GO2-11-083, Response to Request for Additional Information License Renewal Application

Response to Request for Additional Information License Renewal Application

ML11115A098
Person / Time
Site:	Columbia
Issue date:	04/21/2011
From:	Swank D Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-11-083
Download: ML11115A098 (26)

Text

GDave A. Swank ENERGY Acting Vice President, Engineering P.O. Box 968, Mail Drop PE04 NORT fHW EST Richland, WA 99352-0968 NORTH

~W EST Ph. 509-377-2309 F.

509-377-4173 daswank @ energy-northwest.com April 21, 2011 G02-11-083 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION

References:

1) Letter, G02-10-11, dated January 19, 2010, WS Oxenford (Energy Northwest) to NRC, "License Renewal Application"

2) Letter dated October 14, 2010, NRC to SK Gambhir (Energy Northwest),

"Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application," (ADAMS Accession No. ML102800426)

3) Letter, G02-11-014, dated January 18, 2011, SK Gambhir (Energy Northwest) to NRC, "Response to Request for Additional Information, License Renewal Application"

4) Letter dated March 15, 2011, NRC to Energy Northwest, "Summary of Telephone Conference Call Held on March 8, 2011, Between the US Nuclear Regulatory Commission and Energy Northwest, Concerning the Responses to the Request for Additional Information Pertaining to the Columbia Generating Station, License Renewal Application (ML110690997)"

5) Letter, G02-11-031, dated January 28, 2011, SK Gambhir (Energy Northwest) to NRC, "Response to Request for Additional Information, License Renewal Application"

6) Letter, G02-11-030, dated January 28, 2011, SK Gambhir (Energy Northwest) to NRC, "Response to Request for Additional Information, License Renewal Application"

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION Page 2 of 3

7) Letter dated April 5, 2011, NRC to Energy Northwest, "Summary of Telephone Conference Call Held on March 23, 2011, Between the U.S.

Nuclear Regulatory Commission and Energy Northwest, Concerning the Request for Additional Information Pertaining to the Columbia Station, License Renewal Application (ML110871495)"

8) Letter dated February 16, 2011, NRC to Energy Northwest, "Summary of Teleph6ne Conference Call Held on January 24, 2011, Between the U.S.

Nuclear Regulatory Commission and Energy Northwest, Concerning the Request for Additional Information Pertaining to the Columbia Station, License Renewal Application (ML110260380)"

Dear Sir or Madam:

By Reference 1, Energy Northwest requested the renewal of the Columbia Generating Station (Columbia) operating license. Via Reference 2, the Nuclear Regulatory Commission (NRC) requested additional information related to the Energy Northwest submittal.

In a conference call on January 24, 2011 (Reference 8), the NRC staff requested additional information about Table 3.3.2-18; similar to that asked in Request for Additional Information (RAI) 3.3.2.3.16-1 about Table 3.3.2-16. The response to original RAI was provided in Reference 3. The additional information requested is provided in the attachment.

During the conference call discussed in Reference 4, Energy Northwest agreed to amend the License Renewal Application (LRA) to address the examinations of the cast austenitic stainless steel (CASS) valves included in the Small Bore Piping Program (Reference RAI 3.1.2.3-01). However, during the review of documentation, Energy Northwest determined that there are no CASS ASME III class 1 valves less than four inches installed at Columbia. Amendment 31 is provided in the Enclosure to remove the material and environment combination from the LRA.

In References 5 and 6 (Reference RAI 3.1.2.3.1-2), Energy Northwest clarified that portions of the reactor pressure vessel shell welds BG and BM would be evaluated in accordance with the ASME Code,Section XI, IWB-3600, inservice inspection (ISI) for the period of extended operation because the welds are subject to time limited aging analysis (TLAA). In a conference call on March 23, 2011 (Reference 7), the NRC staff discussed crediting both ISI and TLAA in the Aging Management Review. Amendment 31 clarifies that the welds are subject to TLAA in addition to the ISI Program.

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION Page 3 of 3 No new commitments are contained in this letter. If you have any questions or require additional information, please contact Abbas Mostala at (509) 377-4197.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the date of this letter.

DA Swank Acting Vice President, Engineering

Attachment:

Supplemental Information

Enclosure:

Amendment 31 cc:

NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident Inspector/988C EFSEC Manager RN Sherman - BPA/1 399 WA Horin - Winston & Strawn AD Cunanan - NRC NRR (w/a)

BE Holian - NRC NRR RR Cowley - WDOH

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION Attachment Page 1 of 2 Supplemental Information for RAI 3.3.2.3.16-1 The NRC staff requested that Energy Northwest review the response to this request for information (RAI) from the letter dated October 14, 2010, NRC to SK Gambhir (Energy Northwest), "Request for Additional Information for the Review of the Columbia Generating Station, License Renewal Application," (ADAMS Accession No. ML102800426). In a teleconference call on January 24, 2011, the NRC requested that Energy Northwest provide additional clarification as to why the pump casings for License Renewal Application (LRA) Table 3.3.2-18, Row No. 46 are not managed by an Aging Management Program (AMP). The original RAI was directed at stainless steel components exposed to air-outdoor (external).

Original RAI 3.3.2.3.16-1 SS Components RAI 3.3.2.3.16-1

Background:

LRA Tables 3.3.2-16, 3.3.2-42 and 3.4.2-3 state that for stainless steel flexible connections, nozzles, orifices, piping, valve bodies, and tubing exposed to air-outdoor (internal), there is no aging effect and no aging management program (AMP) is proposed. The AMR line items cite Generic Note G.

Issue:

The staff notes that the GALL Report does not address stainless steel components in an outdoor air environment; however, given the stations location to arid land, agriculture, road salt compound, and cooling tower vapor, trace compounds (e.g.,

chlorides) could be contained in the outside air supply that could cause loss of material in stainless steel components.

Request:

Justify why the outside air environment does not contain trace compounds that could cause loss of material in stainless steel components, or propose an AMP to manage the aging of stainless steel flexible connections, nozzles, orifices, piping, valve bodies, and tubing exposed to air-outdoor (internal).

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION Attachment Page 2 of 2 Supplemental Information for RAI 3.3.2.3.16-1 LRA Table 3.3.2-18, Row 46 states that the stainless steel pump casings for transfer pumps DO-P-1 A, 1 B, and 2 have an air-outdoor external environment. This row is in reference to the pump columns that are located inside the storage tanks above the air-oil interface. The environment for the discharge head is air-indoor (LRA Table 3.3.2-18, Row 45). These transfer pumps are configured such that the pump discharge head sits on top of the storage tanks and the pump shafts and impellers are in the storage tanks.

The storage tanks are buried except where access is provided via vertical pipe section inside each tank room of the diesel generator building. The pump discharge head sits on top of each storage tank within the diesel generator building within the applicable pipe section. The pumps are oriented in the vertical position within the storage tanks.

The impeller section of the pump is connected to the discharge head by a stainless steel column pipe. The environment for the column pipe within the storage tanks is air-outdoor (external) and fuel oil (external). The top part of the column pipe within the storage tanks above the air-oil interface is exposed to outdoor air because the tanks are vented to the atmosphere outside the diesel generator building. The tank is vented through a flame arrester which prevents free flow of air into the tank. The inlet to the flame arrester is in the downward position and contains a weatherhood. As a result of the flame arrester configuration, there is a limited amount of air entering or exiting the storage tanks. In addition, the flame arrester has an element which also minimizes air entering or exiting the storage tanks. The flame arrester opens and closes just enough to maintain safe working pressures. The flame arrester blocks off the flow path to outside air when the tank pressure is steady.

In conclusion, the configuration of the flame arrester minimizes the introduction of outdoor air and atmospheric contaminants inside the storage tanks. Due to the fact that a very limited amount of air entering the storage tanks must pass through the flame arresters, there are no aging effects that would require management.

The stainless steel components exposed to outdoor air (both internally and externally) in tables 3.3.2-42 (standby service water) and 3.4.2-3 (condensate nuclear system) will be managed by the External Surfaces Monitoring Program. In addition, aluminum components exposed to outdoor air (both internally and externally) in tables 3.3.2-18 (diesel fuel oil system) and 3.3.2-22 (fire protection system) will also be managed by the External Surfaces Monitoring Program. LRA Amendment 31 is provided as an attachment to this letter to reflect these changes.

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION LICENSE RENEWAL APPLICATION Enclosure Page 1 of 1 License Renewal Application Amendment 31 LRA Section Number Page Number RAI Number Table 3.1.2-1, 3.1-31a Supplement to Row 20a 3.1.2.3.1-2 Table 3.1.2-3, 3.1-114b Supplement to Row 182 & 183 3.1.2.3-01 Table 3.3.2-18 3.3-208 Supplement to Line Items 16 & 17 3.3.2.3.16-1 Table 3.3.2-18 3.3-212 Supplement to Line Item 46 3.3.2.3.16-1 Table 3.3.2-22 3.3-234 Supplement to Line Items 11 & 12 3.3.2.3.16-1 Table 3.3.2-42 3.3-381 Supplement to Line Items 29, 31 & 32 3.3.2.3.16-1 Table 3.3.2-42 3.3-382 Supplement to Line Items 36 & 41 3.3.2.3.16-1 Table 3.3.2-42 3.3-383 Supplement to Line Items 43 & 47 3.3.2.3.16-1 Table 3.3.2-42 3.3-385 Supplement to Line Items 61 & 64 3.3.2.3.16-1 Table 3.3.2-42 3.3-388 Supplement to Line Item 95 3.3.2.3.16-1 Table 3.3.2-42 3.3-389 Supplement to Line Item 98 3.3.2.3.16-1 Table 3.3.2-xx 3.3-400 Supplement to Insert Rows 3.3.2.3.16-1 Table 3.3.2-xx 3.3-400b Supplement to Rows 0332 & 0333 3.3.2.3.16-1 Table 3.4.2-3 3.4-50 Supplement to Line Item 58 3.3.2.3.16-1 Table 3.4.2-3 3.4-51 Supplement to Line Items 62 & 68 3.3.2.3.16-1 Table 3.4.2-3 3.4-52 Supplement to Line Item 69 3.3.2.3.16-1 Table 3.4.2-xx 3.4-78 Supplement to Insert Row 0413 3.3.2.3.16-1 Section A.1.3.7.1 A-40 Supplement to 3.1.2.3.1-2 Section A. 1.3.7.1 A-40a Supplement to 3.1.2.3.1-2 Table C-11 C-30 Supplement to Line Item 14 3.1.2.3.1-2

ITable 3.1.2-1 Aging Management Review Results - Reactor Pressure Vessel Columbia Generating Station License Renewal Application Technical Information Insert A to Page 3.1-31 Aging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801 Table 1 Notes No.

Type Function(s)

Management Program Volume 2 Item Item RPV Shell Reactor 20a (welds BG and Pressure Steel w. SS Coolant Cracking - Flaw BM)

Boundary Cladding (Internal)

Growth Inservice Inspection N/A N/A K

Aging MngmtR Rag A

Aging Management Review Results Page 3.1-31 a Arremdrmemt 27 jAmendment 31

Colunmbia Generating Station License Renewal Application Technical Information Table 3.1.2-3 Aging Management Review Results - Reactor Coolant Pressure Boundary Aging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801 Table 1 Notes No.

Type Function(s)

Management Program Volume Item 2 Item Piping &

Pressure Stainless Reactor Cracking -

180 Fittings <4 Boundary Steel coolant Cckig-Inservice Inspection IV.C1-1 3.1.1-48 A

inches Steel (Internal)

SCC/IGA Piping &

Reactor Cracking -

181 Fittings <4 Pressure Steel coolant CraciGrw Inservice Inspection NA NA H

inches Boundary Internal Flaw Growth X/

0 14; D

Reactor f,J L'zi 't 182e L

cuuldln It-1 loIuVice h IspJeiu I I

-NA-S<4 inches Boundary (Internal)

Flaw Growth Valve Bodies Pressure Reactor

_k-IA 8

~

s eulOa,,it Crackeeing-legtvc Wrzctc G4G-1. i

.4-.4-48--A-

< 4 inchqes Boundary (Internal)

Z)U;U/I1UA Reactor 184

<a4eBodies Pressure Stainless coolant Crackingr-Inservice Inspection NA NA H

< 4 inches Boundary Steel (Internal)

FlawGrowth Valve Bodies Pressure Stainless Reactor Cracking -

185Valve Bodies Pressure Stainless coolant SICCIGN nservice Inspection IV.C1-1 3.1.1-48 A

<4 inches Boundary Steel (Internal)

Reactor Crcig-I 186 Valve Bodies Pressure coa Crackingn-

< 4 inches Boundary Steel coolant Flaw Growth Inservice Inspection NA NA H

I(Internal)

FlwGot Aging Management Review Results Page 3.1-114b Amnmn I

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-18 Aging Management Review Results - Diesel Fuel Oil System Row No.

Component Type Intended Function(s)

Material Environment Aging Effect Requiring Management Aging Management Program NUREG-1801 Volume 2 Item Table 1 Item Notes

-~

~-

4

.4.

4 4

4

.4

.4.

4 10 11 Filter Body Pressure boundary Gray Cast Iron Fuel oil Loss of (Internal) material Chemistry Program Effectiveness Inspection Selective Leaching Inspection VII.H1-10 3.3.1-20 A

4

+

4 4-

-4 4

+

Filter Body Pressure boundary Gray Cast Iron Fuel oil Loss of (Internal) material NIA N/A G

_______ 4 4

I.

+

4 4

4

.4 12 Filter Body Pressure boundary Gray Cast Iron Air-indoor uncontrolled (External)

Loss of material External Surfaces Monitoring VII.I-8 3.3,1-58 A

-4

+'

4 4

.4

.4-13 Filter Body Pressure boundary Steel Steel 14 15 16 Filter Body Filter Body Pressure boundary Fuel oil (Internal)

Fuel oil (Internal)

Air-indoor uncontrolled (External)

Loss of materia Loss of materia Fuel Oil Chemistry External Surfaces Monitoring VII.H1-10 VII.I-8 Loss of material Chemistry Program VII.HI-Effectiveness 10 Inspection 3.3.1-20 3.3.1-20 3.3.1-58 A

B Pressure boundary Steel Flame Arrestor Structural integrity Aluminum Alloy Air-outdoor (Internal)

A G

`4 None None N/A N/A 103241

-10332 17 Flame Arrestor Structural integrity 18 Flexible Pressure Connection boundary Aluminum Alloy Stainless Steel Air-outdoor (External)

Fuel oil (Internal)

Loss of material None None Chemistry Program Effectiveness Inspection N/A VII.1H11-6 N/A 3.3.1-32 G

0332 A

Aging Management Review Results Page 3.3-208 Ja O

jAmendment 31

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-18 Aging Management Review Results - Diesel Fuel Oil System NUREG-Row Component Intended Aging Effect Aging 1801 Table No.

Type Function(s)

Material Environment Requiring Management Volume 2 1 Item Notes Management Program Item Pump Casing Pressure Stainless Air-outdoor 46 (DO-P-None None N/A N/A G

1A,1B,2) boundary Steel (External) 0333 Chemistry Pump Casing Chemistr 47 (DO-P-Pressure Stainless Fuel oil Loss of Program VII.H1-6 3.3.1-A 1A,113,2) boundary Steel (External) material Effectiveness 32 Inspection Pump Casing Pressure Stainless Fuel oil Loss of Fuel Oil 3.3.1-48 (DO-P-32.H-1A,1B,2) boundary Steel (External) material Chemistry 32 Chemistry 49 Strainer (body)

Pressure Gray Cast Fuel oil Loss of Program VII.H1-3.3.1-A boundary Iron (Internal) material Effectiveness 10 20 Inspection 50 Strainer (body)

Pressure Gray Cast Fuel oil Loss of Fuel Oil VII.H1-3.3.1-B boundary Iron (Internal) material Chemistry 10 20 Pressure Gray Cast Fuel oil Loss of Selective 51 Strainer (body) boury Iron (Intel oil Leaching N/A N/A G

boundary Iron (Internal) material Inspection Pressure Gray Cast Air-indoor Loss of External 3.3.1-52 Strainer (body)

Prsunare ry In uncontrolled material Surfaces VII.I-8 58 A

5)boundary Iron (External)

Monitoring Chemistry 53 Strainer (body)

Pressure Steel Fuel oil Loss of Program VII.H1-3.3.1-A boundary (Internal) material Effectiveness 10 20 Inspection 54 Strainer (body Pressure Steel Fuel oil Loss of Fuel Oil VII.H1-3.3.1-B I

I

)

boundary ItIl(Internal) material Chemistry 10 20 Aging Management Review Results Page 3.3-212 jAmendment 31 -.

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-22 Aging Management Review Results -Fire Protection System Aging Effect Aging NUREG-Row Component Intended Material Environment Requiring Management Volume 1 Item Notes No.

Type Function(s)

Management Program 2 Item I Item Exhaust Pressure Air-outdoor Loss of Diesel-Driven3.3.1-E 9

Silencer boundary Steel (Internal) material Fire Pumps VII.H2-2 18 0322 Inspection Exhaust Pressure Air-outdoor Loss of External 3.3.1-10 Silencer boundary (External) material Surfaces VII.1-9 58A Monitoring 11 Flame Arrestor Pressure Aluminum Air-outdoor None None N/A N/A G

boundary Alloy (Internal) 0332 12 Flame Arrestor Pressure Aluminum Air-outdoor None None N/A N/A G

boundary Alloy (External) 0332 13 Flexible Pressure Fuel oil None None N/A N/A G

Connection boundary (Internal) 14 Flexible Pressure Elastomer Lubricating None None N/A N/A G

Connection boundary oil (Internal)

Flexible Pressure Raw water 3.3.1-15 Cneto bonay Elastomer (Itra)

None None VII.C1-1I Connection boundary (internal) 75 Ai-norFlexible 331 16 Flexible Pressure Elastomer Andor Hardening and Connection VII.F1-7

.3.1-Connection boundary uncontrolled loss of strength Inspection 11 (External)

Iseto Aging Management Review Results Page 3.3-234

~jaf*.ey 2010 Thmendent 3

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-42 Aging Management Review Results - Standby Service Water System NUREG-Aging Effect Aging Notes Row Component Intended Material Environment Requiring Management 1801 Table INotes No.

Type Function(s)

Maaeet Porm Volume Item Management Program 2 Item Heat Exchanger 26 (tubes and Lubricating oil Reduction in Lubricating Oil N/A N/A H

fittings) (SW-P-Heat transfer Copper Alloy (External) heat transfer Inspection 1A/1B oil cooler)

Heat Exchanger (tubes and Pressure Raw water Loss of Open-Cycle VII.C1-3 3.3.1-fittings) (SW-P-boundary Copper Alloy (Internal) material Cooling Water 82 1A/1B oil cooler)

Heat Exchanger 28 (tubes and Pressure Copper Alloy Lubricating oil None None VII.C1-8 3.3.1-fittings) (SW-P-boundary (External) 26 0311 1A/1B oil cooler)

Pressure Stainless Air-outdoor 29 Nozzle budr Ste(Iena)

None None N/A N/A G

boundary Steel (internal) 0332 30 Nozzle Pressure Stainless Raw water Loss of Open-Cycle VII.C1-15 3.3.1-B boundary Steel (Internal) material Cooling Water 79 31 Nozzle Pressure Stainless Air-outdoor None N/A N/A G

boundary Steel (External) 0332 32 Nozzle Spray Stainless Air-outdoor None None N/A N/A G

Steel (internal) 0332 Aging Management Review Results Page 3.3-381

-jaRwaFy 204 0

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-42 Aging Management Review Results - Standby Service Water System NUREG-Row Component Intended Aging Effect Aging 1801 Table 1 No.

Type Function(s)

Material Environment Requiring Management Volume Item Notes Management Program 2 Item 33 Stainless Raw water Loss of Open-Cycle VIILC1-15 3.3.1-B Nozzle Spray Steel (Internal) material Cooling Water 79 34 Orifice Pressure Stainless Raw water Loss of Open-Cycle VII.C1-15 3.3.1-B boundary Steel (Internal) material Cooling Water 79 Pressure Stainless Air-indoor 3.3.1-35 Orifice uncontrolled None None VII.J-15 A

boundary Steel (External) 36 Orifice Pressure Stainless Air-outdoor None None N/A N/A G

boundary Steel (External) 0332 Pressure Stainless Condensation Loss of External 3.3.1-37 Orifice boundary Steel (External) material Surfaces VII.F2-1 27 E

Monitoring 38 Orifice Pressure Steel Raw water Loss of Open-Cycle VI1.C1-19 3.3.1-B boundary (Internal) material Cooling Water 76 Pressure Air-indoor Loss of External 3.3.1-39 Orifice Steel uncontrolled Surfaces VII.I-8 58A (External material Monitoring boundaryEExternal Pressure Condensation Loss of External 3.3.1-40 Orifice Steel (External) material Surfaces VII.-11 58A boundary(External) mtrMonitoring 58 41 Orifice Structural Stainless Air-outdoor None None N/A N/A G

integrity Steel (Internal) 0332 Aging Management Review Results Page 3.3-382 Je~e.y-a04O Aging Management Review Results Page 3.3-382 I

- januaFy 2019 jAmendment 31

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-42 Aging Management Review Results - Standby Service Water System Aging Effect Aging NUREG-Row Component Intended Aging Effect agint 1801 Table I No.

Type Function(s)

Material Environment Requiring Management Volume Item Notes Management Program 2 Item 42 Orifice Structural Stainless Raw water Loss of Open-Cycle VI1.C1-15 3.3.1-B integrity Steel (Internal) material Cooling Water 79 43 Orifice Structural Stainless Air-outdoor None None N/A N/A G

integrity Steel (External) 0332 44 Orifice Throttling Stainless Raw water Loss of Open-Cycle VII.C115 3.3.1-B Steel (Internal) material Cooling Water 79 45 Steel Raw water Loss of Open-Cycle VII.C1-19 3.3.1-B 45 Orifice Throtling S(Internal) material Cooling Water 76 Air-indoor Pressure Stainless 3.3.1-A 46 Piping boundary Steel uncontrolled None None VII.J-15 94 0306 (Internal) 94_0306 47 Piping Pressure Stainless Air-outdoor None None N/A N/A G

Piping boundary Steel (Internal) 0332 48 Piping Pressure Stainless Raw water Loss of Open-Cycle VII.C1-15 3.3.1-B boundary Steel (Internal) material Cooling Water 79 Pressure Stainless Air-indoor 3.3.1-49 Piping boundary Steel uncontrolled None None VII.J-15 A

49 Ppngbudry Sel(External) 94--__

50 Piping Pressure Stainless Air-outdoor None None N/A N/A G

boundary Steel (External)

Aging Management Review Results Page 3.3-383 jernuaFy 2910

_'A-mcn 25n M2ýt f

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-42 Aging Management Review Results - Standby Service Water System NUREG-Row Component Intended Aging Effect Aging 1801 Table I No.

Type Function(s)

Material Environment Requiring Management Volume Item Notes Management Program 2 Item Structural Stainless Air-indoor 3.3.1-A 60 Piping integrity Steel uncontrolled None None VII.J-15 94 0306 60 ipnginegit Se(Internal)

Piping Structural Stainless Air-outdoor 61 Pipinintegrity Steel (Internal)

None None N/A N/A G

0332 62 Piping Structural Stainless Raw water Loss of Open-Cycle V1.Cl1-15 3.3.1-B integrity Steel (Internal) material Cooling Water 79 Structural Stainless Air-indoor3.3.1-63 Piping uncontrolled None None VII.J-15

3.

A 63 Piping integrity Steel (External) 94 64 Piping Structural Stainless Air-outdoor None None N/A N/A G

integrity Steel (External) 0332 Structural Air-indoor Loss of External 3.3.1-C 65 Piping integrity Steel uncontrolled Surfaces VII.I-8 58 0302 (Internal) material Monitoring Structural Air-outdoor Loss of External 3.3.1-C 66 Piping integrity Steel (Internal) material Surfaces Vi1.n-9 58 0324

__________Monitoring 67 Piping Structural Steel Raw water Loss of Open-Cycle VII.C1-19 3.3.1-B integrity (Internal) material Cooling Water 76 Structural Air-indoor Loss of External 3.3.1-Piping integrity Steel uncontrolled material Surfaces VII.I-8 58A (External)

Monitoring Aging Management Review Results Page 3.3-385 Aging Management Review Results Page 3.3-385

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-42 Aging Management Review Results - Standby Service Water System n

ENUREG-Row Component Intended Aging Effect Aging 1801 Table 1 No.

Type Function(s)

Material Environment Requiring Management Volume Item Notes

_ Management Program 2 Item 87 Strainer Filtration Stainless Raw water Loss of Open-Cycle VII.C1-15 3.3.1-B (screen)

Steel (External) material Cooling Water 79 88 Tubing Pressure Stainless Raw water Loss of Open-Cycle VIlC115 3.3.1-B boundary Steel (Internal) material Cooling Water 79 Pressure Stainless Air-indoor 3.3.1-89 Tubing uncontrolled None None VII.J-15 A

8 Tuigboundary Steel (External) 94 (Externa)

___External_

Pressure Stainless Condensation Loss of External3.3.1-90 TbingSurfaces VII.F2-1 331 90 Tubing boundary Steel (External) material Monitoring 27 Air-indoor Structural Stainless 3.3.1-A 91 Tubing integrity Steel uncontrolled None None VII.J-15 94 0306 (Internal) 92 Tubing Structural Stainless Raw water Loss of Open-Cycle VllC115 3.3.1-B integrity Steel (Internal) material Cooling Water 79 Structural Stainless Air-indoor3.3.1-93 Tubing uncontrolled None None VII.J-15

3.

A 9 Tuigintegrity Steel (External) 9 (External)

Structural Stainless Condensation Loss of External 3.3.1-Surfaces VII.F2-1 2

94 Tubing integrity Steel (External) material Monitoring

_____27 95 ValveBoPressure Stainless Air-outdoor None N/A N/A G

Valve Body boundary Steel (Internal)

None

__________0332 Aging Management Review Results Page 3.3-388 Je4~iefy-2O4O Aging Management Review Results Page 3.3-388 janwaFy 2010 jAmendment 31

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-42 Aging Management Review Results - Standby Service Water System Aging Effect Aging NUREG-Row Component Intended Aging Mangint 1801 Table I No.

Type Function(s)

Material Environment Requiring Management Volume Item Notes Management Program 2 Item 96 Valve Body Pressure Stainless Raw water Loss of Open-Cycle VII.C115 3.3.1-B boundary Steel (Internal) material Cooling Water 79 0331 Pressure Stainless Air-indoor 97 Valve Body uncontrolled None None VII.J-15 3.3.1-A y boundary Steel (External) 98 Valve Body Pressure Stainless Air-outdoor None None N/A N/A G

boundary Steel (External)

NoneNone 0332 Pressure Stainless Condensation Loss of External 3.3.1-E 99 Valve Body boundary Steel (External) material Monitoring 27 Pressure Air-outdoor Loss of External 3.3.1-C 100 Valve Body boundary Steel (Internal) material Surfaces ViI.1-9 58 0324 Monitoring 101 Valve Bod Pressure Steel Raw water Loss of Open-Cycle VI1.C1-19 3.3.1-B y

boundary (Internal) material Cooling Water 76 Pressure Air-indoor Loss of External 3.3.1-Pressunry Steel uncontrolled s

Suorfaces Vn.l-8 102 Valve Body boundary (External) material Monitoring 58 Pressure Air-outdoor Loss of External 3.3.1-103ealveBod Steel Surfaces VII.I-9 331 103 Valve Body boundary (External) material Monitoring 58 Pressure Condensation Loss of External 3.3.1-A 104 Valve Body boundary (External) material Surfaces ViI.n-1 1 58

________Monitoring Aging Management Review Results Page 3.3-389 1

7" J1 a RMIXn2OQI iAmendment 31

[Am"Imcn 2

Ge4te-ri Notes Table 3.3.2-xx Columbia Generating Station License Renewal Application Technical Information Plant-Specific Notes:

0315 The BWR Water Chemistry Program and Chemistry Program Effectiveness Inspection will manage loss of material of components submerged in the suppression pool and subject to a treated water environment.

0316 The fire protection diesel engine coolant (antifreeze) is evaluated as Raw Water.

0317 The Fire Water Program also manages loss of material due to selective leaching of fire sprinker system spray nozzles that are normally exposed to a raw water (internal) environment. The copper alloy spray nozzles are inspected or replaced in accordance with the Fire Water Program; the inspection includes detection of selective leaching.

0318 For conservatism, it is assumed that ammonia or ammonium compounds are present in the raw water environment as a by-product of organic decay, as a by-product of MIC, or possibly from fertilizers.

0319 Subject component is exposed to reactor closed cooling (RCC) water.

0320 Subject component has an air-water interface that constitutes an agressive environment.

0321 Subject component is exposed to plant service water (TSW).

0322 Environment is predominantly outdoor air with infrequent, and for short duration, exposure to diesel exhaust.

0323 The internal environment between the outer and inner vessels of CN-TK-1 is conservatively evaluated as air instead of as a vacuum. Since the external surface is exposed to the more aggressive outdoor air environment, aging effects will occur on the external surface before they occur on the internal surface.

0324 The aging effect determination for the Air-outdoor (Internal) environment is the same as the NUREG-1801 determination for an Air-outdoor (External) environment because the material is the same and the internal environment is equivalent to the external environment evaluated in the NUREG-1801 item. Monitoring of the external surface condition will be used to characterize the aging effects on the internal surfaces.

Insert A shown Insert B shown on on page 3.3-400a page 3.3-400b Aging Management Review Results Page 3.3-400 JAmendment 31 enn

Columbia Generating Station License Renewal Application Technical Information Insert B to LRA Page 3.3-400 0332 Columbia will conservatively manage subject components with the External Surfaces Monitoring Program.

0333 The pumps DO-P-1A, 1B, and 2 are located inside of the diesel storage tanks which are vented outdoor air and the flame arrester in the vent line restricts the movement of air and airborne contaminants into the storage tanks.

Aging Management Review Results Page 3.3-400b Amendment 31 Aging Management Review Results Page 3.3-400b Amendment 31

Columbia Generating Station License Renewal Application Technical Information Table 3.4.2-3 Aging Management Review Results - Condensate (Nuclear) System Aging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801 Table Notes No.

Type Function(s)

Management Program Volume I Item 2 Item Cast Pump Casing Structural Austenitic Condensation Loss of External Surfaces N/A N/A G

51 (COND-P-3, integrity Stainless (External) material Monitoring 4, 5)

Steel 52 Tank (COND-Pressure Steel Air-outdoor Loss of External Surfaces VIII.H-8 3.4.1-C TK-1A, 1B) boundary (Internal) material Monitoring 28 0411 Tank (COND-Pressure Moist air Loss of Supplemental 53Piping/Tank N/A N/A G

53 TK-1A, 1B) boundary Steel (Internal) material Inspection 54 Tank (COND-Pressure Steel Treated water Loss of BWR Water VIII.E-40 3.4.1-A TK-1A, 1B) boundary (Internal) material Chemistry 06 Tank (COND-Pressure Treated water Loss of Chemistry Program 3.4.1-A

)

Steel Effectiveness VIII.E-40 061 A

TK-1A, 113) boundary (Internal) material Inspection 06 56 Tank (COND-Pressure Steel Air-outdoor Loss of Aboveground Steel VIII.E-39 3.4.1-B TK-1A, 1B) boundary (External) material Tanks Inspection 20 0409 57 Tank (COND-Pressure Steel Air-outdoor Loss of External Surfaces VIII.H-8 3.4.1-A TK-1A, 1 B) boundary (External) material Monitoring 28 58 Tubing Pressure Stainless Air-outdoor None None N/A N/A G

boundary Steel (Internal) 0413 59 Pressure Stainless Treated water Loss of BWR Water VIIIE29 3.4.1-A 5 Tuing boundary Steel (Internal) material Chemistry 16 Aging Management Review Results Page 3.4-50 j~enmnt_3_1_-ý,i,,,

11

Columbia Generating Station License Renewal Application Technical Information Table 3.4.2-3 Aging Management Review Results - Condensate (Nuclear) System Aging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801 Table Notes No.

Type Function(s)

Management Program Volume 1 Item 2 Item Pressure Stainless Treated water Loss of Chemistry Program 341-60 Tubing Effectiveness VIII.E-29 16 A

60 T gboundary Steel (internal) material Inspection Pressure Stainless Air-indoor3.4.1-61 Tubing uncontrolled None None VIIII-3.10 41 A

61 T g boundary Steel (External) 41 62 Tubing Pressure Stainless Air-outdoor None None N/A N/A G

boundary Steel (External) 0413 63 Tb Pressure Stainless Condensation Loss of External Surfaces VIIF21 3.3.1-E uing boundary Steel (External) material Monitoring 27 64 Tb Structural Stainless Treated water Loss of BWR Water VIlE29 3.4.1-A uing integrity Steel (Internal) material Chemistry 16 Structural Stainless Treated water Loss of Chemistry Program 3.4.1-65 Tubing integrity Steel (Internal) material Effectiveness VIII.E-29 16 A

Inspection Structural Stainless Air-indoor 3.4.1-66 Tubing integrity Steel uncontrolled None None VIII.I-10 41 A

(External) 67 Tubing Structural Stainless Condensation Loss of External Surfaces N/A N/A G

integrity Steel (External) material Monitoring 68 Valve Body Pressure Stainless Air-outdoor None None N/A N/A G

boundary Steel (Internal) 0413 Aging Management Review Results Page 3.4-51 jAmendment 31

Columbia Generating Station License Renewal Application Technical Information Table 3.4.2-3 Aging Management Review Results - Condensate (Nuclear) System Aging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801 Table Notes No.

Type Function(s)

Management Program Volume I Item 2 Item Pressure Stainless Air-outdoor None None N/A N/A G

69 Valve Body boundary Steel (External) 10413 Pressure Air-indoor Loss of External Surfaces 3.4.1-C 70 Valve Body boundary Steel uncontrolled material Monitoring VIII.H-7 28 0404 (Internal) 71 Valve Bod Pressure Steel Treated water Loss of BWR Water VIII.E-33 3.4.1-A y

boundary (Internal) material Chemistry 04 Pressure Treated water Loss of Chemistry Program 3.4.1-72 Valve Body boundary Steel (Internal) material Effectiveness VIII.E-33 04 A

Inspection Pressure Air-indoor Loss of External Surfaces 3.4.1-73 Valve Body boundary Steel uncontrolled VIII.H-7 A

(External) material Monitoring 74 Valve Bod Pressure Steel Air-outdoor Loss of External Surfaces VIII.H-8 3.4.1-A y

boundary (External) material Monitoring 28 75 Valve Body Pressure Steel Condensation Loss of External Surfaces VIII.H-10 3.4.1-boundary (External) material Monitoring 28 76 Valve B Structural Stainless Treated water Loss of BWR Water VIIIE29 3.4.1-A ody integrity Steel (Internal) material Chemistry 16 Structural Stainless Treated water Loss of Chemistry Program 3.4.1-Struca S

s Be wEffectiveness VIII.E-29 16 A

77 Valve Body integrity Steel (Internal) material Inspection 16 Aging Management Review Results Page 3.4-52 j~enmnt 31-7

Plant Specific I Generic Notes Table 3.4.2-xx Columbia Generating Station License Renewal Application Technical Information Plant-Specific Notes:

0404 The aging effect determination for the Air-indoor uncontrolled (Internal) environment is the same as the NUREG-1 801 determination for an Air-indoor uncontrolled (External) environment because the material is the same and the internal environment is equivalent to the external environment evaluated in the NUREG-1801 item Monitoring of the external surface condition will be used to characterize the aging effects on the internal surfaces.

0405 Bolting associated with the quenchers is stainless steel and located in the suppression pool.

0406 This steel component has an external surface temperature > 212 OF. Therefore, the surface is dry and general corrosion is not an aging effect requiring management; there are also no other aging effects requiring management.

0407 The Bolting Integrity Program will also manage cracking for the carbon and low-alloy (steel) bolting at the base and foundation of the CSTs due to potential for ponding or pooling of water.

0408 The Buried Piping and Tanks Inspection Program will manage loss of material for the carbon steel (steel) piping from the CSTs that is enclosed in guard pipe and buried.

0409 The Aboveground Steel Tanks Inspection will detect and characterize loss of material at the base of each CST in contact with the tank foundation.

The aging effect determination for the Air-indoor uncontrolled (Internal) environment is the same as the NUREG-1 801 0410 determination for an Air-indoor uncontrolled (External) environment because the material is the same and the internal environment is equivalent to the external environment evaluated in the NUREG-1 801 item There are no aging effects requiring management.

The aging effect determination for the Air-outdoor (Internal) environment is the same as the NUREG-1 801 determination for an 0411 Air-outdoor (External) environment because the material is the same and the internal environment is equivalent to the external environment evaluated in the NUREG-1801 item. Monitoring of the external surface condition will be used to characterize the aging effects on the internal surfaces.

SAdd:

0412 - The normal environment of the Sealing Steam System is evaluated as a steam environment from when the steam evaporator relief valves are actuated.

Add:

0413 - Columbia will conservatively manage subject components with the External Surfaces Monitoring Program.

Aging Management Review Results Page 3.4-78 I A ---

,4--

janueFy 2014D Amendment 31

Columbia Generating Station License Renewal Application Technical Information A.1.3.7 Other Plant-Specific Time-Limited Aging Analyses The TLAAs that do not fit into any of the previous major categories are evaluated below.

A.1.3.7.1 Reactor Vessel Shell Indications Two indications in the reactor vessel shell were identified using ultrasonic inspection methods during the 2005 inservice inspections. The indications were present in past inservice inspection examinations, but became rejectable under current ASME Section XI, IWB-3610 requirements. The rejected indications were evaluated and determined to be acceptable for continued service without repair, as reported to the NRC.

The indications were evaluated per the guidelines of ASME Section XI, IWB-3610, which include acceptance criteria based on the applied stress intensity factors, using conservative assumptions in the applied stresses to determine the stress intensity factors for comparison to Code allowables.

This conservative evaluation calculated a fatigue crack growth at the end of 33.1 EFPY vessel service life that is insignificant in comparison to the bounding initial crack size. It also determined that the applied stress intensity factor is well below the allowable stress intensity factor.

The calculation is based on time-limited assumptions of neutron fluence and SRV blowdown cycles for 40 years. While it is not expected that the applied stress intensity factor will exceed the allowable fracture toughness during the period of extended operation, cracking near the subject reactor vessel welds is managed by the Inservice Inspection (ISI) Program.

<----I._

nsert A from page Disposition A-40a Cracking of the reactor vessel shell near welds BG and BM will be adequately managed through the period of extended operation by the Inservice Inspection (ISI) Program.

A.1.3.7.2 Sacrificial Shield Wall FSAR Section 3.8.3.6 provides a value of neutron fluence for the outside face of the sacrificial shield wall that is based on 40 years of plant operation. Projections done for 60 years of operation, including increase in fluence due to power uprate, determined that the estimated neutron fluence on the sacrificial shield wall will remain below the threshold for neutron damage of concrete and reinforcing steel.

Therefore, the sacrificial shield wall can be expected to perform its radiation shielding function through the period of extended operation.

Disposition The TLAA associated with the sacrificial shield wall fluence has been projected to the end of the period of extended operation.

Final Safety Analysis Report Supplement Page A-40 ja,'..ny-2 n

JAmendment 31 ýý

Columbia Generating Station License Renewal Application Technical Information Insert A:

Columbia will re-evaluate the indication based on the results of the 2015 inspection and either project this analysis through the period of extended operation or continue augmented inspections as required by the ASME code.

Final Safety Analysis Report Supplement Page A-40a Amendment 31 Final Safety Analysis Report Supplement Page A-40a Amendment 31

Columbia Generating Station License Renewal Application Technical Information Table C-11 BWRVIP-74-A BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines for License Renewal Applicant Action Item Text Plant-Specific Response (12) As indicated in the staff's March 7, 2000 The projected RTNDT of Columbia's limiting letter to Carl Terry, a LR applicant shall monitor axial beltline weld at the end of the axial beltline weld embrittlement. One extended period of operation is less than acceptable method is to determine the mean the values specified in Table 1 of the FSER RTNDT of the limiting axial beltline weld at the for BWRVIP-74. Details of the evaluation end of the extended period of operation is less are in Section 4.2.6 of the LRA.

than the values specified in Table 1 of this FSER.

(13) The Charpy USE, P-T limit, circumferential Columbia used fluence methodology that weld and axial weld RPV integrity evaluations was approved by the NRC based on the are all dependent upon the neutron fluence.

methodology following the guidance in The applicant may perform neutron fluence Regulatory Guide (RG) 1.190. See Section calculations using a staff approved 4.2.1 of the LRA.

methodology or may submit the methodology for staff review. If the applicant performs the neutron fluence calculation using a methodology previously approved by the staff, the applicant should identify the NRC letter that approved the methodology.

(14) Components that have indications that Columbia has two indications that have have been previously analytically evaluated in been previously evaluated (one analysis) in accordance with Subsection IWB-3600 of accordance with Subsection IWB-3600 of Section Xl to the ASME Code until the end of Section XI to the ASME Code until the end the 40-year service period shall be re-of the 40-year service period. These two evaluated for the 60 year service period

... ct.r Y....l shell l!ndiations w...

corresponding to the LR term.

,,aluatd for the pei.d of extendcd l

cpcr-tien andracking of these indications will be managed by the Inservice Inspection (ISI) Program. Details of the evaluation are in Section 4.7.1 of the LRA.

Response to BWRVIP Applicant Action Items Page C-30 Ji.......

,-2n4 2

JAmendment 31