration cumulative usage factor (CUF) analysis in earlier versions of the basis documents but did not provide any other details regarding the analysis. The staff also noted that 10 CFR 54.3 defines a time limited aging analysis (TLAA) as those licensee calculations and analyses that involve conclusions or provide the basis for conclusions related to the capability of the system, structure, and component to perform its intended functions, as delineated in CFR 54.4(b), or are contained or incorporated by reference in the current licensing basis. If the generic incore penetration CUF analysis was included in the design basis document, it is not clear to the staff why it was later deleted from the basis documents. The applicant did not provide a justification for this action.

Question Provide details regarding the generic incore housing penetration CUF analysis and clarify whether the generic analysis bounded the severity and number of transients for the Columbia incore housing penetrations. Also, provide justification for deleting the incore housing CUF analysis from the Columbia basis documents.

Discussion: The staff discussed with the applicant why the LRA states a TLAA for the incore

.housing penetrations in Appendix C, but not in LRA Section 4.3. The applicant explained that there is not a TLAA but a generic analysis report that was sent out by the manufacture GE. The reference in Appendix C to a TLAA is incorrect.

D-RAI 4.3-08 For all locations listed in LRA Table 4.3-6 other than the feedwater (FW) nozzle locations, the dissolved oxygen (DO) concentrations considered in the Fen calculations are acceptable because the applicant has used either conservative values or values consistent with the plant operating water chemistry data. However, the DO concentrations for the FW nozzle locations stated in the applicant's responses to requests for additional information (RAls) 4.3-07 and 4.3-08 seem to be inconsistent with each other and with the Fen values listed in LRA Table 4.3-6. For example, the staff noted that the DO level in the FW piping during both normal water chemistry (NWC) and hydrogen water chemistry (HWC) operation is >50 ppb and in the reactor vessel shell region is 87 and 1 ppb during NWC and HWC operation.* The applicant has correctly assumed DO values >50 ppb for the nickel alloy FW nozzle safe-end for both water chemistries, and the Fen values are consistent with this assumption. However, the DO value ENCLOSURE 2

- 2 listed in the Table presented in the applicant's response to RAI 4.3-07 lists a value of <50 ppb for HWC condition. This value is inconsistent with the plant data. Also, the basis for assuming a DO value of 40 ppb and not ~50 ppb for the FW nozzle shell junction (i.e., blend radius) is not clear to the staff. A value <50 ppb would be non-conservative for low-alloy steel, and seems to be inconsistent with the minimum Fen listed in LRA Table 4.3-6; for <50 ppb DO, Fen would be 2.55 and not 3.04 listed in the LRA.

Question (a) Clarify if DO concentration for the nickel-alloy FW nozzle safe end under HWC conditions was assumed in Fen calculations to be >50 ppb or <50 ppb. If it was conservatively assumed to be <50 ppb, correct the DO value for FW nozzle safe end in Table 1 of Columbia's response to RAI4.3-0B.

(b) Considering a measured DO value of 54 ppb in the FW piping under HWC conditions, justify using a non-conservative value of 40 ppb DO for low-alloy steel FW nozzle shell junction blend radius in Columbia's response to RAls 4.3-07 and 4.3-0B.

Discussion: The staff discussed with the applicant the use of greater than 50 ppb or less than 50 ppb. The applicant stated that the less than 50 ppb was a typo and will correct that in their response.

D*RAI Cumulative Fatigue Damage AMR As stated in LRA Section 4.3.4, all non-Class 1 components are part of the aging management review (AMR), and fatigue analysis of these components is accomplished by a stress range reduction factor. Therefore, LRA Tables 3.2.2-X, 3.3.2-X, and 3.4.2-X should include any AMR items related to TLAA for managing cumulative fatigue damage of non-Class 1 components.

Question LRA Tables 3.2.2-X, 3.3.2-X, and 3.4.2-X with the AMR results, include any AMR items related to TLAA for managing cumulative fatigue damage of non-Class 1 components. What was the reasoning for not listing the TLAAs?

Discussion The staff will issue a formal RAI.

November 19,2010 LICENSEE: Energy Northwest FACILITY: Columbia Generating Station SUB~'ECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 26, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENERGY NORTHWEST, CONCERNING THE DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE COLUMBIA GENERATING STATION, LICENSE RENEWAL APPLICATION (TAC NO. ME3058)

The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Energy Northwest (the applicant), held a telephone conference call on October 26, 2010, to discuss and clarify the NRC's draft request for additional information (D-RAI) concerning the Columbia Generating Station, license renewal application. provides a listing of the participants and Enclosure 2 contains a listing of the D-RAls discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

IRA!

Evelyn Gettys, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-397

Enclosures:

As stated cc w/encls: Distribution via Listserv DISTRIBUTION:

See next page ADAMS Accession No. ML103000479 *concurrence via e-mail OFFICE PM:RPB1:DLR LA:DLR BC: RPB1 :DLR PM:RPB1 :DLR I NAME EGettys YEdmonds* BPham EGettys I DATE 11/02/10 11/08110 OFFICIAL RECORD COpy 11118/10 11/19/10 I

Memorandum to Energy Northwest from Evelyn H. Gettys dated November 19, 2010

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 26.

2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENERGY NORTHWEST, CONCERNING THE DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE COLUMBIA GENERATING STATION, LICENSE RENEWAL APPLICATION (TAC NO. ME3058)

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