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| number = ML102790223
| number = ML102790223
| issue date = 10/25/2010
| issue date = 10/25/2010
| title = 10/05/2010 Summary of Telephone Conference Call Held Between NRC and Energy Northwest, Concerning the Draft Rao Pertaining to the Columbia Generating Station, License Renewal Application
| title = Summary of Telephone Conference Call Held Between NRC and Energy Northwest, Concerning the Draft Rao Pertaining to the Columbia Generating Station, License Renewal Application
| author name = Gettys E
| author name = Gettys E
| author affiliation = NRC/NRR/DLR/RPB1
| author affiliation = NRC/NRR/DLR/RPB1
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:REGU(                                     UNITED STATES "1;.0.,.....             NUCLEAR REGULATORY COMMISSION
{{#Wiki_filter:REGU(
("l                     WASHINGTON, D.C. 20555-0001 o
UNITED STATES "1;.0.,.....
                        !1:
NUCLEAR REGULATORY COMMISSION
                    !                              October 25, 2010
("l WASHINGTON, D.C. 20555-0001 o  
~                 ~
!1:!
1-1)         ~o
October 25, 2010  
      ****'"
~  
LICENSEE:           Energy Northwest FACILITY:           Columbia Generating Station
~
1-1)  
~o LICENSEE:
Energy Northwest FACILITY:
Columbia Generating Station  


==SUBJECT:==
==SUBJECT:==
==SUMMARY==
==SUMMARY==
OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 5, 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.
OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 5, 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)
ME3058)
The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Energy Northwest (EN), held a telephone conference call on October 5, 2010, to discuss and clarify the NRC's draft request for additional information (D-RAI) concerning the Columbia Generating Station, license renewal application (LRA).
The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Energy Northwest (EN), held a telephone conference call on October 5, 2010, to discuss and clarify the NRC's draft request for additional information (D-RAI) concerning the Columbia Generating Station, license renewal application (LRA). 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.
Enclosure 1 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.
The applicant had an opportunity to comment on this summary.
f~~~
f~~~
Evelyn Gettys, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-397
Evelyn Gettys, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-397  


==Enclosure:==
==Enclosure:==
As stated cc w/encls: Distribution via Listserv


As stated cc w/encls: Distribution via Listserv
TELEPHONE CONFERENCE CALL COLUMBIA GENERATING STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS October 5, 2010 PARTICIPANTS AFFILIATIONS Evelyn Gettys Aloysius Obodoako Emma Wong Matt Yoder Ben Parks On Yee Abbas Mostala Doug Ramey John Twomey Scott Wood Marsha Eades Massoud Tafazzoli Mitch McFarland U.S. Nuclear Regulatory Commission (NRC)
 
NRC NRC NRC NRC NRC Energy Northwest (EN)
TELEPHONE CONFERENCE CALL COLUMBIA GENERATING STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS October 5, 2010 PARTICIPANTS                           AFFILIATIONS Evelyn Gettys                         U.S. Nuclear Regulatory Commission (NRC)
EN EN EN EN AREVA AREVA ENCLOSURE 1  
Aloysius Obodoako                      NRC Emma Wong                              NRC Matt Yoder                            NRC Ben Parks                              NRC On Yee                                NRC Abbas Mostala                          Energy Northwest (EN)
Doug Ramey                            EN John Twomey                            EN Scott Wood                            EN Marsha Eades                          EN Massoud Tafazzoli                      AREVA Mitch McFarland                        AREVA ENCLOSURE 1


TELEPHONE CONFERENCE CALL COLUMBIA GENERATING STATION LICENSE RENEWAL APPLICATION October 5, 2010 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Energy Northwest, held a telephone conference call on October 5,2010, to discuss the following draft requests for additional information (D-RAls) concerning the Columbia Generating Station, license renewal application (LRA).
TELEPHONE CONFERENCE CALL COLUMBIA GENERATING STATION LICENSE RENEWAL APPLICATION October 5, 2010 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Energy Northwest, held a telephone conference call on October 5,2010, to discuss the following draft requests for additional information (D-RAls) concerning the Columbia Generating Station, license renewal application (LRA).
Draft RAI B.2.54-1
Draft RAI B.2.54-1  


===Background===
===Background===
Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) Section A.1.2.3.1, states that the scope of the program should include the specific structures and components of which the program manages the aging.
Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) Section A.1.2.3.1, states that the scope of the program should include the specific structures and components of which the program manages the aging.
In addition, SRP-LR Section A.1.2.3.4, states that detection of aging effects should occur before there is a loss of the structure and component intended functions. The parameters to be monitored or inspected should be appropriate to ensure that the structure and component intended functions will be adequately maintained for license renewal under all current licensing basis (CLB) design conditions. This includes aspects such as method or technique (e.g., visual, volumetric, surface inspection), frequency, sample size, data collection and timing of new or one-time inspections to ensure timely detection of aging effects.
In addition, SRP-LR Section A.1.2.3.4, states that detection of aging effects should occur before there is a loss of the structure and component intended functions. The parameters to be monitored or inspected should be appropriate to ensure that the structure and component intended functions will be adequately maintained for license renewal under all current licensing basis (CLB) design conditions. This includes aspects such as method or technique (e.g., visual, volumetric, surface inspection), frequency, sample size, data collection and timing of new or one-time inspections to ensure timely detection of aging effects.
In its response dated August 19, 2010, the applicant states that the Boron Carbide Monitoring Program detects degradation of Boron Carbide neutron absorbers in the spent fuel storage racks by B4 C coupon inspection. The applicant further stated that boron loss is determined through measurement of the boron areal density (i.e., neutron attenuation testing) in the coupons and by insitu areal measurement density techniques, per the corrective action program, such as Boron-10 Areal Density Gauge for Evaluating Racks (BADGER) testing.
In its response dated August 19, 2010, the applicant states that the Boron Carbide Monitoring Program detects degradation of Boron Carbide neutron absorbers in the spent fuel storage racks by B4C coupon inspection. The applicant further stated that boron loss is determined through measurement of the boron areal density (i.e., neutron attenuation testing) in the coupons and by insitu areal measurement density techniques, per the corrective action program, such as Boron-10 Areal Density Gauge for Evaluating Racks (BADGER) testing.
LRA Section B.2.54 does not indicate the number of B4 C coupons used in the Boron Carbide Monitoring Program and whether or not coupon inspection will be performed in the period of extended operation. Furthermore, the applicant indicated that neutron attenuation testing will be performed, but the frequency of testing was not stated.
LRA Section B.2.54 does not indicate the number of B4C coupons used in the Boron Carbide Monitoring Program and whether or not coupon inspection will be performed in the period of extended operation. Furthermore, the applicant indicated that neutron attenuation testing will be performed, but the frequency of testing was not stated.
: 1. Indicate the number of B4 C coupons available for use for the Boron Carbide Monitoring Program and discuss the number of coupons inspected during each inspection and whether coupon inspection will be performed throughout the period extended operation.
: 1. Indicate the number of B4C coupons available for use for the Boron Carbide Monitoring Program and discuss the number of coupons inspected during each inspection and whether coupon inspection will be performed throughout the period extended operation.
: a. Discuss the location of coupons relative to the spent fuel racks and how the coupons are mounted.
: a. Discuss the location of coupons relative to the spent fuel racks and how the coupons are mounted.
ENCLOSURE 2
ENCLOSURE 2  


                                          -2
- 2
: b. Discuss the neutron flux of the coupons relative to that for the fuel assemblies.
: b. Discuss the neutron flux of the coupons relative to that for the fuel assemblies.
: c. Indicate whether or not the coupons are returned back to the spent fuel pool after inspection.
: c. Indicate whether or not the coupons are returned back to the spent fuel pool after inspection.
Line 64: Line 65:
: 3. Provide a commitment in the Table A-1 of the LRA.
: 3. Provide a commitment in the Table A-1 of the LRA.
Discussion: The staff discussed this RAI with the applicant and they understand the staff's question.
Discussion: The staff discussed this RAI with the applicant and they understand the staff's question.
Response to RAI XI.S8-1 Discussion - In letter dated August 19, 2010, (ML102440342) the applicant responded to RAI XI.S8-1 that there was no safety impact on the strainer operation from coating debris on the emergency core cooling system. The staff disagrees with this response and the applicant has agreed to amend their response.
Response to RAI XI.S8-1 Discussion - In {{letter dated|date=August 19, 2010|text=letter dated August 19, 2010}}, (ML102440342) the applicant responded to RAI XI.S8-1 that there was no safety impact on the strainer operation from coating debris on the emergency core cooling system. The staff disagrees with this response and the applicant has agreed to amend their response.
Draft RAI 4.2.1
Draft RAI 4.2.1  


==Background:==
==Background:==
10 CFR 54.3 defines time-limited aging analyses (TLAA) as those licensee calculations and analyses that:
10 CFR 54.3 defines time-limited aging analyses (TLAA) as those licensee calculations and analyses that:
(1) Involve systems, structures and components within the scope of license renewal, as delineated in 10 CFR 50.54(a);
(1) Involve systems, structures and components within the scope of license renewal, as delineated in 10 CFR 50.54(a);
(2) Consider the effects of aging; (3) Involve time-limited assumptions defined by the current operating term, (4) Were determined to be relevant by the licensee in making a safety determination; (5) Involve conclusions or provide the basis for conclusions related to the capability of the system, structure, and component to perform its intended functions, and (6) Are contained or incorporated by reference in the CLB Reactor vessel neutron fluence meets all six of these criteria. It is relevant in making a safety determination because its value affects the reference temperature for nil-ductility transition and the reactor coolant system pressure-temperature limits.
(2) Consider the effects of aging; (3) Involve time-limited assumptions defined by the current operating term, (4) Were determined to be relevant by the licensee in making a safety determination; (5) Involve conclusions or provide the basis for conclusions related to the capability of the system, structure, and component to perform its intended functions, and (6) Are contained or incorporated by reference in the CLB Reactor vessel neutron fluence meets all six of these criteria. It is relevant in making a safety determination because its value affects the reference temperature for nil-ductility transition and the reactor coolant system pressure-temperature limits.
Issue:
Issue:
The Columbia Generating Station License Renewal Application states that neutron fluence is not a TLAA.
The Columbia Generating Station License Renewal Application states that neutron fluence is not a TLAA.  


                                            - 3 Request:
- 3 Request:
Please revise LRA Section 4.2.1 to indicate the correct categorization of neutron fluence and provide the appropriate disposition in accordance with 10 CFR 54.21 (c).
Please revise LRA Section 4.2.1 to indicate the correct categorization of neutron fluence and provide the appropriate disposition in accordance with 10 CFR 54.21 (c).
Discussion: The staff discussed this draft RAI with the applicant and they understands the staff's question.
Discussion: The staff discussed this draft RAI with the applicant and they understands the staff's question.
Draft RAI X In the LRA Page 3.1-11, Item Number 3.1.1-04, the applicant stated in the "Discussion" column that this is not applicable and Cumulative fatigue damage was not identified as a TLAA for Columbia. The staff needs to know more detail about the "not applicable" and "TLAA not identified" .
Draft RAI X In the LRA Page 3.1-11, Item Number 3.1.1-04, the applicant stated in the "Discussion" column that this is not applicable and Cumulative fatigue damage was not identified as a TLAA for Columbia. The staff needs to know more detail about the "not applicable" and "TLAA not identified".
Discussion: The applicant explained that there was no analysis needed per the code. The staff has requested information on the code that was used.
Discussion: The applicant explained that there was no analysis needed per the code. The staff has requested information on the code that was used.  


October 25, 2010 LICENSEE:       Energy Northwest FACILITY:       Columbia Generating Station
October 25, 2010 LICENSEE:
Energy Northwest FACILITY:
Columbia Generating Station  


==SUBJECT:==
==SUBJECT:==
==SUMMARY==
==SUMMARY==
OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 5, 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.
OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 5, 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.
Line 90: Line 91:
The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Energy Northwest (EN), held a telephone conference call on October 5,2010, to discuss and clarify the NRC's draft request for additional information (D-RAI) concerning the Columbia Generating Station, license renewal application (LRA). 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 U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Energy Northwest (EN), held a telephone conference call on October 5,2010, to discuss and clarify the NRC's draft request for additional information (D-RAI) concerning the Columbia Generating Station, license renewal application (LRA). 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.
The applicant had an opportunity to comment on this summary.
IRAJ Evelyn H. Gettys, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-397
IRAJ Evelyn H. Gettys, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-397  


==Enclosure:==
==Enclosure:==
As stated cc w/encls: Distribution via Listserv ADAMS Accession No'.. ML102790223 OFFICE PM:RPB1 :DLR LADLR BC: RPB1 :DLR NAME EGettys YEdmonds BPham DATE 101 110 10/12/10 10/25/10 OFFICIAL RECORD COpy


As stated cc w/encls: Distribution via Listserv ADAMS Accession No'.. ML102790223 OFFICE        PM:RPB1 :DLR                  LADLR                      BC: RPB1 :DLR NAME          EGettys                      YEdmonds                    BPham DATE          101    110                    10/12/10                    10/25/10 OFFICIAL RECORD COpy
Letter to Energy Northwest from E. Gettys dated October 25, 2010.  
 
Letter to Energy Northwest from E. Gettys dated October 25, 2010.


==SUBJECT:==
==SUBJECT:==
==SUMMARY==
==SUMMARY==
OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 5, 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.
OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 5, 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.

Latest revision as of 02:39, 14 January 2025

Summary of Telephone Conference Call Held Between NRC and Energy Northwest, Concerning the Draft Rao Pertaining to the Columbia Generating Station, License Renewal Application
ML102790223
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 10/25/2010
From: Gettys E
License Renewal Projects Branch 1
To:
Gettys E, NRR/DLR, 415-4029
References
TAC ME3058
Download: ML102790223 (7)


Text

REGU(

UNITED STATES "1;.0.,.....

NUCLEAR REGULATORY COMMISSION

("l WASHINGTON, D.C. 20555-0001 o

!1:!

October 25, 2010

~

~

1-1)

~o LICENSEE:

Energy Northwest FACILITY:

Columbia Generating Station

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 5, 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 (EN), held a telephone conference call on October 5, 2010, to discuss and clarify the NRC's draft request for additional information (D-RAI) concerning the Columbia Generating Station, license renewal application (LRA). 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.

f~~~

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

Enclosure:

As stated cc w/encls: Distribution via Listserv

TELEPHONE CONFERENCE CALL COLUMBIA GENERATING STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS October 5, 2010 PARTICIPANTS AFFILIATIONS Evelyn Gettys Aloysius Obodoako Emma Wong Matt Yoder Ben Parks On Yee Abbas Mostala Doug Ramey John Twomey Scott Wood Marsha Eades Massoud Tafazzoli Mitch McFarland U.S. Nuclear Regulatory Commission (NRC)

NRC NRC NRC NRC NRC Energy Northwest (EN)

EN EN EN EN AREVA AREVA ENCLOSURE 1

TELEPHONE CONFERENCE CALL COLUMBIA GENERATING STATION LICENSE RENEWAL APPLICATION October 5, 2010 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Energy Northwest, held a telephone conference call on October 5,2010, to discuss the following draft requests for additional information (D-RAls) concerning the Columbia Generating Station, license renewal application (LRA).

Draft RAI B.2.54-1

Background

Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) Section A.1.2.3.1, states that the scope of the program should include the specific structures and components of which the program manages the aging.

In addition, SRP-LR Section A.1.2.3.4, states that detection of aging effects should occur before there is a loss of the structure and component intended functions. The parameters to be monitored or inspected should be appropriate to ensure that the structure and component intended functions will be adequately maintained for license renewal under all current licensing basis (CLB) design conditions. This includes aspects such as method or technique (e.g., visual, volumetric, surface inspection), frequency, sample size, data collection and timing of new or one-time inspections to ensure timely detection of aging effects.

In its response dated August 19, 2010, the applicant states that the Boron Carbide Monitoring Program detects degradation of Boron Carbide neutron absorbers in the spent fuel storage racks by B4C coupon inspection. The applicant further stated that boron loss is determined through measurement of the boron areal density (i.e., neutron attenuation testing) in the coupons and by insitu areal measurement density techniques, per the corrective action program, such as Boron-10 Areal Density Gauge for Evaluating Racks (BADGER) testing.

LRA Section B.2.54 does not indicate the number of B4C coupons used in the Boron Carbide Monitoring Program and whether or not coupon inspection will be performed in the period of extended operation. Furthermore, the applicant indicated that neutron attenuation testing will be performed, but the frequency of testing was not stated.

1. Indicate the number of B4C coupons available for use for the Boron Carbide Monitoring Program and discuss the number of coupons inspected during each inspection and whether coupon inspection will be performed throughout the period extended operation.
a. Discuss the location of coupons relative to the spent fuel racks and how the coupons are mounted.

ENCLOSURE 2

- 2

b. Discuss the neutron flux of the coupons relative to that for the fuel assemblies.
c. Indicate whether or not the coupons are returned back to the spent fuel pool after inspection.
2. Provide the frequency for which the coupon neutron attenuation testing will be performed.
3. Provide a commitment in the Table A-1 of the LRA.

Discussion: The staff discussed this RAI with the applicant and they understand the staff's question.

Response to RAI XI.S8-1 Discussion - In letter dated August 19, 2010, (ML102440342) the applicant responded to RAI XI.S8-1 that there was no safety impact on the strainer operation from coating debris on the emergency core cooling system. The staff disagrees with this response and the applicant has agreed to amend their response.

Draft RAI 4.2.1

Background:

10 CFR 54.3 defines time-limited aging analyses (TLAA) as those licensee calculations and analyses that:

(1) Involve systems, structures and components within the scope of license renewal, as delineated in 10 CFR 50.54(a);

(2) Consider the effects of aging; (3) Involve time-limited assumptions defined by the current operating term, (4) Were determined to be relevant by the licensee in making a safety determination; (5) Involve conclusions or provide the basis for conclusions related to the capability of the system, structure, and component to perform its intended functions, and (6) Are contained or incorporated by reference in the CLB Reactor vessel neutron fluence meets all six of these criteria. It is relevant in making a safety determination because its value affects the reference temperature for nil-ductility transition and the reactor coolant system pressure-temperature limits.

Issue:

The Columbia Generating Station License Renewal Application states that neutron fluence is not a TLAA.

- 3 Request:

Please revise LRA Section 4.2.1 to indicate the correct categorization of neutron fluence and provide the appropriate disposition in accordance with 10 CFR 54.21 (c).

Discussion: The staff discussed this draft RAI with the applicant and they understands the staff's question.

Draft RAI X In the LRA Page 3.1-11, Item Number 3.1.1-04, the applicant stated in the "Discussion" column that this is not applicable and Cumulative fatigue damage was not identified as a TLAA for Columbia. The staff needs to know more detail about the "not applicable" and "TLAA not identified".

Discussion: The applicant explained that there was no analysis needed per the code. The staff has requested information on the code that was used.

October 25, 2010 LICENSEE:

Energy Northwest FACILITY:

Columbia Generating Station

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 5, 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 (EN), held a telephone conference call on October 5,2010, to discuss and clarify the NRC's draft request for additional information (D-RAI) concerning the Columbia Generating Station, license renewal application (LRA). 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.

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

Enclosure:

As stated cc w/encls: Distribution via Listserv ADAMS Accession No'.. ML102790223 OFFICE PM:RPB1 :DLR LADLR BC: RPB1 :DLR NAME EGettys YEdmonds BPham DATE 101 110 10/12/10 10/25/10 OFFICIAL RECORD COpy

Letter to Energy Northwest from E. Gettys dated October 25, 2010.

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 5, 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)

DISTRIBUTION:

HARD COPY:

DLR RF E-MAIL:

PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource EGettys DDoyle FLyon WWalker, RIV RCohen, RIV LSubin,OGC