GO2-10-094, License Renewal Application First Annual Update

License Renewal Application First Annual Update

ML102090559
Person / Time
Site:	Columbia
Issue date:	07/16/2010
From:	Gambhir S Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-10-094
Download: ML102090559 (440)

Text

EN ER GY ENERGYSudesh S ColumbiaP.O.

K Gambhir Generating Station Box 968, PE04 Richland, WA 99352-0968 Ph. 509.377.8313 I F. 509.377.2354 sgambhir@ energy-northwest.com July 16, 2010 G02-10-094 10 CFR 54.17 10 CFR 54.21 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE

Reference:

Letter, G02-1 0-11, dated January 19, 2010, WS Oxenford (Energy Northwest) to NRC, "License Renewal Application"

Dear Sir or Madam:

In the reference, Energy Northwest requested the renewal of the operating license for Columbia Generating Station (Columbia). The License Renewal Rule, 10 CFR 54.21 (b), requires that each year following submittal of a license renewal application (LRA), and at least 3 months before scheduled completion of the NRC review, an amendment to the renewal application must be submitted that identifies any change to the current licensing basis (CLB) of the facility that materially affects the content of the LRA.

In accordance with this requirement, Energy Northwest performed a review of CLB changes after the LRA reference freeze date that formed the basis for the submittal of LRA until January 2010 to determine if any sections of the LRA were affected by these changes. This update also includes a review of plant specific operating experience for the same time frame. As another element of the review, Energy Northwest personnel walked down areas of Columbia to validate scoping and screening decisions reached early in the License Renewal Project. During the walkdown, the Energy Northwest License Renewal team identified systems and components that should have been included in the original scope for license renewal. The issues identified during the walkdown were entered into the corrective action program.

Ao 5

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 2 As a result, Energy Northwest has determined that several changes to the LRA are required. A number of these changes are related to a new material and environment combination of stainless steel exposed to soil was identified and the Buried Piping and Tanks Inspection Program (XI.M34) has been revised to manage the aging effects.

However, no new aging effects have been identified and no new aging management programs are required. Energy Northwest has determined that the LRA, as amended, continues to provide the appropriate administrative, technical, and environmental information sufficient to support the findings required by 10 CFR 54.29. Actions have been identified to manage the effects of aging on the structures and components subject to aging management review, such that the intended functions will be maintained consistent with the current licensing basis during the Columbia period of extended operation (PEO). contains Amendment 1 to the LRA. As discussed with the NRC License Renewal Project Manager, Ms. Evelyn Gettys, Energy Northwest is providing marked-up pages and new pages to add to the LRA, rather than clean pages with the changes incorporated into the text.

As was provided in the original application, the revised Boundary Drawings are provided in Enclosure 2 as information only to aid the reviewers and are not part of the LRA submittal.

Some of the changes to the scoping, aging management review results, or an aging management program have resulted in changed pages in several LRA sections. To facilitate the review, the change summaries, categorized by change type and numbered, are followed by the LRA Amendment 1 pages (an additional copy of the same pages provided in Enclosure 1). No changes were required because of facility changes. The summaries are divided into 4 groups.

Editorial (E) changes are in Attachment 1.

Operating (0) experience update changes are in Attachment 2.

Reference (R) update review changes are in Attachment 3.

Walkdown (W) result changes are in Attachment 4.

There are no new regulatory commitments contained in the LRA Amendment.

Should you have any questions concerning this submittal, please contact Abbas Mostala, License Renewal Project Manager, at 509-377-4197.

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 3 In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated Washington State Official.

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

Vice President, Technical Services

Enclosures:

1. License Renewal Application, Amendment 1

2. For information only - Revised boundary drawings (3 copies)

Attachments:

1. Summary of Editorial changes

2. Summary of Operating experience update changes

3. Summary of Reference update review changes

4. Summary of Walkdown result changes cc: NRC Region IVAdministrator NRC Senior Resident Inspector/988C EJ Leeds - NRC NRR RN Sherman - BPA/1 399 BE Holian - NRC NRR WA Horin - Winston & Strawn EH Gettys - NRC NRR (5 copies) EFSEC Manager NRC NRR Project Manager RR Cowley - WDOH

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 1 of 1 Summary of Editorial changes Change Summary Changed or new Number pages Corrected plural "criteria" to "criterion" 2.5-3 Noted that ISG-02, "Staff Guidance on Scoping of Equipment 2 Relied on to Meet the Requirements of the Station Blackout (SBO) 2.5-8 Rule (10 CFR 50.63) for License Renewal," is historical because the document was incorporated into NUREG 1801, Revision 1.

Corrected "going" to "ongoing" in the commitment related to 3 Masonry Wall Inspection. A-56 Revised description of the Operating Experience section of the 4 Flow-Accelerated Corrosion (FAC) Program to delete the B-120 subjective words "recently" and "current."

Revised description of the Operating Experience section of the 5 Structures Monitoring Program to delete the subjective word B-196 "recent." Corrected "documents" to "documented."

Added the acronym (DOT) following the first use of Department of 49 Transportation. Acronym was used in following sentences without 2.3-96 prior definition

Co1umbi.Ge~erating Station License Renewal Application

______________

______________ _______ TCchnical ln frmatiOn 2ZS. Elimina ion of Componen* Cornmodity: c~ups wit h no Li ceis.eRei e~waI intended unctions No geno,,c Stri a. and l&C -nmponeat-onrodity groups we eemmated from AMR at Columbia;in accordance *With the direction of 10 CFR 54.2i(a)(1)(i) regarding license renewal intended fbPitions. Hdweve id ividual componentswithin c lomponent and commodt grq-up may still be eliminate from AMR based on this.

2.5A Appiication of Screening Criteria 10 CFR.5421(aP)(I){. to lectri cal and l&c Component Commodity*Groups The next :step in the: electrical screening process is to' sewega'e "long'liv'ed" elecir~idal comPonents from thosethat are subjetA `to replacement based on a qu!alified life or

'a specified time schedule. In general, components that .re screened out of license :renewal coisideret.on bas'ed on' the. oigiiv~ed" criterion are. thoseI included in the plant environmenta qualification (EQ) program:. Electrical omponent, included in the plant EQ pOrogram haye:.qualified J-Hes nd are replaced based on their qualified life determination. Therefore, environmentally qualified components do not' meet the "long-ived" criterion of, 10 CFR, 54221#(a)(i)(ii) and are excluded from further evaluation.

EQ evaluations that meet the criteria for a time-limited aging analysis are addressed in Se~tion 4.4.

154,1 ElIctrial Porlions ,of E ectI nI l&C Penetration Asmbies Th electrcal penetration assewmby commodity group iS excluded rom AMR because all of he Colunbia. electrical penetrotos are part of the EQ pIogram. The electrical penetration assemblies are addrcssed by various EQ enalyses. Therefore, the electrical penetration assemblies ate not. subject to AMR at.. Coimbia.because they do not meet the long-lived criterion of 10 CFR.54.21(a)(1)(ii).

2.5,4.2 Insulated Cables and Connections in theEQ-Program The insulated cables and connections that are included in the plant EQ program have quaiualified life det-mination Therefore, insulated cables and connections that are included in the-EQ progran'do no~ meet the.

• • ong.]ivcjdscrit~erion of 10 CFR 54,21(a;*(1)(ii) and are not0 subj~ect to AMR' 5'.5 E~ctic! an' l,&C Compo ne 'Cormmod~it:yGroups Requli:*ing an Aging Pian gement Review The' electrical and &C 'component commodity groups that require AMP are listed in,

'Fable 2.5*i along with their intended functions. initended:functibons are defined in Table 2.0:-1, Table 3.6.2-1, Aging. Management Review Results - Electrical and I&C Cbmponents, provides the results of the AMR.

Scoping and Screening Results. Page 2,5-3 J Ž Amendment 1

Columbia.Generating Statioh License:,Renewal Application TechOnial Information The function of highvoltage insulators is to insulate and. dupport an electrical conduptor.z High: voltage, insulator,are. passive, longdiived components .... Therefore, high, voltage insulators meetAthe crtera of110 CFR.54.21(a)(1) and are :subject to an AMR..

2.5.6 Evaluation Boua¢es 2.56.1 Syst rn valuation.Boun aries The evalUation boundaes for the electrical and I&C sys ems within the scope of license renewal include :the ent.e; system. Electrical and IMC !component types within :thee boundaries, of in-scope rmechanical systems are also included within the electrical and I&C.evaluationnboundaries.

2.5.6.2 Station Blackou't- Evaluation Boundaries The, License .Renewal Rule, 10 CFR 54,4(a)(3), requires thati plarnt .SSCs. relied on for compliance With the NRC regulation on st'ation blackout (SBO), 10OCFR 50.63, be included. in the 'svope of license renewal.. In April 21002., the NRC issued'. additional.

guidance 'on the (icense' renewal) scOping of equiphnnt relied, on to meet! the requirements of :10 CFRi 50:63F in the form o. an Interim Staff Guidance document.(ISGO 02)4 Subse uentflv thistuidance was incorporated into NU REG.801, ReviSion s itisovnIRte ntePitdaf .pvie hl NULGing ins 1erqirt of Li7G' re02e,.a InR the gteidanic provifdedtin NUREGS1800, the insih'tsso.f 1G-02,:arid the urrentieln i cumentatin, the SSG licenste renesc!.oping boudaray was established Lnd th e iinscopen effSSCs 580- were identifieýd. The following paragraphs describe the'. 580 license renewal .off:

site power recovery paths for Columbia.

Two independent offsite power :sources areý supplied to Columbia via start-up:

transformer:vETR-S abrd back-up"tran sformer .E.T.-TR-B.

The, 230-kV grid is: connected to the. onsite: power,.system by breaker E-0.-TRS: (also known as A$09).at the Ashe.substation then via overhead line to ttansform&rtrE-TR-S located in the Columbiat ansformervyard. The distribution from the star8-up transformer (E7.TR-S) to the Class .E buses is through the non-segreg ted bis to witchgear SM-i and SM-3. Each of these SR switchgear feed, to the Class! , E wi for Division fhgear 1 and Division 2(SM7 and SMA8, respectively).

The ' 15-kV grid ;ionne ced to the onsi te powe.r ource by* oil. circuit breaker -CB*

TRB located in Clumbia transformer tthe. yard The output of breaker E.-CB-TRB is.

directly tied by swit"hyard bus tof back-up, transformer EATR{B, vhich isz. then directly connected ,by cable: (routed underground and then in tray) to the Class 1IE switchgear for Division 1 and Division. 2 (SMi7 arid:SM-8: respectively)..,

Scoping and Screening Results Page2Z5-8%a"..'a

• Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table A-1 Columbia License Renewal Commitments FSAR Enhancement Commitment Supplement or Item Number Location Implementation (LRA App. A) Schedule

38) Masonry Wall The Masonry Wall Inspection is an existing program that will be A.1.2.38 Enhancement Inspection continued for the period of extended operation, with the following prior to the period enhancements: of extended

• Specify that for each masonry wall, the extent of observed operation.

masonry cracking or degradation of steel edge supports and Then geing.

bracing are evaluated to ensure that the current evaluation basis is still valid. Corrective action is required if the extent of masonry cracking or steel degradation is sufficient to invalidate the longoing I evaluation basis. An option is to develop a new evaluation basis that accounts for the degraded condition of the wall (i.e.,

acceptance by further evaluation).

39) Material The Material Handling System Inspection Program is an existing A,1.2.39 Efthaceement-Handling program that will be continued for the period of extended operation-_ pri to the-pciord System wit lnean t of-extended-Inspection opefatai".

Program inspected for corrosion. Then ongoing.

Amendment 1 Fina Saety nalsis epot Supleent ageA-5 Final Safety Analysis Report Supplement Page A-56

B2.28 Flow-Accelerated Corrosion (FAC) Program Columbia Generating Station License Renewal Application Technical Information periodically reported, including material conditions. Industry operating experience has been, and continues to be, evaluated for impact to Columbia and for possible program enhancement. For example, based on review of INPO operating experience 14865, the program was enhanced to require evaluation of replacements for future inspection.

Periodic self assessments are also conducted. Gaps identified during the most recent self assessment have all been closed; and the FAC program plan was -eatly updated, with the-e et-revision addressing all issues identified by the self assessment. In the last benchmark assessment, performed in March 2007, no issues or weaknesses were identified.

As a result, Columbia has programs and procedures in place, with operating experience demonstrating that the FAC Program is capable of detecting and managing loss of material due to FAC for susceptible components, and will continue to be an effective aging management program for the period of extended operation.

A review of program health reports, recent self-assessment reports, and related condition reports, demonstrates that the FAC Program is effective in detecting loss of material due to FAC for susceptible components, and defining the corrective actions (e.g., repair or replacement) necessary to assure their continued operation in accordance with design requirements.

Conclusion The FAC Program will detect and manage loss of material due to FAC for susceptible components. The FAC Program, with the required enhancements, provides reasonable assurance that the aging effects will be managed such that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Page B-120 Janudry 2010 Aging Aging Management Programs Management Programs Page B- 120 __Jmnmrrzýý jAmendniýýt 1 7

..........

.

B2.50 Structures Monitoring Program Columbia Generating Station License Renewal Application Technical Information of whether failures were maintenance preventable. A review of the Maintenance Rule program periodic assessments did not identify any age-related functional failures related to structures. Two non-age related functional failures identified were that the Reactor Building crane was parked without the tornado latches installed and a 10 CFR 21 notice from Whiting Crane Corporation regarding a weld defect on the Reactor Building crane main trolley. I-Replace with "documented" A feeefA condition report deeunme#s a surface flaw noted in the concrete of the west exterior wall of the Reactor Building. The surface flaw appears to have existed for a significant period of time with no apparent adverse effects on secondary containment or the Reactor Building structure. Add Insert A on page B-196a NRC Unresolved Item (URI)05000397/2007005-02 was issued in February of 2008.

This URI identified that Columbia had not performed nor scheduled condition monitoring, inspection, or preventative maintenance (since receiving an operating license in 1983) of the submerged portion of the suppression chamber, the standby service water spray ponds, or the condensate storage tanks. The URI stated that although the licensee performed some monitoring of these structures, failure to perform monitoring of the submerged portion of these structures could result in undetected cracks or leakage that could prevent them from meeting their design basis functions.

This URI was documented in a condition report resolved under the corrective action process with closure information Replace with "and Replace with "reviewed and accepted by the NRC" The Structures Monitoring Program provides reasonable assurance tha aging e ects are being managed. This has been demonstrated through inspection reports, program health reports, periodic assessments, and the corrective action program.

The site corrective action program and ongoing review of industry operating experience will be used to ensure that the program continues to be effective in managing the identified aging effects.

Conclusion The Structures Monitoring Program, with enhancements, will be capable of detecting and managing aging effects for structures within the scope of license renewal. The continued implementation of the Structures Monitoring Program, with the required enhancements, provides reasonable assurance that the effects of aging will be managed so that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Aging Management Programs Page B-196 Janay-24O1 Amendment I

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 1 of 2 Summary of Operatinq Experience Update Chances Change Summary Changed or new Number pages Based on a review of recent operating experiences, the 3.3-315 environment of the air handling units WMA-AH-51 A/B was updated 3.3-328 16 to include internal condensation. A plant specific note was added 3.3-328a to clarify. 3.3-4003.3-400a B-68 B-68a Updated the Appendix J Program to include the system health report information for an additional (2009) year. The new 17 information did not change the conclusions reached about the B-35 program.

Updated the Fuel Oil Chemistry Program to reflect the completion of the evaluation for possible adverse impacts due to use of ultra-18 low-sulfur diesel (ULSD). Energy Northwest has determined that there are no compatibility issues and that no corrective actions or B-123 modifications are required to complete the transition to ULSD.

Included information about the August 2009 failure of a 6.9 kV metal-enclosed bus (MEB) to the Operating Experience section of 19 the Metal-Enclosed Bus Program. Although the MEB is not in B-158 scope, the failure was attributed to an aging effect and is applicable to the program discussion.

Updated the Operating Experience section of the Structures Monitoring Program. One item provided additional information regarding the flaw in exterior wall of the reactor building. The results of the visual examination were included. Corrective actions include re-inspection and trending by the Program.

A second change was made to reflect the closure of the B-196 20 Unresolved Item (URI) regarding the failure to perform monitoring B-196a on submerged portions of some structures. The NRC has closed B-207 the URI in NRC Integrated Inspection Report 05000397/20090004.

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 2 of 2 Summary of Operating Experience Update Changes Change Summary Changed or new Number pages 47 Updated the Material Handling System Inspection Program to B-154 include the system health report information for an additional (2009) year. The new information did not change the conclusions reached about the program.

0 i ,-I Columbia Generating Station License Renewal Application Technical Information Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801 Further Item Co Co dt Aging Aging Management Evaluation Discussion Number omponenommoiy Effect/Mechanism Programs Recommended 3.3.1-94 Stainless steel and nickel alloy None None NA - No AEM or Consistent with NUREG-1801.

piping, piping components, and AMP piping elements exposed to No aging effects requiring air- indoor uncontrolled management are identified for (external) stainless steel piping, piping Insert: components, and piping elements in the auxiliary systems "heat that are exposed to air-indoor exchanger uncontrolled (external).

components,"

This item is also applied to stainless steel accumulators, bolting, drain pans, duct, screens, and tanks that are exposed to air-indoor uncontrolled (external). A Note C is applied.

3.3.1-95 Steel and aluminum piping, None None NA - No AEM or Not applicable.

piping components, and piping AMP elements exposed to air - There are no steel or aluminum indoor controlled (external) piping, piping components, or piping elements in the auxiliary systems that are exposed to air-indoor controlled (external). All air-indoor environments were conservatively evaluated as uncontrolled environments.

Aging Management Review Results Page 3.3-115 l~renrnntI~ 1

0 I6-2 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-36 Aging Management Review Results - Radwaste Building HVAC Systems NUREG-Row Component Intended Material Environment Aging EfcAging 1801 Table 1 Notes No. Type Function(s) Requiring Management Volume Item Management Program 2 Item Structural Air-indoor Loss of External 3.3.1-92 Valve Body integrity Steel uncontrolled Surfaces VII.I-8 58A 9 (External) Monitoring 58 93 Valve Body Structural Condensation Loss of External 3.3.1- A Steel (External) material Surf11 58 9 3V l e B d inte g rity ( x e n lm a ri lM o nito rin g _ 5 8__

_ _ _ _ _ _ _ _ _

Insert new rows 94 through 99 for Table 3.3.2-36 as shown on page 3.3-328a Page 3.3-328 Aging Review Results Management Review Aging Management Results Page 3.3-328 ia;;uary 2010 jAmendrn

0 I4-:~%

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-36 Aging Management Review Results - Radwaste Building HVAC Systems Aging Effect Aging NUREG-Row Component Intended Material Environment Requiring Management 1801 Table 1 Notes No. Type Function(s) Maaeet Porm Volume Item Management Program 2 ftem Air-Handling Air-indoor External Unit Housing 94 (M-H Pressure onay SteelLoss Seluncontrolled Lossriof of Surfaces VII.I-8 3.31-58C00 (WMA-AH- boundary (Internal) materal Monitoring Air-Handling Unit Housing Pressure Condensation Loss of Cooling Units VIL.G-23 3.3*I-(WMA-AH- boundary Steel (Internal) material Inspection 71 51 AB) ..

Air-Handling Air-indoor External 96 Unit Housing Pressure Steel uncontrolled Loss of Surfaces VII.l-8 3.3.1- A (WMA-AH-51 AM) boundary (External) material Monitoring 58 Moiorn Pressure Soil Buried Piping 97 Bolting boundary Steel (External) Cracking and Tanks N/A N/A G Inspection Pressure Soil Loss of Buried Piping 98 Bolting boundary Steel (External) material and Tanks N/A N/A G I _Inspection Pressure Soil Loss of Buried Piping 99 Bolting boury Steel (oil load and Tanks N/A N/A G boundary (External) pre-load Inspection Amendment I Aging Management Aging Review Results Management Review Results Page 3.3-328a Page 3.3-328a Amendment 1

0 I6PK5 Columbia Generating Station Generic Notes Table 3.3,2-xx 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 on page 3.3-400a Aging Management Review Results Page 3.3-400 JaiymedmenO1 JAmendment 1

0 16V3 Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Page 3.3-400 0325 The material is not aluminum alloy > 12% Zinc or 6% Magnesium, which is required for the mechanism of cracking due to stress corrosion cracking to be applicable.

0326 Based on a review of recent operating experience, the bottom portion of the air-handling unit housings for WMA-AH-51A/B are evaluated as exposed to an internal environment of condensation.

0327 No aging effects requiring management have been identified. However, for all brass (copper alloy > 15% Zn) spray nozzles that are in the scope of license renewal, the Fire Water Program is credited to provide confirmation of the absence of significant aging effects during the period of extended operation.

Amendment 1 Aging Management

.Aging Management Review Results Review Results Page 3.3-400a Page 3.3-400a Amendment' i

.2.14 Cooling Units Inspection Columbia Generating Station License Renewal Application Technical Information experience (e~g., time in-service, most susceptible locations, lowest**design margins).

Inspection findings that do notý meet the, acceptance criteria will be evaluated using the Columbia corrective action process to determine the need. for subsequent aging management activities and for monitoringand taending df the results.

" Acceptance Criteria Indications or relevant conditions of degradation detected during, the inspections will be compared to pre-determined acceptance criteria. If the acceptance criteria are not met, then the indications and, conditions wvill be.evaluated under: the corrective action program to, determine whether they could result in a loss of component intended function dur.ing the period of extended operation,

, Corrective Actions This element is common to Columbia programs and activities that are credited with aging management .during the period of extended operation and is discussed in Section B. :3

" Confirmation Process This element is dommon to. Columbia programs and activitlies that are .credited with aging management during. the period of extended operation and is discussed in Section B.1:,3.

" Administrative Controls This, element is common to Columbia programs and activities that are credited with aging management during the period of extended operation and is discussed in Section 8 13.

o Operating Experience The Cooling Units Inspection is a new one-time inspection activity for which plant operating experience has not shown the occurrence of the aforementioned aging effects. The inspection provides for confirmation of material conditiOns near the period of extended operation. The elements comprising the inspection activity are to be consistent with industry practice.

NUREG-1801 is based on industry operating experience through January 2005.

Recent industry operating experience, has been reviewed for applicability; none was identified. Future operating experience is captured through the normal. operating experience review process, which will continue through the period of extended operation.

A review of Columbia operating experience, documented in recent work. orders, revealed that cooling unit coils have been found clean and no leakage was observed. *. . t___-__

Aging Management Programs Page B-68 *JdanTudy0110

[Arnendment 1 A

License Renewal Application Technical Information Insert A to LRA Section B.2.14, page B-68 In addition, water was found to be dripping from duct downstream of Control Room Division 1 air handling: unit WMA-AH-51A in June of 2009. This was determined to be, from condensation that collected in a depression in the bottom of the air handling unit housing. Water was removed from the bottom of the housing and similar air handling units were inspected and confirmed to be self-draining properly. No corrosion of the air unit housing was identified during the removal and inspection.

Page Amendment 1 Page B-68a Aging Management. Programs Aging Management Programs B-68a Amendment 1

O B.2.3 Appendix J Program Columbia Generating Station License Renewal Application Technical Information Type B and C leakage rate test results from the 2007 Refueling Outage (R18) are summarized in the local leak rate test post outage report. The R18 local leak rate test involved ninety-one Type B and C air tests. Twenty-five Type B tests were conducted, including the personnel airlock barrel test. All Type B as found leak rates were below their administrative limits with the exception of the containment-side flange (CEP-V-2A),

which had a leak rate exceeding its administrative limit. This flange was checked using a soap solution with test pressure applied and showed no external leakage. This visual inspection confirmed that the leakage recorded was into the system rather than a breach of the containment penetration. Sixty-six Type C tests were conducted. All but eight valves had as found leak rates below their administrative limits. The valves with leak rates in excess of their administrative limit required corrective actions to reduce their leak rates. Of the eight valves with as found leak rates in excess of their administrative limits, five required disassembly and rework, and one valve was replaced. The remaining two valves were successfully flushed and as-left tested without disassembly.

The total as found leakage at the beginning of Refueling Outage 19 (R19) was 19,712 standard cubic centimeters per minute (sccm). This equates to 16.2 percent of the total allowable containment leakage (La) of 121,536 sccm. The values from previous refueling outages (R18) and (R17) were 13,683 sccm and 20,879 sccm respectively.

The total as left leakage at the end of R19 was 13,098 sccm. This equates to 10.8 percent of the total allowable containment leakage (La) of 121,536 sccm and well below.

the maximum allowable startup containment leakage rate of 0.6La. The values from the previous refueling outages (R18) and (R17) were 14,051 sccm and 17,423 sccm, respectively.

The results of previous Type A tests are shown below. No Type A tests have failed to meet their acceptance criteria at Columbia.

Test Date Total Leakage Acceptance Limit (percent) (percent) 02/16/1984 0.2758 0.50 06/17/1987 0.3241 0.50 06/09/1991 0.319 0.50 07/20/1994 0.330 0.50 06/14/2009 [ 0.3418 0.50 The health of the Appendix J Program is reported periodically in terms of performance indicators. The program health reports for 2007ýýý indicated no age-related concerns for systems and components within the, ope of the Appendix J Program.

Ito 2009 k [Amendment 1 ]

AgngMaagmet roras ag B3 Aging Management Programs Page B-35 __>ý Ja4uaryý

0 13, B,2,29 Fuel Oil Chemistry Program Columbia Generating Station License Renewal Application Technical Information contain fuel oil. Quarterly sampling of the fuel oil tanks for the diesel-driven fire pumps has been effective at identifying unacceptable levels of water and sediment prior to a loss of function. Higher than expected amounts of water or sediment during periodic sampling has resulted in cleaning of the tanks and filtering of the fuel to restore acceptable conditions. The periodic cleaning and filtering has included the addition of a biocide due to evidence of biofouling.

To meet new Environmental Protection Agency requirements, Columbia will be transitioning to Ultra-Low-Sulfur Diesel (ULSD) fuel prior to the period of extended operation. ULSD fuel and its possible adverse impacts on diesel performance are addressed in NRC Information Notice 2006-022. The impact of using ULSD fuel on the Columbia design and licensing basis has been evaluated, including the consideration of related operating experience from the industry, and corrective actions assigned to account for the future transition. -Getumbia Will "c" t to a ha -t-th

• ,-,nn VVI i*iHgiVI a

"-*Replace with Insert A below The Fuel Oil Chemistry Program will manage loss of material and cracking for susceptible components through monitoring and control of contaminants in the fuel oil.

The Fuel Oil Chemistry Program provides reasonable assurance that the aging effects will be managed such that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Insert A:

Energy Northwest determined that there are no compatibility issues and that no corrective actions or modifications are necessary as a result of the transition to ULSD fuel, Aging Management Programs Page B-123 7 ~

IAmendment 1

Q~c~

B.2.40 Metal-Enclosed Bus Program Columbia Generating Station License Renewal Application, Technical Information Confirmation Process This element isý common to. Columbia programs. and activities that are credited with aging management -during, the: period of extended operation and is discussed 'in Section. B.1 .3>.

• Administiative' Controls This element is common to. Columbia prog rams and.activitiesý that are credited with aging management during the period of extended' operation and is discussed in Section B>1.3.

Operating, Experience The Metal-Enclosed Bus Program is.anewv program for which there is no direct site-specific operating experience. Based on re-,iew of plant-specific and industry operating experience,* the identified' aging effects require management for the period of extended operation.

Plant operating experience has shown that the corrective action program has addressed' issues related to bus and bus enclosure degradation i inecent years. For example, corrosion was identified 'on insulators used to support bus associated with the unit normal auxiliary transfOrmer(which is not in scope for license, renewal). In.

addition, the corrective action program noted that the use of thermography would provide an improvement to the bus preVe'ntive,. maintenance program. Industry operating experience will be included in the development of this program;.

Required Enhancements dd hnse A.shOo Not applicable, this is a new program.

Conclusion The Metal-Enclosed Bus Program will manage.aging degradation for metal-enclosed

.bus., The Metal-Enclosed Bus Program will provide reasonabie assurance that the aging. effects will be managed such that:, metal-enclosed bus subject to aging management review will continue to perform its intended 'functions consistent with the:

current licensing basis for the period of extended, operation.,

Insert A:

Also, in August 2009, there was a failure of a 6.9 kV non-segregated metal-enclosed bus (this bus not in the license renewal scope). The corrective action program is addressing the cause and actions needed to prevent reoccurrence on plant metal-enclosed busses.

Aging Management Programs Page B-158

0 B.250 Structures Monitoring Program Columbia Generating Station License Renewal Application Technical Information of whether failures were maintenance preventable. A review of the Maintenance Rule program periodic assessments did not identify any age-related functional failures related to structures. Two non-age related functional failures identified were that the Reactor Building crane was parked without the tornado latches installed and a 10 CFR 21 notice from Whiting Crane Corporation regarding a weld defect on the Reactor Building crane main trolley. I Replace with "documented" I A Feeet condition report detumeRt a surface flaw noted in the concrete of the west exterior wall of the Reactor Building. The surface flaw appears to have existed for a significant period of time with no apparent adverse effects on secondary containment or the Reactor Building structure. Add Insert A on page B-196a NRC Unresolved Item (URI)05000397/2007005-02 was issued in February of 2008.

This URI identified that Columbia had not performed nor scheduled condition monitoring, inspection, or preventative maintenance (since receiving an operating license in 1983) of the submerged portion of the suppression chamber, the standby service water spray ponds, or the condensate storage tanks. The URI stated that although the licensee performed some monitoring of these structures, failure to perform monitoring of the submerged portion of these structures could result in undetected cracks or leakage that could prevent them from meeting their design basis functions.

This URI was documented in a condition report resolved under the corrective action process with closure information ieaFthe m, 6,4b Replace with "and

.. Replace with "reviewed and accepted by the NRCý has been" The Structures Monitoring Program provides reasonable assurance that aging effects are being managed. This has been demonstrated through inspection reports, program health reports, periodic assessments, and the corrective action program.

The site corrective action program and ongoing review of industry operating experience will be used to ensure that the program continues to be effective in managing the identified aging effects.

Conclusion The Structures Monitoring Program, with enhancements, will be capable of detecting and managing aging effects for structures within the scope of license renewal. The continued implementation of the Structures Monitoring Program, with the required enhancements, provides reasonable assurance that the effects of aging will be managed so that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Aging Management Programs Page B-196 JanuaiQ24O

0 o-Columbia Generating Station License Renewal Application Technical Information Insert A for LRA Section B.2.50, Pa-ge B-1 96 Investigation concluded that the crack has existed since construction and was repaired by grout material. A visual inspection of the cracked area determined additional sealing was required in order to prevent potential corrosion of reinforcing steel. The surface flaw crack has been partially sealed at the north end to close up the wider portion of the gap. The location of the surface flaw has been noted for re-inspection and future trending by the Structural Monitoring Program.

Amendment 1 Aging Programs Management Programs Aging Management Page B-1 96a Page B-i 96a Amendment 1

0 2o-;l Columbia Generating Station B.2.53 Water Control Structures Inspection License Renewal Application Technical Information Operating Experience The Water Control Structures Inspection has been effective in managing the identified aging effects. Visual inspections conducted by the Water Control Structures Inspection, implemented as part of the Structures Monitoring Program, have found no age-related problems.

The general structural condition of Standby Service Water Pump Houses "A" and "B" and their associated spray ponds is good. No adverse conditions or deficiencies (cracking, spalling, or honeycombs) were noted during the inspection of concrete structural elements (walls, slabs, beams, etc.) that would affect the structural integrity of either pump house or spray pond. Equipment anchorages were secured. No degraded conditions (bent or twisted members, cracked welds, loose or missing fasteners, etc) were identified for steel members. The "saddle" supports for the ring header were noted to have the coating delaminating in places. However, there were only minor amounts of corrosion products at those locations (i.e., not a structural concern). Pipe supports on spray pond walls were in good shape with all fasteners installed and tight. Doors and frames did not show any evidence of a degraded condition. There were no signs of moisture intrusion from the roof above and no signs of gross deficiencies (spalling, cracking, honeycombs) found from below. There were no obvious deficiencies identified with the crane structural frames. The rails appeared in good physical condition with no obvious signs of degradation such as bent or deformed rails. The Standby Service Water Pump Houses and the Spray Ponds are capable of performing their intended design function as the ultimate heat sink in response to accident conditions. -- Replace with "and has been" NRC Unresolved Item (URI) 05000397/2007005-0F was issued in February of 2008.

This URI identified that Columbia had not p rformed nor scheduled condition monitoring, inspection, or preventative mainten nce (since receiving an operating license in 1983) of the submerged portion of th suppression chamber, the standby service water spray ponds, or the condensate orage tanks. The URI stated that although the licensee performed some monitoring of these structures, failure to perform monitoring of the submerged portion of these tructures could result in undetected cracks or leakage that could prevent them fro meeting their design basis functions.

This URI was documented in a condition report resolved under the corrective action process with closure information expeeted-aRe thc timcofth-c RA su4hta. *-Replace with previewed and accepted by the NRC" '

The general conditions noted for the Circulating Water Pump House (including circulating water basin) and the cooling tower basins, including the structural components within the structures, was acceptable. Minor leaching was observed in the Circulating Water Pump House on a concrete pad near the interface with the siding, in addition to cracks in the wall along joints due to stresses caused by a hanger attached to the wall above the door, corrosion on the lower section of various door frames, and Aging Management Programs Page B-207 Ja44wary "G-t-Amendment 1

0QLAI Columbia Generating Station B.2.39 Material Handling System Inspection Program License Renewal Application Technical Information frequency in that degradation of cranes (including bridge, trolley, rails, and girders),

monorails, and hoists was detected prior to loss of function. Related crane and hoist inspections have found no age-related degradation problems.

The health of the Material Handling System Inspection Program is reported periodically in terms of performance indicators. The program health reports for 2007 and-20eS-noted no age-related improvements for the program.

The Material Handling System Inspection Program has been effective in managing the identified aging effects. The site corrective action program and ongoing review of industry operating experience will be used to ensure that the program continues to be effective in managing the identified aging effects. replace with Conclusion "to 2009" The Material Handling System Inspection Program will be capable of detecting and managing loss of material for cranes (including bridge, trolley, rails, and girders),

monorails, and hoists within the scope of license renewal. The continued implementation of the Material Handling System Inspection Program,-with-he-requbed-enhancement provides reasonable assurance that the aging effects will be managed such that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

JAendment 1 t Jo~a~y2O4 Agin MaageentProgamsPag B-54 Aging Management Programs Page B-1 54 L-ý Japwapy-2(M-0

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 1 of 3 Summary of Reference Update Review Changes Change Summary Changed or new Number pages Deleted cracking of stainless steel (SS) for the Radwaste Building HVAC System piping from the External Surfaces 6 Monitoring Program. Cracking of SS occurs when 3.3-325 temperatures are greater than 140'F. The Radwaste Building A-49 HVAC maximum temperature exposure is 120'F. Therefore, B-101 cracking is not an applicable aging effect. The Radwaste B-102 Building HVAC has the only SS piping subject to cracking that B-103 had been covered by the program.

Deleted cracking as an aging effect for the aluminum alloy in the following systems:

Diesel Building HVAC 3.3-34 Potable Cold Water (PWC) 3.3-180 7 Pump House HVAC Systems 3.3-181 Radwaste Building HVAC Systems 3.3-287 Reactor Building HVAC Systems 3.3-288 The aluminum alloys do not exceed the limits of > 12% zinc 3.3-307 or > 6% magnesium for alloys exposed to a condensation 3.3-308 environment. The plant specific note was added for further 3.3-309 clarification. 3.3-320 3.3-321 3.3-333 3.3-334 3.3-400 3.3-400a Removed some of the Reactor Recirculation Air (RRA) 8 cooling coils from the list because the aluminum alloy fins 3.3-334 have been replaced with cooper alloy.

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 2 of 3 Summary of Reference Update Review Changes Change Summary Changed or new Number pages Materials in the Process Sampling (PS) System have been updated to include copper alloys with > 15% zinc. As a result, 3.3-36 a new aging effect of cracking was added. An additional 3.3-294 9 program, Monitoring and Collection System Inspection, is 3.3-340 required to manage the new aging effect in the PS. Removed 3.3-340a cracking as an aging effect managed by the Open Cycle A-22 Cooling Water Program. B-160 B-160a B-163 Removed the management of drain pans and drain piping for A-13 the diesel building HVAC from the Diesel System Inspection A-46 10 because the components are included in the Cooling Units B-77 Inspection. The management is addressed in the Cooling B-78 Units Inspection and does not need to be covered in both sections.

Deleted the commitment to enhance the existing Material Handling System Inspection Program by ensuring that jib A-21 11 cranes and electronically operated hoists are visually A-56 inspected for corrosion. The enhancement has been added to B-23 the program and the inspection will be tracked as a regulatory B-153 commitment. B-154 The fire requirement for the masonry walls in the Diesel Fire 2.4-21 Pump Fuel Storage Tank Room has been changed from 3-12 hour to 2-hour Secondary Containment isolation was added to the function of 2.3-24 13 the HPCS System. 2.3-24a The Diesel Fuel Oil (DO) System description was changed to reflect the editorial changes made to FSAR sections 2.3-80 14 8.3.1.1.7.2.6 and 9.5.4.2 in Amendment 60, submitted to the 2.3-80a NRC in December 2009.

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 3 of 3 Summary of Reference Update Review Changes Change Summary Changed or new Number pages Based on a review of Columbia operating cycle history, new estimates are shown for the expected reactor thermal cycles that Columbia could reasonably expect to occur over a 60 15 year operating life. The actual cycles in the same table were 4.3-4 updated based on results of the surveillance performed in 4.3-4a accordance with Technical Specification 5.5.5, "Component Cyclic or Transient Limit."

Revised the description of the Fire Protection (FP) System to clarify that the diesel engines referred to are the fire pump diesel engines. The discussion that excluded the jockey 45 pumps from the scope of license renewal was deleted from 2.3-95 the section describing components that are in scope. This is 2.3-96 a presentation issue and does not impact the scoping status 2.3-97 of the jockey pumps. Further clarification was provided by 2.3-97a dividing the strainer into 2 components; the strainer body and the strainer screen. This was done to clarify that the 2 parts of the strainer provide different intended functions.

The FP System has spray nozzles made from copper alloy with > 15% zinc. Although Energy Northwest has not identified an aging mechanism for this material when exposed 3.3-248 46 to fire water, the existing FP program inspects the spray 3.3-249 nozzles to confirm the absence of aging effects. Therefore, 3.3-400 the aging management review results were revised to include 3.3-400a this aspect of the FP program. A plant specific note (0327) was added to Table 3.3.2-xx was added. Appendix B (B.2.26) includes this discussion and no change is required for that section.

Columbia Gene.rating Station License Renewal Application Technical information Table 3.3.2-36 Aging Management Review Results -Radwaste Building HVAC Systems Intended Aging Effect Aging Table 1 Row Componet No. Type Function(s) Material Environment Requiring Management Volume Item Notes Management Program 2 Item Steel uncontrolled I -. Surfaces VIllIt8 A..i Structurag

'tructural Air-indoor Loss of External. 331A r6DeleteiG Piping 65 integrity * (External)l Monito.ring -_58_A External

- 6.........Sta...u m . S ta_ _ess_ -

-- 66--P0119 integrity Structural I Steel

,_

Stainless (External)ý-nracingt

-Monitoring Condensation Loss of Exen I

....

External 67 Piping ISalesSurfaces integrity Steel (External) material Miring V11.172..1 3E:1 27 Monitoring Sound - Air-indoor External 68 Absorber Pressure Steel uncontrolled L Surfaces V.1-8 3,3.1-5 c 0302 Casing boundary (Internal) material Monitoring Sound Air-indoor External 69 Absorber boundary Steel uncontrolled oSuffaces.

a viI-8 5 A Casing o (External), materal Monitoring V8 Structural Raw water Loss of Open-Cycle 70 Strainer (body) -Steel .1-7 B integrity (internal) material Coolig :Water:

4 .4. 4.

Structural Condensation External Loss of' A 71 Strainer (body) intfgrity Steel Surfaces VIII-1I (External) material 58 Monitoring Air-indoor .4, '.'. 4. ' 4. .4 Pressure 72 1Tubing boundtary Copper Alloy uncontrolled None .None. N/A N/A G (internal) 4 -4. 4- 4 4 4 Pressure :Copper Alloy, Air-indoor 73 1 Tubing boundary uncontro1led None None. NWA NiA Aging Management Review*Results Page 3.3-325 FAmendment 1

Columbia Generating Station Licenste Renewal Application Technical Informnation Table A-I*

Columbia License Renewal Commitments FSAR Enhancement Item Number Commitment Supplement Location or. o n (LoA ApdImplementation (LRA App. AP Schedule

23) External The External Surfaces Monitoring Program is an existing program A; .223 Enhancement Surfaces that will be continued for the period of extended operation, with the prior to the peri.od Monitoring fIollowing enhancements: of eended Program Add aluminum, copper alloy, copper alloy >15 %.Zn, gray cast operation.

iron, stainless steel (including CASS), arnd.-elastomers to the Then ongoing.

scope of the program.

Add cracking as an aging effect for aluminum avstaWsee components.

Add visual (VT-t or equivalent) or volumetric examination techniques to detect cracking.

" Add hardening and loss of strength as aging effectsfor elastomer-based mechanic§al sealants and flexible connections in HVAC systems.

Add physical examination techniques in addition to Visual inspection to detect hardening and loss of strength for elastomer-based mechanical sealants and flexible connections.in HVAC systems. _

24) Fatigue The Fatigue Monitoring Program is an existing program that will be A1,2,24 Enhancement Monitoring continued for the period of extended operation, with the following AA.3,2 prior to the period Program enhancements: oflextended A.1.34 Operation.

Then onugoing, Final Safety Analysis ReportSupplement Page A-49.

tAmendment 1

ColUmbia Generating .station License Renewal Application Technical Information B.2.3 External Surfaces Monitoring Program Program Description The External SurIaces Monitoring Program. will manage he following aging effects for.

the external sri aces, and in some cases the internal surfaces, of mechanical components within the scope of license renewal:

Loss, of material'for metalsý (aluminum, copper alloy, copper alloy > 15%.Zn, gray cast iron, stainless steel (including CASS), and steel) that are exposed to condensation, airindoor uncontrolled, and air~outdoor environments

" Cracking Of aluminum and4st s47.44exposed to condensation e.nvironments Hardening and loss of strength for elastomer-based mechanical sealants and flexibl!e.connectiohs in HVAC systems The External Surfaces Monitoring Program. is a .condition monitoring pro.gram that consists .of visual, inspections and surveillance activities of accessible. external surfaces on a frequency that generally exceeds once per fuel cycle. Surfaces that are inaccessible during normal plant operation are inspected, during refueling. outages.

Surfaces that are inaccessible or not readily visible during .both plant operations and refueling outages,; such as surfaces that are insulated, are inspected opportunistically, for example during maintenance activities during which insulation, is removed.

The External Surfaces Monitoring Program: is supplemented by the Aboveground Steel, Tanks insp rianage loss .f to-ti)n, iaterial for the inaccessible: external surfaces, of the carbon steel condensate storage tanks (L..e., the tank.; bottom).

NUREG-1801 Consistency The- External Surfaces Monitoring Program is. an existihg Columbia program that, with enhancement, will be consistent with the 10 elements.of an effectiveaging management program as described in N.UREG-1801, Section.XILM36, "External Surfaces Monitoring."

Exceptions to NUREG-i 801 None.

Required Enhancements Prior to the period of extended operation, the enhancements listed below will b.e implemented in the identified program element:

Aging Management Programs Page 13t01 -anuary -i1-

[Amendment 1 /

Columbia Generating Station License Renewal Application Technical Information Scope of Program -

Add aluminum,: copper alloy, copper alloy >15% Zn, gray cast iron, stainless steel (including.CASS), and elastomerS to the scope of the program.

Add cracking as an aging effect for aluminum apkiqs4aWe-ssteaeel.

components.

o Add hardening and loss of strength as aging effects for elastomer-based mechanical sealants and flexible connections in HVAC systems.

Monitoring and Trending,-

• Add physical examination techniques in addition to visual inspection to detect hardening and loss of strength for elastomer-based mechanical sealants and flexible connections in HVAC systems.

• Add visual (VT-i or equivalent)ý.or volumetric examination techniques to detect cracking.

Operating Experience.

The elements that comprise the External Surfaces Monitoring Program are consistent with industry practice and have proven effective in maintaining the material condition of Columbia plant systems and components.'

A review of the most recent plant-specific operating experience, through a search of condition reports,, revealed that minor component leakage (typically at. bolted joints andý closures), damage (event-driven,,. not age-related),, and degradaltion are routinely identified by the External Surfaces Monitoring Program, with subsequent corrective; actions, taken., in a timely manner;, and that no loss of pressure boundary integrity has.

occurred that-was, or could have been,. attributed to the aging ,effects that are in the scope of the program..

Operating experience associated with he External Surfaces Monitoring Program is:

routinely documented and communicated to site personnel in System Health Reports.

System Health Reports are updated after significant changes., or at lreast quarterly.

Aging Management Programs Page B-1 02 -

[Amendment 1_ý

R 6 Columbia Generating Station License Renewal Application Technical. Information Conclusion The External Surfaces Monitoring, Program will detect and manage - oss of material for aluminum, copper alloy, copper alloy > 15% Zn,.gray cast iron, stainless steel (including CASS), and :steel components, The continued implementation of the External Surfaces Monitoring Program, with the required enhancements, provides. reasonable assurance that, the effects of aging,, including cracking for aluminum iaa4-scta s e components and hardening and loss of. strength for elasto'mer-based mechanical sealants and flexible. .connectionS: in HVAC systems, will be managed: sucht that components- subject to aging management Will continue to perform their intended functions consistent With the current licensing basis for the period: of extended operation, Aging Management Programs Page B-103

-7;ý IlArnendryient 1

R~ 7-1 Columbia Generating Station License Renewal Application Technical Information Environments Subject mechanical components of the Potable Cold Water System are exposed to the following normal operating environments:

o Condensation

• Raw water Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Potable Cold Water System:

• Loss of material Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Potable Cold Water System:

• External Surfaces Monitoring Program

• Potable Water Monitoring Program

• Selective Leaching Inspection 3.3.2.1.30 Potable Hot Water System Materials The materials of construction for subject mechanical components of the Potable Hot Water System are:

• Copper alloy

• Copper alloy > 15% Zn Environments Subject mechanical components of the Potable Hot Water System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

• Raw water Aging Management Review Results Page 3.3-34 JAmendment. 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-14 Aging Management Review Results - Diesel Building HVAC Systems No. Type Function(s) Material ToTeAging Environment Effect Requiring Aging Management NUREG-Voum Te Notes Management Program Volume Item 2 Item Fan Housing Air-indoor External Pressure Steel uncontrolled Loss of Surfaces VII.l-8 3.3.1-58 C 18 (DEA-FN-1 1, 12, 21, 22, 31, boundary (Internal) material Monitoring0302 32 & 52)

Fan Housing Air-indoor External 19 (DEA-FN-11, Pressure Steel uncontrolled Loss of Surfaces VII.I-8 3.3.1-58 A 12, 21, 22, 31, boundary (External) material 32 & 52) Monitoring Air-indoor Hardening and External 20 Connection boundary Elastomer uncontrolled loss of Surfaces VII.F4-6 3.3.1-11 E (Internal) strength Monitoring Flexible Pressure Air-indoor Hardening and External 21 Connection boundary Elastomer uncontrolled loss of Surfaces VIIF4-6 3.3.1-11 E Connectionboundary_(External) strength Monitoring Heat Exchanger Raw water Loss of Open-Cycle 22 (header) (DMA- Pressure Steel L3.1-77 VRw.Cle-5 B CC-11, 12, 21, boundary (Internal) material Cooling Water 22, 31 & 32)

Heat Exchanger Pressure Condensation Loss of External 23 (header) (DMA- Steel Surfaces VIIl-11 3.3.1-58 A CC-11, 12, 21, boundary (External) material Monitoring 22, 31 & 32)

Heat Exchanger ,_,.._,Op____

--"`inD1- Heat transfer Alumninum nracking N/A N/A H CC-11, 12, 21, (External) Cooling Water

_____22, 31 &32)

IDelete row 24 1 Aging Management Review Results Page 3.3-180 Amedment 1 .

.....

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-14 Aging Management Review Results - Diesel Building HVAC Systems Component Intended Aging Effect Aging NUREG-Row RNo. Type Function(s) Material Environment Requiring Management 1801 Table I Notes No. Management Program Volume Item

_____~ 2tem I

Heat Add:

Exchanger Ad 25 (fins) (DMA- Heat transfer Aluminum Condensation Loss of Open-Cycle VII.F2- 3.3.1-27 E 0325 (External) material Cooling Water 12 CC- 1i, 12, 2 1, 22, 31 & 32)

Heat Exchanger Condensation Reduction in Open-Cycle 26 (fins) (DMA- Heat transfer Aluminum Condenato ReductionN/A N/A H CC-11, 12, 21, (External) heat transfer Cooling Water 22, 31 & 32)

Heat Exchanger 27 c(tubes Raw water Reduction in Open-Cycle VIIC1-6 27 (tubes) (DMA- Heat transfer Copper Alloy (Internal) 3.3.1-83 CC-11, 12, 21, heat transfer Cooling Water 22, 31 & 32)

Heat 28 Exchanger (tubes) (DMA- Heat transfer Copper Alloy Condensation Reduction in Open-Cycle CC-il, 12, 21, (External) heat transfer Cooling Water N/A N/A H 22, 31 & 32)

Heat 29 Exchanger (tubes) (DMA- Pressure Raw water Loss of Open-Cycle

(

CC29 , 12, 21, boundary Copper Alloy (Internal) material Cooling Water VII.C1-3 3.3.1-82 B 22, 31 & 32)

Heat Exchanger Pressure Condensation Loss of Open-Cycle VIIF2-30 (tubes) (DMA- boundary Copper Alloy (External) material Cooling Water 14 3.3.1-25 E CC-11, 12, 21, 22, 31 & 32)

Aging Management Review Results Page 3.3-181 j---nuwy-2010 jAnmndment 1

R ~~L1 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-29 Aging Management Review Results - Potable Cold Water System

.=lm iiiiiJNUREG-Aging Effect Aging NRG Row Component Intended Aging t ageng 1801 Table No. Type Function(s) Material EnvironmentoRequiring Management Volume I Item Notes 2 Item Pump Casing Structural Copper Alloy Condensation Loss of Selective 10 (PWC-P-4A/B) integrity > 15% Zn (External) material Leaching N/A N/A G

______ _ ____ ____Inspection I___

Shock Structural Copper Alloy Raw water Loss of Potable Water VII.C19 3.3.1- E Suppressor integrity (Internal) material Monitoring 81 Shock Structural Condensation Loss of External 3.3.1-12 u Copper Alloy (External) materal Surfaces VII.F1-16 25 E Suppressor integrity I (External)_ materialMonitoring 25 Structural Copper Alloy Raw water Loss of Potable Water 3.3.1-13 Strainer (body) integrity > 15% Zn (Internal) material Monitoring VI1-9 81 E El3x t e r n a .3 .1 -

Structural Copper Alloy Condensation Loss of Surfaces VII.F1-16 14 Strainer(body) integrity > 15% Zn (External) material Monitoring 25

• ~Selective*

Structural Copper Alloy Condensation Loss of Leaching N/A N/e G integrity > 15% Zn (External) material Inspection Selective 16 Strainer (body) Structural Copper Alloy Raw water Loss of Selctive VII.C1- 3.3.1-integrity > 15% Zn (Internal) material Leaching 10 84 17 Tank (shell and Structural Aluminum Raw water Loss of end cap) integrity Potable Water VIIG-8 3.3.1-(Internal) material Monitoring 62 E Insert:1 03215j 18 Tank (shell and Structural External Aluminum Condensation Loss of Surfaces VII.F1-14 3.3.1- E end cap) integrity (External) material Monitoring 27 Aging Management Review Results Page 3.3-287 FAmendment 1 1

R4 7-<5 IFefete row 19] Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-29 Aging Management Review Results - Potable Cold Water System Aging Effect Aging NUREG-Row Component Intended M 1801 Table No. Type Function(s) Material Environment Requiring Management Volume I Item Notes SManagement Program 2 Item Tank (~helI and Tank (shell and I Struc~tural Structural Condensation External i NOA WA end cap) i (External) Monitoring integrity Structural Gray Cast Raw water Loss of Potable Water 3.3.1-20 Tank (bushing) integrity Iron (Internal) material Monitoring VII.G-24 68 E Structural Gray Cast Raw water Loss of Selective VII.Cl- 3.31-21 Tank (bushing) integrity Iron (Internal) material Leaching 11 85 C

____________ _____________ Inspection ____ ____

22 Tank (bushing) Structural Gray Cast Condensation Loss of External 3.3.1-integrity Iron (External) material SuMraces - 58 A

__________________ ___________Monitoring_____ ____

Structural Gray Cast Condensation Loss of Selective 23 Tank (bushing) integrity Iron (External) material Leaching N/A N/A G Inspection 24 Tubing Structural Copper Alloy Raw water Loss of Potable Water VILC1-9 3.3.1- E integrity (Internal) material Monitoring 81 25 Tubing Structural Condensation Loss of External 3.3.1-integrity Copper Alloy (External) material Surfaces VII.F1-16 25 E Monitoring 26 Tubing Structural Copper Alloy Raw water Loss of Potable Water VIILC1-9 3.3.1- E integrity > 15% Zn (Internal) material Monitoring 81 27 Tubing Structural integrity Copper Alloy Raw water Loss of Selective VII.C1- 3.3.1-

> 15% Zn (Internal) material Leaching 10 84 A

_______ ___________ ___________ _____________ Inspection_____ ____

Aging Management Review Results Page 3.3-288 dnuaTy 20 10 jAmendment 1

P~ 7<o Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-34 Aging Management Review Results - Pump House HVAC Systems Row Component Intended Agn fet Aging Aig1801 NUREG-Now Type Aging Effect Table Function(s) Material Environment Requiring Management Voum TaIte Notes Management Program I volume Item 2 Item Heat Exchanger Pressure Raw water Open-Cycle 3.3.1-34 (header) (PRA- bounary Steel (Loss of material Cooling Water 77 CC-1A/B, boundary (Internal) Coln.Wtr7 91A/B)

Heat Delete Exchanger Pressure Condensation External 3.3.1-Row 35 (header) (PRA- boury Steel ena Loss of material Surfaces VI1.1-11 A 36 CC-IA/B, boundary (External) Monitoring 58 91 A/B)

Heat Exchanger Condensation Open-Cvrle

-36 (fi is) (PRA- Hetm haiisfeir Aluminru (External) Cracking Cooling Water IA VA H CC-1A/B, 91A/B)

Heat PAdd.:

Exchanger; Condensation Open-Cycle 3.3.1-37 (fins) (PRA- Heat transfer Aluminum (External) Loss of material VII.F2-12 27.E CC-1A/B, Cooling Water 27 91 A/B)

Heat Exchanger Condensation Reduction in Open-Cycle 38 (fins) (PRA- Heat transfer Aluminum (External) heat transfer Cooling WaterH CC-1A/B, 91A/B)

Heat Exchanger 39 (tubes) (PRA- Heat transfer Copper Alloy Raw water Reduction in Open-Cycle VII.C1-6 33.1- B CC-IA/B, (Internal) heat transfer Cooling Water 83 91 A/B) I I_____

Jonue~y 2010 Review Results Management Review Aging Management Results Page 3.3-307 Page 3.3-307 jAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-34 Aging Management Review Results - Pump House HVAC Systems Aging Effect Aging NUREG-Row Component Intended Aging Magint 1801 Table No. Type Function(s) Material Environment Requiring Management Volume 1 Item Notes Management Program 2 Item Heat Exchanger Condensation Reduction in Open-Cycle N/A N/A 40 (tubes) (PRA- Heat transfer Copper Alloy (External) heat transfer Cooling Water H CC-lA/B, 91A/B)

Heat Exchanger Raw Open-Cycle 3.3.1-41 (tubes) (PRA- Pressure Copper Alloy (In water Loss of material Coole VII.C1-3 82.1 CC-IA/B, boundary (Internal) Cooling Water 82

" 91A/B)

Heat Exchanger Pressure Condensation Open-Cycle 3.3.1-42 (tubes) (PRA- boury Copper Alloy (Extenal) Loss of material Coole VII.F2-14 25.E CC-IA/B, boundary (External) Cooling Water 25 91 A/B)

Heat Exchanger Pressure Steel Raw water Loss of material Open-Cycle, 3.3.1-43 (header) boundary (Internal) Cooling Water VIICl- 77 B (PMA-CC-81 A/B)

Heat Exchanger Pressure Condensation External 3.3.1-44 (header) Steel Loss of material Surfaces VI1.1-11 3. A (PMA-CC- boundary (External) Monitoring 58 81 A/B)

Heat 46 Exchanger u .......... .......... Condensation era Open-Cycle (fins) (PMA- (External) Cooling Water CC-81A/B)

Delete Row 45 Aging Management Review Results Page 3.3-308 -januaey2O41-Amendment 1 p

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-34 Aging Management Review Results - Pump House HVAC Systems Aging Effect Aging NUREG-Row Component Intended Aging Magint 1801 Table Notes No. Type Function(s) Material Environment Requiring Management Volume I Item Management Program 2 Item Add:

Heat 0325 46 46 (fins) (PMA-Exchanger Hettase Heat transfer lmnm Aluminum (External)

Condensation Loso aeilCooling Loss of material Water Open-Cycle VII.F2-12 27 3,3.1- EE

• CC-81A/B)

Heat 47 Exchanger Heat transfer Aluminum Condensation Reduction in Open-Cycle N/A N/A H (fins) (PMA- (External) heat transfer Cooling Water CC-81 A/B)

Heat Exchanger Raw water Reduction in Open-Cycle VIICl6 3.3.1-(tubes) (PMA- (Internal) heat transfer Cooling Water 83 CC-81 A/B)

Heat Exchanger Cnesto euto n Oe-yl / /

49 Exchanes)(PA Heat transfer Copper Alloy Condensation Reduction in Open-Cycle N/A N/A H (tubes) (PMA- (External) heat transfer Cooling Water CC-81 A/B)

Heat Exchanger Pressure Copper Alloy Raw(Inter Loss of material Open-Cycle VI1Cl-3 B (tubes) (PMA- boundary (internal) Cooling Water 82 CC-81A/B)

Heat 51 Exchanger Pressure Condensation Copper Alloy (External) Loss of material Open-Cycle VII.F2-14 331- E (tubes)

CC-81A/B)

(PMA- boundary (Etrnl Cooling Water 25 Mechanical Pressure Air-indoor Hardening and External 52 Sealants boundary Elastomer uncontrolled Hareng Surfaces VII.F1-7 3.3.1- E Sealants______ boundary_ (Internal) loss of strength Monitoring 11 Air-indoor External 53 Mechanical Pressure Elastomer uncontrolled Hardening and Surfaces VII.F1-7 33.1- E Sealants boundary (External) loss of strength Monitoring I E Aging Management Review Results Page 3.3-309 Janunrnde010 jAmendment 1ý

A 1?-ý Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-36 Aging Management Review Results - Radwaste Building HVAC Systems Row Component Intended Agn fet Aig1801 NUREG- Table 1 No. Type Aging Effect Aging Notes-Function(s) Material Environment Requiring Management V m Tem.

Management Notes Program Volume Item 2 Item Heat Exchanger 3 (header) Pressure Steel Condensation Loss of Ernal-11 3.3.1- A (WMA-CC- boundary (External) material Moitorin 58 51A2, 51B2, Monitoring 52A2 & 52B2)

Heat Exchanger 38 (fins) (WMA- Heat transfer Aluminum Condensation Cooling Units N/A N/A H CC-51A2, (External) Cracking Inspection 51B2, 52A2 &

52B2)

Heat Exchanger 39 (fins) (WMA- Heat transfer Aluminum Condensation Loss of Cooling Units VII.F2-12 3.3.1- E CC-51 A2, (External) material Inspection 27 51B2, 52A2 &

52B2)

Heat Exchanger 40 (fins) (WMA- Heat transfer Aluminum Condensation Reduction in Cooling Units N/A N/A H CC-51A2, (External) heat transfer Inspection 51B2, 52A2 &

52B2)

Heat Exchanger __ _ _,__ _...._ _ ______..._,,.,_

41 (fins) (WMA- Heat transfer Aluminum CExtern Crackin g W te N/A NA H CC-53A2 &- (External) Cooling Water D53eR2)

I~elete Row 41 Aging Management Review Results Page 3.3-320 Amendment 1 -

R 7n o Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-36 Aging Management Review Results - Radwaste Building HVAC 'Systems Aging Effect Aging NUREG-No. Type Function(s) Material Environment Requiring Management Volume Item Notes Management Program 2 Item Heat Exchanger Condensation Loss of Open-Cycle 3.3.1- Add:

42 (fins) (WMA- Heat transfer Aluminum (External) material Cooling Water VII.F2-12 2.3.1- E 0325 CC-53A2 & ( n 53132)

Heat 43 Exchanger Heat transfer Aluminum Condensation Reduction in Open-Cycle N/A N/A (fins) (WMA- H (External) heat transfer Cooling Water CC-53A2 &

5312 Heat Exchanger (tubes)

CC-51A1, (WMA-44 51B1, 52A1, Heat transfer Copper Alloy Condensation Reduction. in Open-Cycle H (External) heat transfer Cooling Water N/A N/A 52B1, 53A1, 53A2, 53B1 &

53B2 Heat Exchanger (tubes) (WMA-45 CC-51A1, Heat transfer Copper Alloy Raw water Reduction in Open-Cycle VII.C1-6 3.3.1-51B1,52A1, (Internal) heat transfer Cooling Water 83 B 52B1, 53A1, 53A2, 53B1 &

53B2)

Aging Management Review Results Page 3.3-321 AJdIUdy 2n1m JAmendment 1 4J

R 7.11 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-37 Aging Management Review Results - Reactor Building HVAC Systems NUREG-Row Component Intended Agina Effect Aging 1801 Table I No. Type Function(s) Material Environment Requiring Management Volume Item Notes Management Program 2 Item Heat Exchanger Structural Air-indoor Loss of External 3.3.1-33 (housing) integrity Steel uncontrolled LossroflSurfaces VII.1-8 58A (ROA-HC-1 & (External) material Monitoring 2)

Heat Exchanger (header) 34 (RRA-CC-1, 2, Pressure Steel Raw water Loss of Open-Cycle VII.C1-5 3.3.1- B 3, 4, 5, 6, 10, boundary (Internal) material Cooling Water 77 11, 12, 13, 14, 15, 17, 19 &

20)

Heat Exchanger (header) External 35 (RRA-CC-1, 2, Pressure Steel Condensation Loss of Surfaces V11.1-11 3.3.1- A 3, 4. 5, 6, 10, boundary (External) material Monitoring58 11, 12, 1.3, 14, 15, 17, 19 &

20)

Heat Exchanger (fins) (RRA-

... 3-'--6

• 1.o*2*-4;- Hetrnse Auminum- ... Condensation Open-Cycle

..- NfA~........ 1tA11

- 3 1, -Hea tfansfel-5, &6 1, (External) Cooling Water 5,6, 10, 11, 211 12, 13, 14, 15,

_ _ _ 17, 19 & 20)

Delete row 36 Aging Management Review Results Page 3.3-333 j~edrnentf~ I

R 7-I2 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-37 Aging Management Review Results - Reactor Building HVAC Systems Row Component Intended Agn fet Aging Effect Aging Aig1801 NUREG- Table 1 Row Compoen Functionded Material Environment Requiring Management 181 TbeINotes Management Program Volume Item 2 Item Heat Exchanger Add:

(fins) (RRA- Condensation Loss of Open-Cycle 3.3.1- E 37 CC-1, 2, 3, 4, Heat transfer (External) material Cooling Water 0325 Aluminum 27 5, 6, 10, 11, Heat Exchanger (fins) (RRA- Condensation Reduction in Open-Cycle 38 CC-1, 2, 3, 4, Heat transfer Aluminum Condenato Redtionans OpenC ycle N/A N/A H 5,6, 10, 11, (External) heat transfer Cooling Water

,.44*,494 2,)

Heat Exchanger Structural Steam Loss of BWR Water 39 (header) integrity Steel (Internal) material Chemistry N/A N/A G (ROA-HC-1 &

2)

Heat Chemistry Exchanger Structural Steam Loss of Program (xheaner) integrity Steel (Internal) material Effectiveness (ROA-HC-1 & integrityn

2) Inspection Heat Flow-Exchanger Steam Loss of Accelerated Exchaner integrity Steel (Internal) material Corrosion (ROA-HC-1 & (FAC) 1 2) _ (

Aging Management Review Results Page 3.3-334 j~edent 1

A 13 Columbia Generating Station Generic Notes Table 3.3.2-xx 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 on page 3.3-400a Aging Management Review Results Page 3.3-400 Aamenuadmen JAmnendmnentL 1 __-

R 7-13 Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Page 3.3-400 0325 The material is not aluminum alloy > 12% Zinc or 6% Magnesium, which is required for the mechanism of cracking due to stress corrosion cracking to be applicable.

0326 Based on a review of recent operating experience, the bottom portion of the air-handling unit housings for WMA-AH-51A/B are evaluated as exposed to an internal environment of condensation.

0327 No aging effects requiring management have been identified. However, for all brass (copper alloy > 15% Zn) spray nozzles that are in the scope of license renewal, the Fire Water Proqram is credited to provide confirmation of the absence of significant aging effects during the period of extended operation.

Aging Management Review Results Page 3.3-400a ,Amendmeni

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-37 Aging Management Review Results - Reactor Building HVAC Systems Row Component Intended ging Effect Aging NUREG-Row Typo Funtended Material Environment Requiring Management 1801 Table 1 Notes No. Type Function(s) Management Program Volume Item

__________~ 2tem___

I Heat I Exchanger Add:

(fins) (RRA- Condensation Loss of Open-Cycle VII.F2-12 3.3.1- E 0325 37 CC-i,2 ý4 ettase lmnmVL21 Cooling Water 27 1 2,3,4, 5,6,10,11, eat transfer Aumium (External) material I Heat Exchanger (fins) (RRA-! (ins (RA-Condensation Reduction in Open-Cycle 38 CC-1, 2, 3, 4, Heat transfer Aluminum Condenato ReductionN/A O N/A 5,6,10, 11, (External) heat transfer Cooling Water 12, 13, 14, 15, Heat Exchanger Structural Steel Steam Loss of BWR Water N/A N/A G 39 (header) integrity (Internal) material Chemistry (ROA-HC-1 &

2)

Heat Chemistry Exchanger Structural Steam Loss of Program 40 (header) 'integrity Steel (Internal) material Effectiveness N/A N/A G (ROA-HC-1 & IInspection s eto J2 ____

IIHeat HetFlow-41 ExchangerFlw (header) Structural Steel Steam Loss of Accelerated N/A N/A G (RExchanger integrity (Internal) material Corrosion (ROA-HC-1 & (FAC)

(FAC Aging Management Review Results Page 3.3-334 j~~~mendmenJouar 201...0.........

Columbia Generating Station License Renewal Application Technical Information 3.3.2.1.32 Process Sampling System Materials The materials of construction for subject mechanical components of the Process Sampling System are:

• Copper alloy

" Copper alloy > 15% Zn

• Polymer

" Stainless steel

° Steel Environments Subject mechanical components of the Process Sampling System are exposed to the following normal operating environments:

• Condensation

° Raw water Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Process Sampling System:

• Cracking

• Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Process Sampling System:

• Bolting Integrity Program

• External Surfaces Monitoring Program Add:

• Open-Cycle Cooling Water Program "Monitoring and

• Selective Leaching Inspection lCollection Systems SInspection" Aging Management Review Results Page 3.3-36 January 7210 JAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-32 Aging Management Review Results - Process Sampling System Aging Effect 1 Aging NUREG-Row Component Intended Aging Magint 1801 Table No. Type Function(s) Material Environment Requiring Management Volume 1 Item Notes IManagement Program 2 Item 10 Strainer (body) Structural Steel Raw water Loss of Open-Cycle VII.C1-19 3763I-integrity (Internal) material Cooling Water 76 Structural Condensation Loss of External 3.3.1-11 Strainer (body) integrity Steel (External) material Surfaces Monitoring VII.I-1 1 58A 12 Tubing integrity Structural Copper C Aloy All Raw wte water Loss of Open-Cycle VII.Cl 81 3.3.1- B (Internal) material Cooling Water 81 Structural Condensation Loss of External 3.3.1-13 Tubing integrity Copper Alloy (External) material Surfaces VII.F1-16 25 E Monitoring 14 Tubing Structural Stainless Raw water Loss of Open-Cycle VII.C1-15 3.3.1- B integrity Steel (Internal) material Cooling Water 79 External 15 Tubing Structural integrity Stainless Steel Condensation (External)

Loss of material Surfaces Miring Monitoring VIIF1-1 3.3.1-27 E

E lonitoring a

nd C,ollection Structural Copper Alloy Raw water -E)Ven-Gye <_

16 Valve Body integrity > 15% Zn (Internal)

Cracking Cooaing-Water N/A N/A H Systems i -I I +i i i -i i Itnspection Structural Copper Alloy Raw water Loss of Open-Cycle 3.3.1-17 Valve Body VII.C1-9 B integrity > 15% Zn (Internal) material Cooling Water 81 Structural Copper Alloy Raw water Loss of Selective 3.3.1- A 18 Valve Body integrity > 15% Zn (Internal) material Inspection _______ 84 A Aging Management Review Results Page 3.3-294 Amendment 1

Rý9-3 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-37 Aging Management Review Results - Reactor Building HVAC Systems Row Row Component Cmpone Intended Material Environment TAging Agn Effect fet Requiring Aging Aig10 Management NUREG-1801 al Table 1 Notes No. Type iFunction(s) Maaeet Management Porm Program Volume 2 Item Item 80 Valve Body Structural Steel Raw water Loss of Potable Water 3.3.1- E integrity (Internal) material Monitoring 76 81 Valve Body Structural Steel Steam Loss of BWR Water N/A N/A G integrity (Internal) material Chemistry Chemistry 82 Valve Body Structural Steel Steam Loss of ProgramG integrity (Internal) material Effectiveness Inspection Flow-83 Valve Body Structural Steel Steam Loss of Accelerated N/A N/A G integrity (Internal) material Corrosion (FAC)

Air-indoor External 84 Valve Body Structural integrity Steel uncontrolled Loss of Surfaces VII.I-8 3.3.1-58 A (External) material Monitoring Structural Condensation Loss of External 3.3.1-Surfaces VII.I-1 1 58 A 85 Valve Body integrity Steel (External) 85material Ve BMonitoring I rnsert new rows 6 through 87 from Page 3.3-340a Aging Management Review Results Page 3.3-340 -Jai:uafy-2G40--

Amnment 1

R 9-3 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-37 Aging Management Review Results - Reactor Building HVAC Systems Row No.

Component Type Intended Function(s) Material Environment SAging AingEfetEffect Requiring Aging Agn Management NUREG-1801 Voum Table I Te Notes N Management Program Volume Item 2 Item Heat Exchanger 86 (fins) (RRA- Condensation Loss of Open-Cycle V1.F2-14 3.3.1- E 86 CC-12, 13, 14, Heat transfer Copper Alloy (External) material Cooling Water 225 15, 17, 19, &

20)

Heat Exchanger 87 (fins) (RRA- Heat transfer Copper Alloy Condensation Reduction in Open-Cycle N/A N/A H CC-12, 13, 14, (External) heat transfer Cooling Water 15, 17, 19, &

20) 3.3-340a Amendment 1 Aging Management Review Results Management Review Results 3.3-340a Amendment 1

R 9-LI Columbia Generating Station License Renewal Application Technical Information The Metal-Enclosed Bus Program is a new aging management program that will be implemented prior to the period of extended operation. The thermography portion of the program will be performed once every 10 years, with the initial inspections to be performed prior to the period of extended operation. The visual inspection portion of the program will also be performed once every 10 years, with the first inspections to be performed prior to the period of extended operation.

A.1.2.41 Monitoring and Collection Systems Inspection The Monitoring and Collection Systems Inspection detects and characterizes the condition of materials at the internal surfaces of subject mechanical components that are exposed to equipment or area drainage water and other potential contaminants and fluids. The inspection provides direct evidence as to whether, and to what extent, a loss of material due to corrosion or erosion has occurred. The inspection also determines whether cracking due to SCC of susceptible materials has occurred.

The Monitoring and Collection Systems Inspection is a new one-time inspection that will be implemented prior to the period of extended operation. The inspection activities will be conducted within the 10-year period prior to the period of extended operation.

A.1.2.42 Open-Cycle Cooling Water Program The Open-Cycle Cooling Water Program manages du tra CC of susceptible mater4as-and- loss of material due to corrosion and erosion for components located in the Standby Service Water and Plant Service Water systems, and for components connected to or serviced by those systems. The program manages fouling due to particulates (e.g., corrosion products) and biological material (micro- or macro-organisms) resulting in reduction in heat transfer for heat exchangers (including condensers, coolers, cooling coils, and evaporators) within the scope of the program.

The Open-Cycle Cooling Water Program also manages loss of material for components associated with the feed-and-bleed mode for emergency makeup water to the spray pond.

The Open-Cycle Cooling Water Program consists of inspections, surveillances, and Insert:

testing to detect the presence, and assess the extent oferaeking*-fouling* ank d loss of=foulingJ material. The inspection activities are combined with chemical treatments and cleaning activities to minimize the effects of aging. The program is a combination condition monitoring and mitigation program that implements the recommendations of NRC Generic Letter 89-13 for safety-related equipment in the scope of the program. The scope of the program also includes non-safety related components containing either service water or spray pond makeup water.

The Open-Cycle Cooling Water Program is an existing program that requires enhancement prior to the period of extended operation.

Final Safety Analysis Report Supplement Page A-22 e f Amenment 1

R 1,5-Columbia Generating Station B.2.41 Monitoring and Collection Systems Inspection License Renewal Application Technical Information

o. Floor Drains Radioactive (FDR) System

• Fuel Pool Cooling (FPC) System

• Miscellaneous Waste Radioactive (MWR) System Add:

• Plant Sanitary Drains (PSD) System Process Sampling

• Process Sampling Radioactive (PSR) .System (PS) System

• Reactor Closed Cooling (RCC) Water System A representative sample of components in these systems, to be defined in the implementing documents, and to include containment isolation piping and valve bodies, will be examined for evidence of a loss of material (due to crevice, galvanic, general, or pitting corrosion, erosion, or MIC), or to confirm a lack thereof, and the results applied to all of the systems and components within the scope of the inspection, based on engineering evaluation. 4ff-i4eklenhe-r-eprsentativcm wilH rmiuestaUifriss-steebcomtoneiits expUsd to teniperatures grter-tan-44-&-F ICIt Wll L Ii f-iId tReplace with insert A

• Preventive Actions Ion page B-160a No actions are taken as part of the Monitoring and Collection Systems Inspection to prevent aging effects or to mitigate aging degradation.

• Parameters Monitored or Inspected The parameters to be inspected by the Monitoring and Collection Systems Inspection include wall thickness or visual evidence of internal surface degradation, as measures of a loss of material or cracking in susceptible materials. Inspections will be performed by qualified personnel using established NDE techniques.

o Detection of Aging Effects The Monitoring and Collection Systems Inspection will use a combination of established volumetric and visual examination techniques (such as equivalent to VT-1 or VT-3) performed by qualified personnel on a sample population of subject components to identify evidence of loss of material or cracking in susceptible materials or to confirm a lack thereof on the susceptible internal surfaces of the components.

The sample population will be determined by engineering evaluation based on sound statistical sampling methodology, and, where practical, will be focused on the components most susceptible to aging, such as due to their time in service, the severity of conditions during normal plant operations, and the lowest design margins.

The sample population will include at least one location for containment isolation components.

Aging Management Programs Page B-160 Amendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to Page B-160 In addition, the representative sample will include stainless steel components exposed to temperatures greater than 140 OF and copper alloy> 15% Zn components exposed to raw water that will be examined for evidence of cracking due to SCC.

Page B-160a Amendment 1 Management Programs Aging Management Programs Page B-160a Amendment 1

Columbia Generating Station License Renewal Application Technical Information B.2.42 Open-Cycle Cooling Water Program Program Description The Open-Cycle Cooling Water Program manages loss of material due to crevice, galvanic, general, pitting, and MIC, and erosion for components located in the Standby Service Water and Plant Service Water systems, and components connected to or serviced by those systems, and in the Tower Makeup Water and Circulating Water systems. The program also manages fouling due to particulates (e.g., corrosion products) and biological material (micro- and macro-organisms) resulting in reduction in heat transfer for heat exchangers within the scope of the program. i addition-,-the

-progjram-mana es cacig for co p raly > 1 % n c m o c ts i th P oe e

-Sampig esubject t cst. Replace:

tAdd: The Open-Cycle Cooling Water Program consists of inspections, surveillances, and "fouliing and "and" testing to detect the presence, and assess the extent, of fouting-g4oss-ef-materiaI 7 mtl' loss raGking, combined with chemical treatments and cleaning activities to minimize fouling, o loss of material,-nd--ef-ae*ing. The existing program is a combination condition material" monitoring and mitigation program that implements the recommendations of NRC GL 89-13, "Service Water System Problems Affecting Safety-Related Equipment."

NUREG-1801 Consistency The Open-Cycle Cooling Water Program is an existing Columbia program that, with enhancement, will be consistent with the 10 elements of an effective aging management program as described in NUREG-1801 Section XI.M20, "Open-Cycle Cooling Water System," with exceptions.

Exceptions to NUREG-1801 Proqram Elements Affected:

• Preventive Actions -

NUREG-1801 states that system components are lined or coated to protect underlying metal surfaces from being exposed to aggressive cooling water environments. Protective coatings on the inner walls are not used in the service water systems that are within the scope of license renewal at Columbia.

" Monitoring and Trending -

NUREG-1801 states that testing and inspections are performed annually and during refueling outages. Inspection frequencies for the Open-Cycle Cooling Water Program are based on operating conditions and past history; flow rates, water quality, lay-up, and heat exchanger design.

Aging Management Programs Page B-163 -Jan rr201O Andrent 1

Columbia Generating Station License Renewal Application Technical Information A.1.2.15 CRDRL Nozzle Program The CRDRL Nozzle Program is an existing mitigation and condition monitoring program that manages cracking due to flaw growth of the control rod drive return line (CRDRL) nozzle, safe end, cap, and connecting welds. The CRDRL Nozzle Program consists of a) mitigation activities, and b) inspection, flaw evaluation, and repair in accordance with the ASME Boiler and Pressure Vessel Code, Section Xl, Subsection IWB, Table IWB 2500-1 (2001 Edition through 2003 Addenda) and the recommendations of NUREG-0619. System modifications were implemented by the original equipment manufacturer prior to initial startup to mitigate cracking. The BWR Water Chemistry Program monitors and controls reactor coolant water chemistry in accordance with BWRVIP guidelines to ensure the long-term integrity and safe operation of the critical regions of the CRDRL nozzle.

The CRDRL Nozzle Program credits portions of the Inservice Inspection (ISI) Program.

A.1.2.16 Diesel Starting Air Inspection The Diesel Starting Air Inspection detects and characterizes the condition of materials for the DSA System air dryers and downstream piping and components (excluding the DSA System air receivers). The inspection provides direct evidence as to whether, and to what extent, a loss of material due to corrosion has occurred.

The .Diesel Starting Air Inspection is a new one-time inspection that will be implemented prior to the period of extended operation. The inspection activities will be conducted within the 10-year period prior to the period of extended operation.

A.1.2.17 Diesel Systems Inspection The Diesel Systems Inspection detects and characterizes the condition of materials for the interior of the exhaust piping for the Division 1, 2, and 3 diesels in the Diesel Engine Exhaust System, including the loop seal drains from the exhaust piping, and the In pans and drAing eiatee-with-air-handlng-uno ieseudg'

-system&. The inspection provides direct evidence as to whether, and to what extent, a loss of material due to corrosion has occurred.

The Diesel Systems Inspection is a new one-time inspection that will be implemented prior to the period of extended operation. The inspection activities will be conducted within the 10-year period prior to the period of extended operation.

A.1.2.18 Diesel-Driven Fire Pumps Inspection The Diesel-Driven Fire Pumps Inspection detects and characterizes the material condition of the interior of the Fire Protection System diesel engine exhaust piping, and of Fire Protection System diesel heat exchangers exposed to a raw water environment.

Final Safety Analysis Report Supplement Page A-13 -,3a l jAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table A-1 Columbia License Renewal Commitments

. FSAR Enhancement Commitment Supplement or Item Number Location Implementation (LRA App. A) Schedule

16) Diesel Starting The Diesel Starting Air Inspection is a new activity. A.1.2.16 Within the 10-Air Inspection The Diesel Starting Air Inspection detects and characterizes the year period prior condition of materials for the DSA System air dryers and downstream to the period of piping and components (excluding the DSA System air. receivers), extended The inspection provides direct evidence as to whether, and to what operation.

extent, the relevant effects of aging have occurred.

17) Diesel Systems The Diesel Systems Inspection is a new activity. A.1.2.17 Within the 10-Inspection The Diesel Systems Inspection detects and characterizes the year period prior condition of materials for the interior of the exhaust piping for the to the period of Division 1, 2, and 3 diesels in the Diesel Engine Exhaust System, extended including the loop seal drains from the exhaust piping,-anidhe-elfan operation.

.pais-ai-d.ahipin~j-aseeeiatc iharhn~n unis o th Dsl-Buftding-HVA1&-syWtes. The inspection provides direct evidence as to whether, and to what extent, the relevant effects of aging have occurred.

18) Diesel-Driven The Diesel-Driven Fire Pumps Inspection is a new activity. A.1.2.18 Within the 10-Fire Pumps The Diesel-Driven Fire Pumps Inspection detects and characterizes year period prior Inspection the material condition of the interior of the Fire Protection System to the period of diesel engine exhaust piping, and of Fire Protection System diesel extended heat exchangers exposed to a raw water environment. The operation.

inspection provides direct evidence as to whether, and to what extent, the relevant effects of aging have occurred.

Januay 20K Final Safety Analysis Report Supplement Final Page A-46 Safety Analysis Report Supplement Page A-46 Amendment I

R1o-3 Columbia Generating Station License Renewal Application Technical Information B.2.17 Diesel Systems Inspection Program Description The Diesel Systems Inspection is a new one-time inspection that will detect and characterize the material condition of the interior of the exhaust piping for the Division 1, 2, and 3 diesels in the Diesel Engine Exhaust System, including the loop seal drains from the exhaust piping,-eand-the-dfain--psand-sfn-piping-asseefated-with-air-htema. The inspection provides direct evidence as to whether, and to what extent, a loss of material due to corrosion has occurred or is likely to occur.

Implementation of the Diesel Systems Inspection will provide confirmation that the integrity of the subject components will be maintained consistent with the current licensing basis during the period of extended operation.

NUREG-1801 Consistency The Diesel Systems Inspection is a new one-time inspection for Columbia that will be consistent with the 10 elements of an effective aging management program as described in NUREG-1801,Section XI.M32, "One-Time Inspection."

Exceptions to NUREG-1801 None.

Aging Management Program Elements The results of an evaluation of each program element are provided below.

Scope of Program The scope of the Diesel Systems Inspection includes the steel exhaust piping exposed to an air-outdoor environment, and the loop seal drains from the exhaust piping that are exposed to a raw water environment, for the following diesel engines:

• DG-ENG-1A1/1A2

" DG-ENG-1B1/1B2

• DG-ENG-1C

• DSA-ENG-C/2C

-Additionally thc stinleseee--aipaeelrn gposed-t-a-raw

• -water--e-twro~nment-and-associrate&-wihtefotlovvirg-equipi~i i'b oope-of Ahe-Dies.. e... ~npetien-Aging Management Programs Page B-77 Jaldy 2010

[Amendment 1

RQ10L9 Columbia Generating Station License Renewal Application Technical Information D-q MA Ald-1.1., 1.2 , 2 1., 2 ,321 , 32, a nd 5-i 1h'JousF1 ]

13-.n ---

" Preventive Actions No actions are taken as part of the Diesel Systems Inspection to prevent aging effects or to mitigate aging degradation.

o Parameters Monitored or Inspected The parameters to be inspected by the Diesel Systems Inspection include wall thickness or visual evidence of internal surface degradationr,, of the diesel exhaust piping -a4-tChe--rain-pans--and drain piping as measures of loss of material.

Inspections will be performed by qualified personnel using established NDE techniques (i.e., ultrasonic examination). Visual inspection of the internals for evidence of corrosion and corrosion products may be performed as opportunities for access arise.

• Detection of Aging Effects The Diesel Systems Inspection will use a combination of established volumetric and visual examination techniques (such as equivalent to VT-1 or VT-3) performed by qualified personnel on a representative sample of the subject components to identify evidence of loss of material.

The sample population will be determined by engineering evaluation based on sound statistical sampling methodology, and, where practical, will be focused on the components most susceptible to aging, such as due to their time in service, the severity of conditions during normal plant operations, and design margins.

The Diesel Systems Inspection will be conducted after the issuance of the renewed license and prior to the end of the current operating license, with sufficient time to implement programmatic oversight for the period of extended operation. The activities will be conducted no earlier than 10 years prior to the end of the current operating license, so that conditions are more representative of the conditions expected during the period of extended operation.

o Monitoring and Trending This one-time inspection activity is used to characterize conditions and to determine if, and to what extent, further actions may be required. The activity includes provisions for increasing the inspection sample size and locations if degradation is detected.

The sample size will be determined by engineering evaluation of the materials of construction, the environment (i.e., service conditions), aging effects, and operating experience (e.g., time in-service, susceptible locations, lowest design margins).

Inspection findings that do not meet the acceptance criteria will be evaluated using Aging Management Programs Page B-78 ,ansuary-2,44-

[Amendment 1

R Ii-I Columbia Generating Station License Renewal Application Technical Information A.1.2.37 Lubricating Oil Inspection The Lubricating Oil Inspection detects and characterizes the condition of materials in systems and components for which the Lubricating Oil Analysis Program is credited with aging management. The inspection provides direct evidence as to whether, and to what extent, a loss of material due to corrosion or selective leaching has occurred. The inspection also determines whether a reduction in heat transfer due to fouling has occurred.

The Lubricating Oil Inspection is a new one-time inspection that will be implemented prior to the period of extended operation. The inspection activities will be conducted within the 10-year period prior to the period of extended operation.

A.1.2.38 Masonry Wall Inspection The Masonry Wall Inspection consists of inspection activities to detect cracking of masonry walls within the scope of license renewal. Masonry walls that perform a fire barrier intended function are also managed by the Fire Protection Program. The Masonry Wall Inspection is implemented as part of the Structures Monitoring Program.

The Masonry Wall Inspection performs visual inspection of external surfaces of masonry walls.

The Masonry Wall Inspection is an existing program that requires enhancement prior to the period of extended operation.

A.1.2.39 Material Handling System Inspection Program The Material Handling System Inspection Program manages loss of material for cranes (including bridge, trolley, rails, and girders), monorails, and hoists within the scope of license renewal. The Material Handling System Inspection Program is based on guidance contained in ANSI B30.2 for overhead and gantry cranes, ANSI B30.11 for monorail systems and underhung cranes, and ANSI B30.16 for overhead hoists.

-enhanc.ement pirt h eido xeddoeain A.1.2.40 Metal-Enclosed Bus Program The Metal-Enclosed Bus Program is an inspection program that detects degradation of metal-enclosed bus within the scope of license renewal. The program provides for the visual inspection of interior sections of bus, and an inspection of the elastomeric seals at the joints of the duct sections. The program also makes provision for thermographic inspection of bus bolted connections.

Airnendrnent 1 Final Safety Analysis Report Supplement Page A-21 Janape*,2D4

R I-a~

1 Columbia Generating Station License Renewal Application Technical Information Table A-1 Columbia License Renewal Commitments FSAR Enhancement Commitment Supplement or Item Number Location Implementation (LRA App. A) Schedule

38) Masonry Wall The Masonry Wall Inspection is an existing program that will be A.1.2.38 Enhancement Inspection continued for the period of extended operation, with the following prior to the period enhancements: of extended Specify that for each masonry wall, the extent of observed operation.

masonry cracking or degradation of steel edge supports and Then geaifg.

bracing are evaluated to ensure that the current evaluation basis is still valid. Corrective action is required if the extent of masonry cracking or steel degradation is sufficient to invalidate the !ongoing evaluation basis. An option is to develop a new evaluation basis that accounts for the degraded condition of the wall (i.e.,

acceptance by further evaluation).

39) Material The Material Handling System Inspection Program is an existing A.1.2.39 Enaneemrerr-Handling program that will be continued for the period of extended operation- prboto-thre-period System wIh-teo Uei-ftg-enhlreM1t: oeextended-Inspection -,---E- dtsus-and--etectriists-are-wsuatly Program

• fr.

• ted Then ongoing.

[Amendment 1 Final Safety Analysis Report Supplement Page A-56

" 11-3 Columbia Generating Station License Renewal Application Technical Information Table B-2 Consistency of Columbia Aging Management Programs with NUREG-1801 (continued)

Consistent Consistent with New Cosset wt Plant- Enhancement Program Name ew/ with NUREG- NUREG- plant- enhneen Existing 1801 1801 with Specific Required Exceptions Inservice Inspection (ISI) Program - IWF Existing Yes --

Section B.2,35 Lubricating Oil Analysis Program Existing Yes Yes Section B.2.36 Lubricating Oil Inspection New Yes Section B.2.37 Masonry Wall Inspection Existing Yes Yes Section B.2.38 Material Handling System Inspection Existing Yes -- es--

Program Section B.2.39 Metal-Enclosed Bus Program New Yes Section B.2.40 Monitoring and Collection Systems New Yes Inspection Section B.2.41 Open-Cycle Cooling Water Program Existing Yes Yes Section B.2.42 Potable Water Monitoring Program Existing Yes Yes Section B.2.43 Aging Management Programs Page B-23 Jaanuafy204-0

R U-H Columbia Generating Station License Renewal Application Technical Information B.2.39 Material Handling System Inspection Program Program Description The Material Handling System Inspection Program is credited with managing loss of material for cranes (including bridge, trolley, rails, and girders), monorails, and hoists within the scope of license renewal. The Material Handling System Inspection Program is based on guidance contained in ANSI B30.2 for overhead and gantry cranes, ANSI B30.11 for monorail systems and underhung cranes, and ANSI B30.16 for overhead hoists. The inspections monitor structural members for signs of corrosion and wear.

The inspections are performed periodically for installed cranes and hoists (e.g., annually for the reactor building crane, other NUREG-0612 heavy load handling systems and the refueling platform).

The Material Handling System Inspection Program provides reasonable assurance that the effects of aging are adequately managed for Columbia cranes (including bridge, trolley, rails, and girders), monorails, and hoists and that their intended function will continue to be performed consistent with the current licensing basis for the period of extended operation.

Replace stricken NUREG-1801 Consistency text with "is" The Material Handling Systemjlnspection Program is an existing Columbia program that-,wthhan-eemnt-,ile consistent with the 10 elements of an effective aging management program as described in NUREG-1801,Section XI.M23, "Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems."

Exceptions to NUREG-1801 None.

Reqie EReplace stricken Required Enhancements .text with "None."

-Pfiir-to--Uep ouf-eAtended-upiatira t hancrrIement listed elow wil be implemented inthe idenified-pro*grarme mnt-Dztection-of-AginpgEffects-

-- CE)-Gecrenes FFe&iefl-. wi-Operating Experience A review of crane and hoist inspections previously conducted at Columbia and of industry operating experience confirms the acceptability of the inspections and their Amendment 1 rogras AgingManagment Pag B-15 jnua~~

Aging Management Programs Page B-1 53 jaf+uaff-20ý

R I1-5 Columbia Generating Station License Renewal Application Technical Information frequency in that degradation of cranes (including bridge, trolley, rails, and girders),

monorails, and hoists was detected prior to loss of function. Related crane and hoist inspections have found no age-related degradation problems.

The health of the Material Handling System Inspection Program is reported periodically in terms of performance indicators. The program health reports for 2007 and-2008-noted no age-related improvements for the program.

The Material Handling System Inspection Program has been effective in managing the identified aging effects. The site corrective action program and ongoing review of industry operating experience will be used to ensure that the program continues to beI effective in managing the identified aging effects. rpace withI Conclusion "to 2009" The Material Handling System Inspection Program will be capable of detecting and managing loss of material for cranes (including bridge, trolley, rails, and girders),

monorails, and hoists within the scope of license renewal. The continued implementation of the Material Handling System Inspection Programwieh-tbe rqued-en-hancemeett, provides reasonable assurance that the aging effects will be managed such that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Amendment 1 A

Aging Management Programs Page B-1 54 '-ý JaRuawO-W

Columbia.Genemating Station' License Renewa Appli'ationi0 Technical itfnkimation 2.4.4 Circulating Water Pump House.-,Seismic Catego* y0 Structure Description The Circulating Waer Pump House (a :a Circulation Water Pump: House) houses the electric and es d e w rbd tt're i ulating water o.nmp"; The.

Circul"ating Wate ump Hou .has .a reinforced concrete floor, insulated metal wall panels, 'and a. net Irof dec o'.v&j rstructurdl steel 'framing. The circu.atin .Wa e Pump House and he chlorination sections of the bui dinfg aere parated by a masonry wall, The diesel fifre pumep fuel storagel tank. room is i:solated by '3-hour fire frated masonr~y Walls. \'RpieVIu Theý. portion of the strUcture containing chlorination' systems' does. 'not Contain any equipm ent within the scope of lice'nse renewal.

Remote, buildings. credit ed in the fire:.protection program. (Service -Water Pump House,: I and '2,uCirulating:Water-Pump House:, Water. Filtration Building)i .ithnon.nrated barriers:

are sufficiently separated .from each .other and from ,the.plant that. a -single exposure, fire.:

Would not spi*ad to 'mp!re than one, building.

The circulating water basin is addressed with' Yard Structures (Section 2.4.1,2).

Reason for Snope Dete:h:i nation The. Circulating'Water Pump House :is relied upon, to demnPstrate.compliance. with the Fire. Protection ,(10 CFR50.48) regulated: event and meets the 10 CFR.54,(a)(3) scoping,: criteria. The Circulating Water Pump House provides 'physical support and protection to the, fi'e' water pumps, ..which are relied upon to demonstrate *compliance with Fire.,Protection regulated event.

In: addition, the Circulating Water Pu mp Houis'e is in the& scope of., license: renewal because it contains:.

o Structural components that are. relied on during postulated fire. event.

F.SAR References Section 104 2 and :AppendiX F of the FSAR describe he Circulating Water .Pump House.

Components Subiec to AMR Table 21:4 lists the component types that require.AMR and( theirintended function's; The structural commo ities for the Circulating Water Pump House are 'addressed ithe' bulk commodities evaluation in: Section 2.413 Scoping. and. Screening Results. Page ?24-21

[Amendment 1

R'3 Columbia Generating Station License Renewal Application Technical Information 2.3.2.3 High-Pressure Core Spray (HPCS) System

System Description

The HPCS System consists of a motor-driven centrifugal pump, a spray sparger in the reactor vessel located above the core (separate from the LPCS sparger), and associated system piping, valves, controls, and instrumentation. The HPCS System is designed to pump water into the reactor vessel over a wide range of vessel pressures.

For small breaks that do not result in rapid depressurization, the system maintains reactor water level. For large breaks, the HPCS System cools the reactor core by spray. The HPCS System also provides for core cooling in the event of a station blackout. Suction piping is provided from the condensate storage tank and also from the suppression pool. The elevation of the HPCS pump is sufficiently below the water level of both the condensate storage tanks and the suppression pool to provide a flooded pump suction and to meet pump net positive suction head (NPSH) requirements with the containment at atmospheric pressure and post-accident debris entrained on the beds of the suction strainers.

The HPCS discharge line fill system is designed to maintain the pump discharge line in a filled condition to ensure the time between the signal to start the pump and the initiation of flow into the reactor vessel is minimized. To ensure that any leakage from the discharge line is replaced and the line is always kept full, a water leg pump system is provided. Replace paragraph with Insert A shown onpgJ.-4 s onpage2.3-24a Reason for Scope Determination Th tirS~yte poias i-vspaycoingauig a iarge-break UP a uncovers the care, mainains RrV water level during a small-break LOCA tha dues rot drescurize tha reactoae ,proie P o iaion and inte"rity

, -p....

g ... i d ,maintains the rcactar coolant prcszurc boundary integrity. Alt- these sysete-in-ended fu "nclorare Safejy-relpie.

Therefoie, trie IPCS SyZleni rneets tLlhuupi*r ,gcitelia uf al F 4.4(a)(l ).

The HPCS System does not contain any NSR components that perform a 10CFR54.4(a)(1) function. The HPCS System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1).

Therefore, the HPCS System meets the scoping criteria of 10 CFR 54.4(a)(2).

The HPCS System is also relied upon to demonstrate compliance with, and meets the 10 CFR 54.4(a)(3) scoping criteria for, the Environmental Qualification (10 CFR 50.49),

Anticipated Transients Without Scram (10 CFR 50.62), and Station Blackout (10 CFR 50.63) regulated events.

Scoping and Screening Results Page 2.3-24 dullAdl 61u-Amendment 1

R 13 Columbia Generating Station License Renewal Application Technical Information Insert A for LRA Page 2.3-24 The HPCS System provides RPV spray cooling during a large-break LOCA that uncovers the core, maintains RPV water level during a small-break LOCA that does not depressurize the reactor vessel, provides Primary Containment isolation and integrity (including valve position indication), provides Secondary Containment isolation and integrity (including valve position indication), and maintains the reactor coolant pressure boundary integrity. All of these system-intended functions are safety-related. Therefore, the HPCS System meets the scoping criteria of 10 CFR 54.4(a)(1).

Scoping and Screening Results Page 2.3-24a Amendment 1

Columbia Generating Station License Renewal Application Technical Information 2.3.3.18 Diesel Fuel Oil (DO) System

System Description

The DO System consists of separate, independent diesel oil supply systems serving each of the diesel generators. Each of these systems consists of a fuel oil storage tank, a transfer pump, a day tank, interconnecting piping and valves, and associated instruments and controls.

The auxiliary boiler fuel oil storage tank (FO-TK-1) is used as an additional storage tank for the emergency diesel generator fuel oil storage and transfer system. This tank is maintained to the same cleanliness requirements as the other Class I fuel oil tanks.

The diesel fuel oil stored in this tank is surveyed to the same requirements as the fuel oil in the other diesel storage tanks. Replace paragraph with Insert A shown on page 2,3-80a The fuel oill supply fuin -th-e day-tw iidks to Ua dis~el tngine unsirts u1 LWQ ITULUally

.rdndn 11!; rna Ei__1ther sYstem iscaalofupyigul ltohenie.Eh system entains co a fel oil!--supply liine strai--ner, fuel oil pump, -duplex filter, pressure gargie, and' eliefl aind-check-vafves.

One of the fuel oil supply pumps is mechanically driven by the engine and is normally used during engine operation. The other supply pump is driven by a 120-V DC motor and is used to fill the fuel oil system and fuel header prior to initial operation and after maintenance has been performed on system piping and components. The DC-motor-driven pump runs during engine operation in the event fuel supply through the engine-driven pump systemfal.Add"new paragraph from Insert B shown on page 2.3-80af Reason for Scope Determination The DO System provides fuel oil to enable the emergency diesel generators to start, run, and load. This system-intended function is safety-related. Therefore, the DO System meets the scoping criteria of 10 CFR 54.4(a)(1).

The DO System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The DO System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1). Therefore, the DO System meets the scoping criteria of 10 CFR 54.4(a)(2).

The DO System is relied upon to demonstrate compliance with, and meets the 10 CFR 54.4(a)(3) scoping criteria for, the Fire Protection (10 CFR 50.48), Anticipated Transients Without Scram (10 CFR 50.62), and Station Blackout (10 CFR 50.63) regulated events.

Scoping and Screening Results Page 2.3-80 -4Janu 20 Amendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A for LRA Page 2.3-80 The fuel oil supply from the day tanks to each diesel engine consists of two systems.

Either system is capable of supplying fuel oil to the engine. For diesel generator sets 1 and 2, each system contains a fuel supply line strainer, fuel oil pump, duplex filter, pressure gauge, relief and check valves, and separate fuel return lines to the day tanks.

Insert B for LRA Page 2.3-80 For the.HPCS diesel generator, there are two fuel oil systems external to the engine fuel manifolds, either of which is capable of supplying fuel oil to the engine. One of the fuel oil pumps is mechanically driven by the engine and the other by a 120-V DC motor.

The systems contain the following components from the day tank: fuel supply lines, strainers, fuel oil pumps, duplex filters, and relief and check valves. The two systems join together at the manifold for the duplex filter of the engine-driven fuel oil pump and share that duplex filter, a pressure gage, fuel lines and manifolds to the injectors, injectors, and a return line to the day tank.

Scoping and Screening Results Page 2.3-80a Amendment 1

Replace this page in its entirety Columbia Generating Station with page 4.3-4a License Renewal Application Technical Information f Columbia is analyzed for 120 startups and shutdowns. The 120 startups consist of 117 normal startups and 3 natural circulation startups. The 120 shutdowns consist of 111 nor al shutdowns, 8 single safety or relief valve blowdowns, and 1 rapid depressurization with d trip.

4.3-2 e

\atTable Actual Cycles and Projected Cycles Actual cycles 12/13/1984 60 year Cycles for Analyzed through (12/13/2044) future Conditions cycles 7/31/200/ projection(3) analyses(4)

Boltup/Unbolt 123 21 5 60 Reactor Startup (100 degF/hr) 120 A 233 250 Reactor Shutdown (100 degF/hr) 11 \ 8720 4 242 1 7230 Vessel Pressure Tests X130 / 2(1 2) 2(1) 60 Loss of Feedwater Heaters 10 / 0 0 80 Scram - Loss of feedwater pumps, 1 7 18 20 isolation valves closed Scram - Single safety relief valve 0 blowdown Scram - TG trip, FW on, isolation 40 \22 58 60 valves open Scram - Other 140 34* 90O 90 LPCS operation //10 0 -* 0 10 HPCS operation 10 .4 10 104 LPCI operationp n 10 0 0 10 SLC operation 10 (1) Vessel drostatic pressure tests are no longer performed. Vessel operatio I leak t ts have replaced the hydrostatic pressure tests.

(2) The e two pressure tests were hydrostatic pressure tests.

(3) P/r jections were not changed for those events that have not occurred.

(4)he 20 Scrams with Loss of Feedwater assume 3 HPCS injections per scram.

The HPCS initiation assumes 10 additional injections without a scram. The THPCS nozzle is analyzed for 70 cycles combined from the two events.

Time-Limited Aging Analyses Page 4.3-4 -ganuarr2e4e--

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information Columbia is analyzed for 120 startups and shutdowns. The 120 startups consist of 117 normal startups and 3 natural circulation startups. The 120 shutdowns consist of 111 normal shutdowns, 8 single safety or relief valve blowdowns, and 1 rapid depressurization with delayed trip.

Table 4.3-2 Actual Cycles and Projected Cycles Actual cycles 12/13/1984 60 year Cycles for Analyzed through (12/13/2044) future cycles 2/16/2010 projectionM 1) analyses Conditions Boltup/Unbolt 123 23 54 60 Reactor Startup (100 degF/hr) 120 94 224 250 Reactor Shutdown (100 degF/hr) 111 93 221 250 Vessel Pressure Tests 130 23 54 65 Loss of Feedwater Heaters 80 0 0 80 Scram - Loss of feedwater pumps, 10 7 16 20 isolation valves closed Scram - Single safety relief valve 8 1 2 8 blowdown Scram - TG trip, FW on, isolation 40 23 54 60 valves open Scram - HPCS Injection 30 12 28 602 Scram - Other 140 39 92 90 LPCS operation 10 0 0 10 HPCS operation 10 3 7 102 LPCI operation 10 0 0 10 SLC operation 10 0 0 10 (1) Projections were not changed for those events that have not occurred.

(2) Total HPCS injection cycles from scrams (60) and non-scrams (10) should not exceed 70.

Amendment 1 Time-Limited Aging Analyses Time-Limited Aging Analyses Page 4.3-4a Page 4.3-4a Amendment 1

R LIT- I Columbia Generating Station 2.3.3.22 Fire Protection (FP) System License Renewal Application Technical Information The Carbon Dioxide and Dry Chemical Fire Suppression systems do not contain components that perform a license renewal intended function, and therefore are not within the scope of license renewal.

The diesel fuel oil lines that supply fuel oil to the fire protection pump diesels, designated as DO on the drawings, and the fire protection pump diesel engine exhaust piping, designated as DE on the drawings, are within the evaluation boundaries of the Fire Protection System.

Components Subiect to AMR Table 2.3.3-22 lists the component types that require AMR and their intended functions.

Table 3.3.2-22, Aging Management Review Results - Fire Protection System, provides the results of the AMR.

Portable fire extinguishers are within the scope of license renewal. However, they are periodically inspected and hydrostatically tested, and are replaced if they do not pass an inspection or test. Portable fire extinguishers are short-lived components, subject to replacement based on a qualified life or specified time period, and not subject to AMR.

Fire and smoke detectors, and alarm devices, do not perform a passive mechanical function for the purpose of license renewal. Electrical components that are subject to AMR (the cables for the detectors and alarms) are addressed in Section 2.5.

Fire barriers, fire dampers, fire doors, and fire penetration seals determined to be within the scope of license renewal and subject to AMR are addressed as structural commodities in Section 2.4.13.

Fire hoses are within the scope of license renewal. However, they are periodically inspected to ensure that they are in an acceptable operating condition. These ongoing hose station inspections (together with the associated action to repair or replace any fire hose noted to be in a deteriorated condition) establish a qualified life for the hoses.

Therefore, the fire hoses are not subject to AMR.

The pre-action sprinkler systems are connected to the Control Air System. A failure of the air system will place the sprinkler system in a safe position. That is, the fusible link closed sprinkler heads will maintain water inventory in the piping and the sprinkler system will still be able to perform its system-intended function. Therefore, since this portion of the Control Air System, and associated components, does not have any other component intended function, the portion of the air system included within the Fire Protection System bounda is not subject to AMR.

,Insert: "fire p umpEp The diesel engines, except for the attached heat exchanger, are evaluated as active components and not subject to AMR.

Scoping and Screening Results Page 2.3-95 -Januarty-2Oi_-1 I 'mndent 1 _j7

Columbia Generating Station License Renewal Application Technical Information

• Thjce-ump-r-e-esniI i poeto-equipment~~perF-oum bia-ic-kensee-

...G~onto. dpefetin LS4O hrefoer., since-dhe-jockey-pumps-de-not-hav'e--

.a-component-intended functio, -they-are-not-subjecF toAM;Rr-Halon cylinders are within the scope of license renewal. The principal design criterion for these bottles is Department of Transportation Standards. The halon cylinders comply with the requirements of the DOT standards. The halon cylinders are consumables, replaced periodically in accordance with DOT standards, and are not subject to AMR.

The Fire Protection bladder tank (FP-TK-110) is within the scope of license renewal.

However, it has a service life of approximately 20 years and was replaced accordingly in 2008. The replacement tank is of a similar design, with the same limited service life, and is subject to inspections to ensure its timely replacement. The bladder tank is short-lived, subject to replacement based on a qualified life or specified time period, and is not subject to AMR.

January~2O40-Scoping and Results Screening Results and Screening Page 2.3-96 Page 2.3-96 7 'January-2-04,0-

R4'45--3 Columbia Generating Station License Renewal Application Technical Information Table 2.3.3-22 Fire Protection System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Bolting Pressure Boundary Structural Integrity Exhaust silencer Pressure Boundary Flexible connection Pressure Boundary Heat exchanger (shell) Pressure Boundary Heat exchanger (tubes) Heat Transfer Pressure Boundary Hydrant Pressure Boundary Orifice Pressure Boundary Throttling Piping Pressure Boundary Structural Integrity Pump casing Pressure Boundary Spraynozzle Pressure Boundary Spray Sight glass Pressure Boundary

-S~t~rai~er~body ~scree4- *-RiltFatiofr-o PRess-ufen-BetaFy Tank Pressure Boundary Tubing Pressure Boundary Structural Integrity Valve body Pressure Boundary Structural Integrity Replace this table row with "Insert A" Ifrom page 2.3-97a Scoping and Screening Results Page 2.3-97 -Januafy-021 AAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A for LRA Paae 2.3-97 Strainer (body) Pressure boundary Strainer (screen) Filtration Amendment 1 Scoping and Scoping Screening Results and Screening Results Page 2.3-97a Page 2.3-97a Amendment 1

& q6o-1 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-22 Aging Management Review Results -Fire Protection System Component Intended Aging Effect Aging NUREG-Row yeIFunction(s)

No. Type Material Environment Requiring Management 1801 No ucio~)Management Program Volume ITable Item Notes 2 Item Casing 13 Pump Cain Pressure Prsue Gray Cast Ga at Air-indoor ucontrolled Loss of External SufcsVII8 3.3.1- A 113 (Lb i)

(Lube Oil) budr boundary rnuncotoled Iron (External) material. Surfaces Monitoring VII.1-8 58A Air-indoor Pressure Ai-nor3.3.17 114 Sight Glass boundary Glass uncontrolled None None VII.J-8 93 0306 (internal) 115 SightGlass Pressure Raw water None 3.3.1 boundary Glass (Internal) VII.J-11 93None 3 A Air-indoor Pressure Ai-nor3.3.1-116 Sight Glass boundary Glass uncontrolled None None VII.J-8 3 A (External)

Pressure Air-indoor Loss of External 117 Sight Glass boundary Steel uncontrolled Surfaces VII.1-8 3.3.1-2 (Internal) material Monitoring 58 0302 118 Sight Glass Pressure Raw water Loss of 3.3.1-boundary Steel (Internal) material Fire Water VII.G-24 68 A Air-indoor Etra Pressure Loss of External3.3.1-119 Sight Glass boundary Steel uncontrolled Surfaces VII.I-8 3. A (External) material Monitoring 58 Pressure Copper Alloy Air-indoor 120 Spray Nozzle uncontrolled None -Nene- N/A N/A G boundary > 15% Zn (Internal)  !  !

[Insert: "Fire WVater" Insert: "0327" Aging Management Review Results Page 3.3-248 j~edme t~Z 1dnay-e-

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-22 Aging Management Review Results -Fire Protection System Aging Effect Aging NUREG- T No. Type Function(s) Material Environment Requiring Management Volume 1 Item Notes Management Program 2 Item Pressure Copper Alloy Raw water H 121 Spray Nozzle boundary > 15% Zn (Internal) Cracking Fire Water N/A N/A 0318 Pressure Copper Alloy Raw water Loss of Fire Water VII.G-12 3.3.1- A 122 Spray Nozzle boundary > 15% Zn (Internal) material 70 0317 nsert:

Air-indoor 0327" 123 Spray Nozzle Pressure Copper Alloy uncontrolled None None N/A N/A G eboundary > 15% Zn (External)

Copper Alloy Air-indoor

> 15% Zn uncontrolled (Internal) None >None N/A N/A G Copper Alloy Raw water H 125 Spray Nozzle Spray > 15% Zn (Internal) Cracking Fire Water N/A N/A 0318 Spray Nozzle Spray Copper Alloy Raw water Loss of Fire Water VII.G-12 3.3.1- A 126

> 15% Zn (Internal) material 70 0317 Copper Alloy Air-indoor 127 Spray Nozzle >15aZ uncontrolled None -N4ee N/A N/A G S 15% Z (External)

Air-indoor 128 Strainer (body) boundary Copper Alloy uncontrolled None None N/A N/A G (Internal)

Insert: "Fire Water" Aging Management Review Results Page 3.3-249 Amendment I1

?~I H6O 3 Columbia Generating Station Generic Notes Table 3.3.2-xx 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 on page 3.3-400a Aging Management Review Results Page 3.3-400 JanuaaFy 20 JAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Page 3.3-400 0325 The material is not aluminum alloy > 12% Zinc or 6% Magnesium, which is required for the mechanism of cracking due to stress corrosion cracking to be applicable.

0326 Based on a review of recent operating experience, the bottom portion of the air-handling unit housings for WMA-AH-51A/B are evaluated as exposed to an internal environment of condensation.

0327 No aging effects requiring management have been identified. However, for all brass (copper alloy > 15% Zn) spray nozzles that are in the scope of license renewal, the Fire Water Program is credited to provide confirmation of the absence of significant aging effects during the period of extended operation.

Amendment I Aging Management Review Aging Management Results Review Results Page 3.3-400a Page 3.3-400a Amend'men{ iJ

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 1 of 8 Summary of Walkdown Results Changes Change Summary Changed or Number New Page Numbers Reference to new boundary drawing LR-M532 has been added to reflect the additional portions of the Control Air System (CAS) 21 added to the scope of license renewal. Portions of the CAS are 2.3-57 located in plant areas containing safety-related systems, structures, and components (SSCs) and are included in accordance with the non-safety affecting safety (NSAS) scoping criteria (10 CFR 54.4(a)(2)). No new material and environment combinations have been introduced, no new aging effects have been identified, and no new aging management programs are required.,

New components (tanks), material (stainless steel), environment (moist air), aging effect requiring management (cracking), and an 2.3-166 additional aging management program (Supplement Piping / Tank 2.3-167 22 Inspection) have been added to the LRA for the Condensate 2.3-167a (Auxiliary) (CO). Portions of the CO System are located in plant 3.4-3 areas containing safety-related SSCs and are included in 3.4-14 accordance with the NSAS scoping criteria (10 CFR 54.4(a)(2)). 3.4-14a Reference to new boundary drawings LR-M513 and LR-M514 has 3.4-43 been added to reflect the additional portions of the CO added to the 3.4-43a scope of license renewal B-197 Increased the scope of the Condensate (Nuclear) (COND) System as shown on new or revised boundary drawings LR-M527-2, LR-23 M532, and LR-M534. A new component type (flexible connections) 2.3-169 has been added to the scope of the COND System. Portions of the 2.3-170 COND System are located in plant areas containing safety-related 2.3-170a SSCs and are included in accordance with the NSAS scoping criteria 3.4-53 (10 CFR 54.4(a)(2)). No new aging management programs are 3.4-53a required to manage the aging effects of the additional component type.

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 2 of 8 Summary of Walkdown Results Changes Change Summary Changed or Number New Page Numbers Reference to new boundary drawing LR-M536 has been added to reflect the additional portions of the Condensate Processing 24 Radioactive (CPR) added to the scope of license renewal. Portions of the CPR are located in plant areas containing safety-related SSCs 2.3-38 and are included in accordance with the NSAS scoping criteria (10 CFR 54.4(a)(2)). No new material and environment combinations have been introduced, no new aging effects have been identified, and no new aging management programs are required.

Reference to new boundary drawing LR-M531 has been added to reflect the additional portions of the Floor Drain (FD) System added to the scope of license renewal. Portions of the FD are located in 25 plant areas containing safety-related SSCs and are included in 2.3-98 accordance with the NSAS scoping criteria (10 CFR 54.4(a)(2)). No new material and environment combinations have been introduced, no new aging effects have been identified, and no new aging management programs are required.

Added new components (tanks and pump casing) to the scope of the Equipment Drains Radioactive (EDR) System as shown on new LR- 2.3-90 M532. A new environment (moist air) was also identified. Portions 2.3-91 26 of the EDR are located in plant areas containing safety-related SSCs 2.3-91a and are included in accordance with the NSAS scoping criteria 3.3-25 (10 CFR 54.4(a)(2)). No new material and environment 3.3-104 combinations have been introduced, no new aging effects have been 3.3-232 identified, and no new aging management programs are required. 3.3-232a Added new components (tank and pump casing) to the scope of the Floor Drains Radioactive (FDR) System as shown on new LR-M531.

A new environment (moist air) was also identified. Portions of the 2.3-101 27 FDR are located in plant areas containing safety-related SSCs and 2.3-102 are included in accordance with the NSAS scoping criteria 2.3-102a (10 CFR 54.4(a)(2)). No new material and environment 3.3-29 combinations have been introduced, no new aging effects have been 3.3-2633.3-identified, and no new aging management programs are required 263a

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 3 of 8 Summary of Walkdown Results Chancqes Change Summary Changed or Number New Page Numbers 2.2-4 Added the Heating Steam (HS) System to the scope of license 2.3-35 renewal. Portions of the HS System are located in plant areas 2.3-162 containing safety-related SSCs and are included in accordance with 2.3-162a 28 the NSAS scoping criteria (10 CFR 54.4(a)(2)). No new material and 2.3-162b environment combinations have been introduced, no new aging 3.3-2 effects have been identified, and no new aging management 3.3-2a programs are required. 3.3-5 3.3-5a 3.3-50 3.3-50a 3.3-50b 3.3-55 3.3-55a 3.3-115 3.3-397 3.3-397a 3.3-397b 3.3-397c 3.3-397d 3.3-397e 3.3-397f 3.3-397g B-179

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 4 of 8 Summary of Walkdown Results Changes Change Summary Changed or Number New Page Numbers 2.2-4 Added the Heating Steam Condensate (HCO) System to the scope 2.3-35 of license renewal. Portions of the HCO System are located in plant 2.3-162 areas containing safety-related SSCs and are included in 2.3-162c accordance with the NSAS scoping criteria (10 CFR 54.4(a)(2)). No 2.3-162d 29 new material and environment combinations have been introduced, 3.3-2 no new aging effects have been identified, and no new aging 3.3-2a -

management programs are required. 3.3-5 3.3-5a 3.3-50 3.3-50b 3.3-50c 3.3-55 3.3-55a 3.3-77 3.3-77a 3.3-101 3.3-101a 3.3-113 3.3-397 3.3-397h 3.3-397i 3.3-397j 3.3-397k 3.3-3971 3.3-397m B-179 B-198

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 5 of 8 Summary of Walkdown Results Changes Change Summary Changed or Number New Page Numbers Added the Heating Steam Vent (HSV) System to the scope of 2.2-4 license renewal. Portions of the HSV System are located in plant 2.3-35 areas containing safety-related SSCs and are included in 2.3-162 30 accordance with the NSAS scoping criteria (10 CFR 54.4(a)(2)). No 2.3-162e new material and environment combinations have been introduced, 2.3-162f no new aging effects have been identified, and no new aging 3.3-2 management programs are required. 3.3-2a 3.3-5 3.3-5a 3.3-50 3.3-50c 3.3-50d 3.3-55 3.3-55a 3.3-397 3.3-397n Reference to new boundary drawings LR-M531, LR-M533-1, and LR-M533-2 has been added to reflect the additional portions of the Miscellaneous Waste Radioactive (MWR) System added to the 31 scope of license renewal. Portions of the MWR System are located in plant areas containing safety-related SSCs and are included in 2.3-108 accordance with the NSAS scoping criteria (10 CFR 54.4(a)(2)). No new material and environment combinations have been introduced, no new aging effects have been identified, and no new aging management programs are required.

Added new component (tubing) and location (radwaste building and corridors) for portions of the Potable Hot Water (PWH) System added to the scope of license renewal. Portions of the PWH System 2.3-117 32 are located plant areas containing safety-related SSCs and are 2.3-117a included in accordance with the NSAS scoping criteria 3.3-291 (10 CFR 54.4(a)(2)). No new material and environment 3.3-291a combinations have been introduced, no new aging effects have been B-167 identified, and no new aging management programs are required.

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 6 of 8 Summary of Walkdown Results Changes Change Summary Changed or Number New Page Numbers Revised drawing LR-M525-2 to reflect the additional portions of the Reactor Building Closed Cooling Water (RCC) System added to the scope of license renewal. Portions of the RCC System are located in 2.3-141 33 plant areas containing safety-related SSCs and are included in No page accordance with the NSAS scoping criteria (10 CFR 54.4(a)(2)). No change, new material and environment combinations have been introduced, drawing no new aging effects have been identified, and no new aging revised management programs are required.

Reference to new boundary drawing LR-M536 has been added to reflect the additional portions of the Reactor Water Cleanup (RWCU)

System added to the scope of license renewal. Portions of the 34 RWCU System are located plant areas containing safety-related 2.3-146 SSCs and are included in accordance with the NSAS scoping criteria (10 CFR 54.4(a)(2)). No new material and environment combinations have been introduced, no new aging effects have been identified, and no new aging management programs are required.

Added the Sealing Steam (SS) System to the scope of license 2.2-6 renewal. Portions of the SS System are located in plant areas 2.3-163 containing safety-related SSCs and are included in accordance with 2.3-180 35 the NSAS scoping criteria (10 CFR 54.4(a)(2)). No new material and 2.3-180a environment combinations have been introduced, no new aging 2.3-180b effects have been identified, and no new aging management 3.4-1 programs are required. 3.4-1a 3.4-9 3.4-9a 3.4-76 3.4-76a 3.4-78

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 7 of 8 Summary of Walkdown Results Chanties Change Summary Changed or Number New Page Numbers Reference to new boundary drawing LR-M508-2 has been added and LR-M508-1 has been revised to reflect the additional portions of the Plant Service Water (TSW) System added to the scope of license 36 renewal. Portions of the TSW System are located in plant areas 2.3-113 containing safety-related SSCs and are included in accordance with the NSAS scoping criteria (10 CFR 54.4(a)(2)). No new material and environment combinations have been introduced, no new aging effects have been identified, and no new aging management programs are required.

Removed the rupture discs in the Circulating Water (CW) System from the components subject to aging management review because 2.3-37 37 they do not perform a component level intended function. Buried 2.3-37a bolting and valves subject to cracking were identified in the CW 3.3-6 System. As a result, the aging management review was updated to 3.3-118 address the components and the aging effects. 3.3-119 3.3-119a Revised the discussion of the Buried Piping and Tanks Inspection Program to address cracking, loss of material, loss of pre-load on 3.3-55 bolting, and loss of material on stainless steel piping and piping 3.3-55a 38 components as aging effects managed by the program. The Buried 3.3-75 Piping and Tanks Inspection Program also manages loss of material 3.3-75a due to pitting and crevice corrosion and microbiologically influenced A-9 corrosion. A-9a A-43 A-43a B-39 B-39a B-40 B-40a Added bolting exposed to soil as a material and environment 39 combination to be managed for buried bolts in the Diesel Fuel Oil 3.3-215 System. 3.3-215a

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 8 of 8 Summary of Walkdown Results Changes Change Summary Changed or Number New Page Numbers Added bolting exposed to soil as a material and environment 40 combination to be managed for buried bolts in the Fire Protection 3.3-256 System. 3.3-256a Added bolting exposed to soil as a material and environment 41 combination to be managed for buried bolts in the Radwaste Building 3.3-328 HVAC System. 3.3-328a Added components exposed to soil as a material and environment 42 combination to be managed for buried bolts, orifices, piping, and 3.3-390 valve bodies in the Service Water System. 3.3-390a Added components exposed to soil as a material and environment 43 combination to be managed for buried bolts and valve bodies in the 3.3-395 Tower Makeup Water System. 3.3-395a 44 Added component type of south exterior slab for the Diesel 2.4-24 Generator Building. The slab provides structural or functional 2.4-24a support required to meet the requirement of 10 CFR 54.4(a)(3). The 3.5-98 concrete slab is exposed to air-outdoor and soil environments. 3.5-98a 48 Removed the Reactor Building Potable Hot Water System from 2.2-6 Table 2.2-1 because the single component scoped into the system has been removed from the reactor building. As such, the system no longer exists.

Columbia Generating Station License Renewal Application Technical Information 2.3.3.10 Control Air System (CAS)

System Description

The CAS provides oil-free, filtered, and dried instrument-quality air throughout the plant for pneumatic instrumentation, controls, and actuators. The CAS also provides air to the outboard MSIV accumulators, and to the wetwell vacuum breaker solenoid pilot valves. The system is designed to provide uninterrupted service during normal plant operation.

The air receivers store compressed air to serve associated pneumatic loads. The Cooling Jacket Water (CJW) System is a closed water system provided to cool the three CAS compressors and the two CAS refrigerated dryers. Operation of CAS is not required for the initiation of any engineered safeguard system or for safe shutdown of the reactor, but is required for continuous plant operation. Based on this, operation of the CAS is not required for mitigation of a design basis accident or abnormal operational transient.

Reason for Scope Determination The CAS provides Primary Containment isolation and integrity. This system-intended function is- safety-related. Therefore, the CAS meets the scoping criteria of 10 CFR 54.4(a)(1).

The CAS does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The CAS does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1). Therefore, the CAS meets the scoping criteria of 10 CFR 54.4(a)(2).

The CAS is not relied upon to demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events.

FSAR References Sections 9.3.1.1.1 and 9.3.1.3.1 of the FSAR describe the Control Air System.

License Renewal Drawings The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

LR-M510-2, LR-M510-2A Components Subiect to AMR Table 2.3.3-10 lists the component types that require AMR and their intended functions.

Scoping and Screening Results Page 2.3-57 4

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information 2.3.4.2 Condensate (Auxiliary) (CO) System

System Description

The CO System returns condensate from the Auxiliary Steam System, which operates only when the heating steam evaporators are inoperative during plant shutdown, to the Condensate Return Tank, by means of either the Radwaste Building Heating Condensate Pump Set (WHCO-CU-1) or the Condensate Pump Set (SHCO-CU-1).

Reason for Scope Determination The CO System does not perform any safety-related system intended functions that meet the scoping criteria in 10 CFR 54.4(a)(1).

The CO System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function, The CO System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1). Therefore, the CO System meets the scoping criteria of 10 CFR 54.4(a)(2).

The CO System is not relied upon to demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events.

FSAR References Section 1.2.2.12.16 of the FSAR describes the CO System.

License Renewal Drawings The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

LR-M513, LR-M783 Insert:", LR-M514-1" Components Subiect to AMR Table 2.3.4-2 lists the component types that require AMR and their intended functions.

Table 3.4.2-2, Aging Management Review Results - Condensate (Auxiliary) System, provides the results of the AMR.

Scoping and Screening Results Page 2.3-166 darmeaf2440-IAmendment I

6) aa a Columbia Generating Station License Renewal Application Technical Information Table 2.3.4-2 Condensate (Auxiliary) System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Bolting Structural integrity Condenser Structural integrity Piping Structural integrity Pump casing Structural integrity Valve body Structural integrity n s elnsrt A f rom p a ge 2. 3 -16 7 a

,I Scoping and Screening Results Page 2.3-167

!Amendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to Table 2.3.4-2:

Tank Structural integrity Amendment 1 Scoping and Scoping Screening Results and Screening Results Page 2.3-167a Page 2.3-167a Amendment 1

W ;i>$

Columbia Generating Station License Renewal Application Technical Information

• Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program

• Flow-Accelerated Corrosion (FAC) Program

• Selective Leaching Inspection 3.4.2.1.2 Condensate (Auxiliary) System Materials The materials of construction for subject mechanical components of the Condensate (Auxiliary) System are:

• Gray cast iron o Steel Environments Subject mechanical components of the Condensate (Auxiliary) System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

• Air-outdoor Add: "Moist air"

• Treated water > 60 OC (140 oF)

Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Condensate (Auxiliary) System:

• Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Condensate (Auxiliary) System:

• Bolting Integrity Program

• BWR Water Chemistry Program

• Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program Add: "Supplemental Piping/Tank

-Inspection" Aging Management Review Results Page 3.4-3 --- Jafl-afy-204O--

Amendmnt 1I

Columbia Generating Station License Renewal Application Technical Information Table 3.4.1 Summary of Aging Management Programs for Steam and Power Conversion Systems Evaluated in Chapter VIII of NUREG-1801 Further tem Component/Commodity Aging Effect/ Aging Management Evaluation Discussion Number Mechanism Programs Recommended 3.4.1-04 Steel piping, piping components, Loss of material due Water Chemistry and Yes, detection of Consistent with NUREG-1801.

and piping elements exposed to to general, pitting One-Time Inspection aging effects is treated water and crevice to be evaluated T-h 'RAVai-fter=ristry

• BV corrosion tr ugTnuncttonr~thfrh~e

-Ch-emstfy Progror-

-E-ffecti~er~ess-l

-rntra Gl fo" "ii , 'ipflg-

"to am~peonnt-&, _-Ad rpiping elcmcnte inthoaefi&

PWF-G9ecdt Rc~etcd ,"ytefa Refer to Section 3.4.2.2.2.1 for further information.

Insert A from page 314-14a

-Jaffuai'y-z201 Aging Management Review Results Page 3.4-14 Aedet

Columbia Generating Station License Renewal Application Technical Information Insert A to Paae 3.4.-14 The BWR Water Chemistry Program, in conjunction with the Chemistry Program Effectiveness Inspection, is credited to manage loss of material for steel piping, piping components, piping elements and tanks in the steam and power conversion systems exposed to treated water, including treated water >60 OC (140 OF).

Page 34-14a Amendment 1 Aging Management Results Review Results Management Review Page 3.4-14a Amendment 1

w ~

Columbia Generating Station License Renewal Application Technical Information Table 3.4.2-2 Aging Management Review Results - Condensate (Auxiliary) System Aging Effect NUREG-Row Component Intended MaterialAging Management 1801 Table Notes No. Type Function(s) Management Program Volume 1 Item 2 Item Air-indoor3.1 Structural Ai-no r3.4.1- 1 18 Valve Body integrity Steel uncontrolled None None VIII.H-7 28 0406 (External)

Structural Loss of External Surfaces 3.4.1- C 19 Valve Body integrity Steel uncontrolled material Monitoring VIII.H-7 28 0404 (Internal) I 20 Valve Body Structural integrity Steel Air-indoor uncontrolled Loss of External Surfaces mtraMoirngVIII.H-7 3.4.1-28A (External) material Monitoring 28 Add new rows 21 through 25 to Table 3.4.2-2 as shown on pages 3.4-43a Aging Management Review Results Page 3.4-43 1Amendment 1

Lt3 P-5 Columbia Generating Station License Renewal Application Technical Information Table 3.4.2-2 Aging Management Review Results - Condensate (Auxiliary) 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 Tank (CO- Structural Air-indoor Loss of External Surfaces VIIH7 3.4.1- C 21 TK-4) integrity Steel uncontroll)e material Monitoring 28 0404 (Internal)

Tank (CO- Structural Moist air Loss of Supplemental 22 TK-4) integrity Steel (internal) material Piping/Tank N/A N/A G Inspection Treated 23 Tank (CO- Structural Steel water > 60 'C Loss of BWR Water VIII.E-33 3.4.1- C TK-4) integrity (140 -F) material Chemistry 04 (Internal)

Treated Chemistry Program.

24 Tank (CO- Structural Steel water > 60 °C Loss of Effectiveness VIII.E-33 3.4.1- C TK-4) integrity (140 'F) material Inspection 04 (Internal)

Tank (CO- Structural Steel Air-indoor Loss of External Surfaces VIII.H-7 3.4.1- A 25 TK-4) integrity uncontrolled material Monitoring 28 I__

__I___I___I_ (External) _ _ _ _ I__ __ _ __I__ _ I__

__ _I_ _

Page 3.4-43a Amendment 1 Aging Management Review Aging Review Results Results Page 3.4-43a Amendment 1

Columbia Generating Station License Renewal Application Technical Information B.2.51 Supplemental Piping/Tank Inspection Program Description The Supplemental Piping/Tank Inspection is a new one-time inspection that will detect and characterize the material condition of steel, gray cast iron, and stainless steel components that are exposed to moist air environments, particularly the aggressive alternate wet and dry environment that exists at air-water interfaces or air spaces of susceptible piping and tanks. The inspection provides direct evidence as to whether, and to what extent, loss of material due to crevice, galvanic, general, and pitting corrosion, or MIC has occurred or is likely to occur that could result in a loss of intended function of the subject components.

Implementation of the Supplemental Piping/Tank Inspection will ensure that the pressure boundary integrity of susceptible safety-related components is maintained consistent with the current licensing bases during the period of extended operation.

Implementation of the inspection will also ensure that the structural integrity of susceptible NSR components will be maintained such that spatial interactions (e.g.,

leakage) will not result in the loss of any safety-related component intended functions during the period of extended operation.

NUREG-1801 Consistency The Supplemental Piping/Tank Inspection is a new one-time inspection for Columbia that will be consistent with the 10 elements of an effective aging management program as described in NUREG-1801,Section XI.M32, "One-Time Inspection."

Exceptions to NUREG-1801 None.

Aging Management Program Elements The results of an evaluation of each program element are provided below.

Scope of Program The scope of the Supplemental Piping/Tank Inspection includes the internal and external surfaces of steel, gray cast iron, and stainless steel components at air-water interfaces and other susceptible locations in the following systems:

o Condensate (Nuclear) (COND) Syster\_ Add: "Condensate (Auxiliary) (CO)

• Containment Vacuum Breakers (CVB) System"

• Diesel Cooling Water (DCW) System o Equipment Drains Radioactive (EDR) System Aging Management Programs Page B-197 -r-anuar-2y-l-e-lAmendment 1 r

Columbia Generating Station 2.3-43 Condensate (Nuclear) (COND) System License Renewal Application Technical Information License Renewal Drawings The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

LR-M504-2, LR-M526-1, LR-M527-1 Components Subiect to AMR Table 2.3.4-3 lists the component types that require AMR and their intended functions.

Table 3.4.2-3, Aging Management Review Results - Condensate (Nuclear) System, provides the results of the AMR.

The condenser tubes are not subject to AMR because they do not perform a license renewal intended function of the COND System.

Scoping and Screening Results Page 2.3-169 Januag4-Amendment 1

W) Ž3-)-

Columbia Generating Station License Renewal Application Technical Information Table 2.3.4-3 Condensate (Nuclear) System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Bolting Pressure boundary Structural integrity Heat exchanger (shell) Pressure boundary Pressure boundary Orifice Structural integrity Throttling Piping Pressure boundary Structural integrity Structural integrity Pump casing Pressure boundary Tank (COND-TK-IA, COND-TK-18)

Pressure boundary Tubing Structural integrity i

Pressure boundary Valve body Structural integrity

""*'*Insert A from page 2.3-1 70a Scoping and Screening Results Page 2.3-170

=Amendment 1 -J

• . ~LJ Xz3- D Columbia Generating Station License Renewal Application Technical Information Insert A to Table 2.3.4-3:

Flexible connection Structural integrity Scoping and Screening Results Page 2.3-170a Amendment 1

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 Requiring1801 Table No. Type Function(s) Management Program Volume 1 Item 2 Item Structural Stainless Air-indoor 3.4.1-78 Valve Body uncontrolled None None VIII.1-10 A 7 Va y integrity Steel (External) 41 79 Structural Stainless Condensation Loss of External Surfaces N/A N/A G Valve Body integrity Steel (External) material Monitoring 80 Valve Body Structural Steel Treated water Loss of BWR Water VIIIE-33 3.4.1- A integrity (Internal) material Chemistry 04 Structural Steea(vteral) Treated water Loss of ateil Chemistry Program Effectiveness VIII.E-33 341-04 81 Valve Body integrity (internal) material Inspection 04 Structural Air-indoor Loss of External Surfaces 3.4.1-82 Valve Body integrity Steel uncontrolled material Monitoring 28 (External) materialMnitoring _2 83 Valve Body Structural Steel Condensation Loss of External Surfaces Vlll.H-10 3.4.1- A integrity (External) material Monitoring 28 Insert new rows 84 through 87 to Table 3.4.2-3 as shown on page 3.4-53a Aging Management Review Results Page 3.4-53 eJanarymMOn-

[AmendmentF I

L) PL3-5 Columbia Generating Station License Renewal Application Technical Information Table 3.4.2-3 Aging Management Review Results - Condensate (Nuclear) System Aging Effect Aging NUREG- Table Row No. Component Type Intended IFunction(s) Material Environment Requiring Management1 1801 1 Notes Noe F Management Program Volume 2 Item I Item Flexible Structural Steel Treated water Loss of BWR Water VIII.E-33 3.4.1- A 84 Connection integrity (Internal) material Chemistry 04 Flexible Structural Steel Treated water Loss of Chemistry VIII.E-33 3.4.1- A 85 Connection integrity (Internal) material Program 04 Effectiveness Inspection Flexible Structural Steel Air-indoor Loss of External VIII.H-7 3.4.1- A 86 Connection integrity uncontrolled material Surfaces 28 (External) Monitoring Flexible Structural Steel Condensation Loss of External VIII.H-10 3.4.1- A 87 Connection integrity (External) material Surfaces 28 Monitoring Page 3.4-53a Amendment 1 Aging Aging Management Results Review Results Management Review Page 3.4-53a Amendment 1

Columbia Generating Station License Renewal Application Technical Information 2.3.3.2 Condensate Processing Radioactive (Demineralizer) (CPR) System

System Description

The CPR System, also referred to as the Condensate Filter Demineralizer System, is designed to maintain feedwater quality such that the reactor water limits are not exceeded. The system removes corrosion products, condenser inleakage impurities, and impurities present in the condensed steam. The system controls the condensate impurity concentration during plant operation. The system functions as a chemical mixing and supply system to clean the filter demineralizer units and direct the waste to the chemical waste system, as a backwash system to remove the spent resin from the filter demineralizers and direct the waste to the backwash receiving tank, and as a precoat system to circulate fresh precoat material through the filter demineralizers.

Reason for Scope Determination The CPR System does not perform any safety-related system-intended functions that meet the scoping criteria of 10 CFR 54,4(a)(1).

The CPR System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The CPR System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory.

accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1).

Therefore, the CPR System meets the scoping criterion of 10 CFR 54.4(a)(2).

The CPR System is not relied upon to demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events.

FSAR References Section 10.4.6 of the FSAR describes the Condensate Filter Demineralizer System, evaluated for license renewal as the Condensate Processing Radioactive (Demineralizer) System.

License Renewal Drawings The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

LR-M523-1, LR-M526-1 LR-M536'I I___--*nsert' Components Subiect to AMR Table 2.3.3-2 lists the component types that require AMR and their intended functions.

Table 3.3.2-2, Aging Management Review Results - Condensate Processing Radioactive (Demineralizer) System, provides the results of the AMR.

Scoping and Screening Results Page 2.3-38 J t f

[Amendment 1

Ld -

Columbia Generating Station License Renewal Application Technical Information 2.3.3.23 Floor Drain (FD) System

System Description

The FD System consists of non-radioactive floor drain subsystems in the Service Building and Turbine Building.

Floor drains from normally uncontaminated areas of the Turbine Building are collected in three sumps. All three sumps are routed to the Radwaste System for processing.

Floor drains in the Service Building are collected in a single sump containing two sump pumps. Water collected in the Service Building floor drain sump is pumped to the storm water drainage system. Water collected by the storm water drainage system is conveyed by a concrete pipe to a point approximately 1,500 feet northeast of the plant.

The pipe discharges to an earthen channel that carries the water to a small unlined evaporation and percolation pond. Roof drains, which are evaluated as part of the FD System, are drained by gravity or pumped to the storm drain system.

Reason for Scope Determination The FD System contains components designated as safety-related by Columbia choice.

Therefore, the FD System meets the scoping criteria of 10 CFR 54.4(a)(1).

The FD System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The FD System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1). Therefore, the FD System meets the scoping criteria of 10 CFR 54.4(a)(2).

The FD System is not relied upon to demonstrate compliance with any regulated event and does not meet the 10 CFR 54.4(a)(3) scoping criteria.

FSAR References Section 9.3.3.2.3 of the FSAR describes the Nonradioactive Water Drainage System, and the Roof Drain System, evaluated collectively for license renewal as the Floor Drain System.

License Renewal Drawings The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

LR-M539, LR-M540, LR-M788-1, LR-M852, LR-216-01,3682 -

Scoping and Screening Results Page 2.3-98 Jan

[Amendment 1

b6 0q -

Columbia Generating Station 23.321 Equipment Drains Radioactive (EDR) System License Renewal Application Technical Information Reason for Scope Determination The EDR System provides Primary Containment isolation and integrity (including valve position indication), and secondary containment isolation and integrity (including valve position indication). These system-intended functions are safety-related. Therefore, the EDR System meet the scoping criteria of 10 CFR 54.4(a)(1).

The EDR System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The EDR System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1).

Therefore, the EDR System meets the scoping criteria of 10 CFR 54.4(a)(2).

The EDR System is relied upon to demonstrate compliance with, and meets the 10 CFR 54.4(a)(3) scoping criteria for, the Environmental Qualification (10 CFR 50.49) regulated event.

FSAR References Section 9.3.3.2.1 of the FSAR describes the Radioactive Equipment Drainage System, evaluated for license renewal as the Equipment Drains Radioactive System.

License Renewal Drawings The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal: Insert: ", LR-M532" LR-M521-2, LR-M523-2, LR-M537, LR-M539 Components Subiect to AMR Table 2.3.3-21 lists the component types that require AMR and their intended functions.

Table 3.3.2-21, Aging Management Review Results - Equipment Drains Radioactive System, provides the results of the AMR.

Solenoid pilot valves and the associated air lines provide a control air supply to actuators for the primary and secondary containment isolation valves (EDR-V-19, EDR-V-20, EDR-V-394, and EDR-V-395), Failure of the air supply places the valve in a safe position that supports the system function. Therefore, pressure boundary integrity is not a required component intended function of these solenoid valves, air supply lines, or actuators for the system to perform its intended function. Since these components have no other component intended function, they are not subject to AMR.

The external subcomponents (shell and channel covers) of the in-scope heat exchangers will contain fluid leakage in the event of a failure of an internal Scoping and Screening Results Page 2.3-90, JAmendment I ]J----'

Columbia Generating Station License Renewal Application Technical Information subcomponent (tubes and tubesheet). Failure of an internal subcomponent will therefore not create the potential for spatial interaction that could prevent a safety-related SSC from performing its intended function. As a result, the internal subcomponents (tubes and tubesheet) of the in-scope heat exchangers are not subject to AMR.

Table 2.3.3-21 Equipment Drains Radioactive System Components Subject to Aging Management Review Intended Function Component Type (as defined in Table 2.0-1)

Bolting Pressure Boundary Structural Integrity Heat exchanger (channel and shell) Structural Integrity Orifice Structural Integrity Piping Pressure Boundary Structural Integrity Sight glass Structural Integrity Tubing Structural Integrity Valve body Pressure Boundary Structural Integrity "In"nsert A from page 2,3-91a1 Scoping and Screening Results Page 2.3-91 AAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to Table 2.3.3-21:

Pump casing Structural Integrity Tank Structural Integrity Scoping and Screening Results Page 2.3-91 a Amendment 1

Columbia Generating Station License Renewal Application.

Technical Information

• Loss of pre-load o Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Diesel Lubricating Oil System:

• Bolting Integrity Program

• Chemistry Program Effectiveness Inspection

• Closed Cooling Water Chemistry Program o External Surfaces Monitoring Program

• Heat Exchangers Inspection

• Lubricating Oil Analysis Program

• Lubricating Oil Inspection 3.3.2.1.21 Equipment Drains Radioactive System Materials The materials of construction for subject mechanical components of the Equipment Drains Radioactive System are:

• Glass

• Stainless steel o Steel Environments Subject mechanical components of the Equipment Drains Radioactive System are exposed to the following normal operating environments:

• Air-indoor uncontrolled o Closed cycle cooling water

" Concrete Add "Moist Air" as a new bullet in the

• Raw water list of environment

• Treated water Aging Management Review Results Page 3.3-25 JAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801 Item Iter Component/Commodity Aging Effect/Mechanams IAging Management Further Evaluation Discussion Number Effect/Mechanism Programs Recommended 3.3.1-76 Steel piping, piping Loss of material Open-Cycle Cooling No Consistent with NUREG-1801, components, and piping due to general, Water System with exceptions.

elements (without lining/coating pitting, crevice, and or with degraded lining/coating) microbiologically Except as noted below, the exposed to raw water influenced Open-Cycle Cooling Water corrosion, fouling, Program is credited to manage and lining/coating loss of material for steel piping, degradation piping components, and piping elements that are exposed to raw water.

For steel piping and piping components in the other auxiliary systems that are exposed to raw water, the following programs are credited to manage loss of material:

• Diesel Starting Air Inspection for drain piping in Diesel Starting Air System

" Diesel Systems Inspection for drain piping in the Diesel (Engine) Exhaust System

" Monitoring and Collection

---

Systems Inspection for dfeai-eieet Replace deleted -ptpmJ in Equipment Drains Radioactive, Floor Drain, and text with: "drain Floor Drain Radioactive piping and tanks" systems Aging Management Review Results Page 3.3-104 4aftuafy-20+e-

cJ g;~-5 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-21 Aging Management Review Results - Equipment Drains Radioactive System Agg Effect A g NUREG-Row Component Intended Aging Efect ging 1801 Table No.

No.

Tympoen Type Functionds)

Function(s) Material Environment. Requiring Management Management Program Voum021 Volume 2 ITabemNotes 1 Item Item Treated Monitoring and 52 Valve Body Structural Steel water Loss of Collection VIIE3- 3.3.1- E integrity (Internal) material Systems 18 17 nnInspection Structural Air-indoor Loss of External 3.3.1-53 Valve Body integrity Steel uncontrolled Surfaces VII.l-8 58 A (External) material Monitoring Insert new rows 54 through 60 for Table 3.3.2-21 after this page Aging Management Review Results Page 3.3-232 -- Amendment jAmendment 1

• 1"

-

bJ 94-5 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-21 Aging Management Review Results - Equipment Drains Radioactive System I NUREG-Row Component Intended Aging Effect Aging 1801 Table Row Cmponen Fnctiond Material Environment Requiring Management 1801 1 Notes Management Program Volume 2 Item Item -Ie Pump Casing Structural Stainless Air-indoor 3.3.i- A 54 (EDR-P14A, uncontrolled None None VII.J-15 9.3.1- 6 14B, 15) integrity Steel (Internal) 94 0306 Monitoring and Pump Casing Structural Stainless Raw water Loss of Collection VII.C1- 3.3.1- E 14B, 15) integrity Steel (Internal) material Systems 15 79 Inspection Pump Casing Structural Stainless Air-indoor 3.3.1-56 (EDR-P14A, uncontrolled None None VII,J-15 A 14B, 15) integrity Steel (External)

Tank (EDR- Structural Air-indoor Loss of External 57 T an 4B, Strity Steel uncontrolled LossroflSurfaces VII.I-8 3.3.1- C TK-4A, 4B, 5) integrity (Internal) material Monitoring 58 0302 Tank (EDR- Structural Moist air Loss of Supplemental VII.H2- 3.3.1- E 58 TK-4A, 4B, 5) integrity Steel (Internal) material Piping/Tank 21 71 0303 TK-4, 4B 5) ntegityInspection Monitoring and 59 Tank (EDR- Structural Steel Raw water Loss of Collection VII.C1- 3.3.1- E TK-4A, 4B, 5) integrity (Internal) material Systems 19 76 Inspection Tank (EDR- Structural Air-indoor Loss of External 331 60 Tan 413, Strity Steel uncontrolled LossroflSurfaces VII.I-8 8- A TK-4A, 4B, 5) integrity (External) material Monitoring 58 Aging Management Review Results Page 3.3-232a Amendment 1

Columbia Generating Station 2.3.3.24 Floor Drains Radioactive (FDR) System License Renewal Application Technical Information FDR-V-3 and FDR-V-4). These system-intended functions are safety-related.

Therefore, the FDR System meets the scoping criteria of 10 CFR 54.4(a)(1).

The FDR System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The FDR System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1).

Therefore, the FDR System meets the scoping criteria of 10 CFR 54.4(a)(2).

The FDR System is relied upon to demonstrate compliance with, and meets the 10 CFR 54.4(a)(3) scoping criteria for, the Environmental Qualification (10 CFR 50.49) regulated event.

FSAR References Section 9.3.3.2.2 of the FSAR describes the Radioactive Floor Drainage Subsystem, evaluated for license renewal as the Floor Drain Radioactive System.

License Renewal Drawin-gs The following license renewal drawing depicts the evaluation boundaries for the system components within the scope of license renewal:

LR-M539* .... *-*ert: ",LR-M531"]

LR-M539 <-

Components Subiect to AMR Table 2.3.3-24 lists the component types that require AMR and their intended functions.

Table 3.3.2-24, Aging Management Review Results - Floor Drain Radioactive System, provides the results of the AMR.

Solenoid pilot valves and associated air lines provide a control air supply to actuators for the primary and secondary containment isolation valves (FDR-V-3, 4, and 219 through 222). Failure of the air supply places the valve in a safe position that supports the system function. Therefore, pressure boundary integrity is not a required component intended function of these solenoid valves, air supply lines, or actuators for the system to perform its intended function. Since these components have no other component intended function, they are not subject to AMR.

Spectacle flanges (FDR-SF-1 and 2) are normally open. As such the spectacle does not perform any license renewal function and is not subject to AMR. The flange portion of the component is evaluated as piping.

Scoping and Screening Results Page 2. 3-101

Columbia Generating Station License Renewal Application Technical Information Table 2.3.3-24 Floor Drain Radioactive System Components Subject to Aging Management Review CnIntended Function (as defined in Table 2.0-1)

Bolting Pressure Boundary Structural Integrity Orifice Structural Integrity Piping Pressure Boundary Structural Integrity Tubing Structural Integrity Valve body Pressure Boundary Structural Integrity Scoping and Screening Results Page 2.3-102 JAmendm ent 1

Columbia Generating Station License Renewal Application Technical Information Insert A to Table 2.3.3-24:

Pump casing Structural Integrity Tank Structural Integrity Amendment 1 Scoping and Scoping Screening Results and Screening Results Page 2.3-102a Page 2.3-102a Amendment 1

Columbia Generating Station License Renewal Application Technical Information 3.3.2.1.24 Floor Drain Radioactive System Materials The materials of construction for subject mechanical components of the Floor Drain Radioactive System are:

• Stainless steel

• Steel Environments Subject mechanical components of the Floor Drain Radioactive System are exposed to the following normal operating environments:

• Air-indoor uncontrolled Add "Moist ir" s

• Concrete new bullet in the o Raw water list of environments

• Treated water Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Floor Drain Radioactive System:

o Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Floor Drain Radioactive System:

• Bolting Integrity Program o BWR Water Chemistry Program o Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program

• Monitoring and Collection Systems Inspection

• Supplemental Piping/Tank Inspection

[Amendment 1 Aging Management Review Results Page 3.3-29 iJaudy-2010

Lu ; Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-24 Aging Management Review Results - Floor Drain Radioactive System NUREG-Row Component Intended Material Environment Aging EfcAging 1801 Table Notes No. Type Function(s) Requiring Management Volume 2 1 Item Management Program Item Monitoring and 37 Structural Stainless Raw water Loss of Collection VII.C1- 3.3.1- E Valve Body integrity Steel (Internal) material Systems 15 79 Inspection 38 Vle oy Structural integrity Stainless Steel Air-indoor (External) 3.3.1-38 Valve Body uncontrolled None None VII.J-15 94 A (Extr-nal) xera Structural Air-indoor Loss of External 3.3.1- C 39 Valve Body integrity Steel uncontrolled material Surfaces VII.I-8 58 0302 (Internal) Monitoring Monitoring and 40 Valve Body Structural Raw water Loss of Collection VII.C1- 3.3.1- E integrity Steel (Internal) material Systems 19 76 Inspection 41 Valve Body Structural Steel Air-indoor Loss of External 33.1-integrity uncontrolled (External) material Surfaces Monitoring VII.I-8 58A 58 Insert new rows 42 through 47 for Table 3.3.2-24 after this page Aging Management Review Results Page 3.3-263 janlary -201U0 IAmendment 1 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-24 Aging Management Review Results - Floor Drain Radioactive System Row Component Intended Maeil Eniomnt Aging Rqiing Effect Aging Mfet angemnt TNUREG-1801 Table Noe No. Type Function(s) Material Environment Requiring Management Volume 2 1 Item Notes Management Program Item Monitoring and 42 Pump Casing Structural Stainless Raw water Loss of Collection VII.C1- 3.3.1- E (FDR-P-21) integrity Steel (Internal) material Systems 15 79 Inspection Pump Casing Structural Stainless Air-indoor 3.3.1-43 Pump intrity Steel uncontrolled None None VII.J-15 94 A (FDR-P-21) integrity Steel (External) 94 Tank (FDR- Structural Air-indoor Loss of External 3.3.1- C 44 TK-9) integrity Steel uncontrolled material Surfaces VII.t-8 58 0302 (Internal) Monitoring Tank (FDR- Structural Moist air Loss of Supplemental VII.H2- 3.3.1- E 45 TK-9) integrity (Internal) material Piping/Tank 21 71 0303 TK-9)interityInspection Monitoring and 46 Tank (FDR- Structural Steel Raw water Loss of Collection VII.C1- 3.3.1- E TK-9) integrity (Internal) material Systems 19 76 Inspection Tank (FOR- Structural Air-indoor Loss of External 3.3.1-Tk intrity Steel uncontrolled LossroflSurfaces VII.I-8 58 A (External material Monitoring Aging Management Review Results Page 3.3-263a Amendment 1

&i)LT -I Columbia Generating Station License Renewal Application Technical Information Table 2.2-1 License Renewal Scoping Results for Mechanical Systems. (continued)

, I Screening Results System Name In Scope? Section Floor Drain Radioactive. Yes 23.3.24 Fuel Oil Yes. 2.3.3.18 Fuel Pool Cooling Yes 2.3.3.25 Glycol No Guard House Exhaust Air No.

Guard House Fire Protection No Guard House Mixed Air No Guard House Outside Air No Guard House Potable Hot Water No Guard House Return Air No Heater Drain No Heater Vents No Heating Hot Water No

.. ~-,.. __

Heating Steam EEF Heating Steam Condensate Te Tý -> -No- ~3.49

..... ...

Heating Steam Vent [Yes Ne

~.50 High-Pressure Core Spray Yes 2.3.2.3 Hydrogen No Hydrogen Water Chemistry No Independent Spent Fuel Storage Installation No Instrument Rack Yes 2.3.3.40 lsophase Bus Duct Cooling No.

Laboratory Equipment (Permanent Plant) No Leak Detection Yes 2.3.3.26 Local Power Range Monitor Yes 2.3.1.2 Low-Pressure Core Spray Yes 2.3,2,4 Machine Shop Equipment No Main Steam Yes 2.3.4.4 Plant-Level Scoping Results Page-2,2-4

. ....... . . ...

jAmnendm~e

Columbia Generating Station License Renewal Application Technical. Information Leak Detection (LD) System (Section 2.3.326)

Miscellaneous Waste Radioactive (MWR) System (Section 2.3.3.27)

Plant Sanitary Drains (PSD) System (Section 2.3.3,28)

Plant Service Water (TSW) System (Section 2.3.3.29)

Potable: Cold Water (PWC) System (Section 2.3.3.30)

Potable, Hot Water (PWH) System (Section 2.,3.3.31)

Primary Containment (c) System (Section 2.3.3.32)

Process Sampling (PS) System (Section 2.3.3.33)

Process.Sampling Radioactive (PSR) System (Section 2.3.3.34)

Pump House HVAC Systems (Section 2.33.35)

Radwaste Building Chilled Water (WCH) System :(Section 2.3.3.36)

Radwaste .Building HVAC Systems (Section 2.3.3.37)

Reactor Building, HVAC Systems (Section 2.3.3.38)

Reactor Closed Cooling Water (RCC) System (Section 2.3.3.39)

Reactor Protection, System (RPS). (Section 2.3.3.40)

Reactor Water Cleanup .(RWCU) System (Section 2.33,341)

Service Air (SA) System (Section 2.3.3.42)

Standby Liquid Control (SLC) System (Section 2.33.43)

StandbyService Water (SW) System (Section 2.3,3,44)

Suppression. Pool Temperature Monitoring (SPTM) System (Section .2.3.3.45)

Tower Makeup Water (TMU) System (Section 2.3.3,46)

Traversing Incore Probe (TIP) System (Section 2.3.3.47)

A brief system, description, reasoný for scope determination, associated,: FSAR references, associated license renewal drawings, and components subject to AMR information are, provided for each system.

Seaing Steam )7,*c ion, 23.3.48)

H...

Hea*iig Stea ~cnd ~ef~Sae'ir2.3.

Heating a Sea entiR suy m (St 2.3 Pign ;3.5 Scoping and Screening Results Page 2.3-35 ~oy .1

!Arendrnent 1 **>

6A) 1r-3 Columbia Generating Station License, Renewal Application Technical Information Table 2.3.3-44 Traversing Incore Probe.System Components Subject tO Aging Management Review Component Type Intended Function.

(as defined In Table 2.0-1)

Bolting Pressure Boundary Structural Integrity Chamber shield, Structural Integrity:

Piping Pressure Boundary Structural Integrity_

Valve body Pressure Boundary Structural Integrity,

~o~j 2f d~lviq 7hi7; Scoping and Screening Results Page 2.3-162, Amendment 1

U-3)LI Columbia Generating Station License Renewal Application Technical Information 2.3.3.48 Heating Steam System

System Description

The Heating Steam (HS) System originates from four pressure reducing stations (two in the Turbine Generator Building and one each in the Reactor and Radwaste buildings).

Steam at 200 psig pressure is supplied to these pressure, reducing stations from either the auxiliary boiler or the gland steam evaporator. At the pressure reducing stations, the steam pressure is reduced to 50 psig and this steam is fed to the heating coils, humidifiers, steam unit heaters, andc hot water heat exchanger.

Reason for Scope Determination The HS System does not perform any safety-related system intended functions that meet the scoping criteria of 10 CFR 54.4(a)(1).

The HS System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The HS System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that, could prevent the satisfactory accomplishment of one or more of the. functions identified in 10 CFR 54.4(a)(1). Therefore, the HS System meets the scoping criteria of 10 CFR 54.4(a)(2)-.

The HS System is not relied upon to demonstrate compliance with the 10 CFR.54.4(a)(3) scoping criteria for any regulated events.

FSAR References Section 9.4.16.2 of the FSAR describes the Heating Steam System.

License Renewal Drawings The following licene renewal drawing depicts the evaluation boundaaýfris te syste-m

--

components within the scope of license renewal:

LR-M514-1 Components assigned by equipment piece number (EPN) to the Radwaste Building Mixed Air (WMA), Radwaste Building Outside Air (WOA), and Radwaste Building Return Air (WRA) systems are included within the evaluation boundaries of the HS System for completeness (see LR-M514-1).

Page 2.3~162a Amendment 1 Scoping and Screening Results and Screening Results Page 2.3-162a Amendment 1

Columbia Gererating Station License Renewal Application Technical Information Components Subiect to AMR Table 2.3.3-45 lists the component types that require AMR and their intended functions, Table 3.3,2-45, Aging Management Review Results:- Heating Steam System, provides the results of the.AMR.

Table 2,3;3-45.

Heating Steam System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Bolting Structural integrity Heat exchanger (heating. coil headers) Structural integrity Heat exchanger (heating coil tubes) Structural integrity Humidifier Structural. integrity Piping. Structural integrity Strainer (body) Structural integrity Trap body Structural integrity Tubing, Structural integrity Valve body Structural integrity Amendment 1 and Screening Scoping and Scoping Results Screening Results Page 23-162b Page 2,3-162b Amendment 1

1w P~-7 Columbia Generating Station 3.3 Aging Management of Auxiliary Systems License Renewal Application Technical Information

• Fire Protection System (Section 2.3.3.22)

• Floor Drain System (Section 2.3.3.23) o Floor Drain Radioactive System (Section 2.3.3.24)

" Fuel Pool Cooling System (Section 2.3.3.25)

• Miscellaneous Waste Radioactive System (Section 2.3.3.27)

• Plant Sanitary Drains System (Section 2.3.3.28) o Plant Service Water System (Section 2.3.3.29)

• Potable Cold Water System (Section 2.3.3.30)

• Potable Hot Water System (Section 2.3.3.31)

• Primary Containment System (Section 2.3.3.32) o Process Sampling System (Section 2.3.3.33)

• Process Sampling Radioactive System (Section 2.3.3.34)

• Pump House HVAC Systems (Section 2.3.3.35)

• Radwaste Building Chilled Water System (Section 2.3.3.36)

° Radwaste Building HVAC Systems (Section 2.3.3.37)

• Reactor Building HVAC Systems (Section 2.3.3.38)

• Reactor Closed Cooling Water System (Section 2.3.3.39)

• Reactor Water Cleanup System (Section 2.3.3.41)

• Service Air System (Section 2.3.3.42)

• Standby Liquid Control System (Section 2.3.3.43) o Standby Service Water System (Section 2.3.3.44)

• Tower Makeup Water System (Section 2.3.3.46) page 3,3-2a f (Section 2.3.3.47)

• Traversing Incore Probe System Table 3.3.1, Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801, provides the summary of the programs evaluated in NUREG-1801 that are applicable to component and commodity groups in this section.

Text addressing summary items requiring further evaluation is provided in Section 3.3.2.2.

Aging Management Review Results Page 3.3-2 --Janua-40--

Amendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.3.1

" Heating Steam System (Section 2.3.3.48)

• Heating Steam Condensate System (Section 2.3.3.49)

• Heating Steam Vent System (Section 2.3.3.50)

Page 3.3-2a Amendment 1 Aging Review Results Management Review Aging Management Results Page 3.3-2a Amendment 1

(A)

Columbia Generating Station 3.3.2 Results License Renewal Application Technical Information Table 3.3.2-39 Aging Management Review Results - Reactor Water Cleanup System Table 3.3.2-40 Aging Management Review Results - Service Air System Table 3.3.2-41 Aging Management Review Results - Standby Liquid Control System Table 3.3.2-42 Aging Management Review Results - Standby Service Water System Table 3.3.2-43 Aging Management Review Results - Tower Makeup Water System Table 3.3.2-44 Aging Management Review Results - Traversing Incore Probe System i~Add Insert A from page 3.3-5a 3.3.2.1 Materials, Environments, Aging Effects Requiring Management, and Aging Management Programs The materials from which specific components and commodities are fabricated, the environments to which they are exposed, the aging effects requiring management, and the aging management programs used to manage these aging effects are provided for each of the above systems in the following sections.

3.3.2.1.1 Circulating Water System Materials The materials of construction for subject mechanical components of the Circulating Water System are:

" Concrete

" Gray cast iron

• Stainless steel

• Steel Environments Subject mechanical components of the Circulating Water System are exposed to the following normal operating environments:

• Air-outdoor

• Raw water

• Soil Aging Management Review Results Page 3.3-5 --- tarruary-22041

'Arendtent1

J A-5 Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.3.2 Table 3.3.2-45 Aging Management Review Results - Heating Steam System Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate System Table 3.3.2-47 Aging Management Review Results - Heating Steam Vent System Results Page 3.3-5a Amendment 1 Aging Management Review Aging Management Review Results Page 3.3-5a Amendment 1

Columbia Generating Station 3.3,2 Results License Renewal Application Technical Information

• External Surfaces Monitoring Prograr _as shown on pages 3.3-50a through d4 3.3.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1801 For the Auxiliary Systems, those items requiring further evaluation are addressed in the following sections.

3.3.2.2.1 Cumulative Fatigue Damage Fatigue is a time-limited aging analysis, as defined in 10 CFR 54.3. Time-limited aging analyses are required to be evaluated in accordance with 10 CFR 54.21(c). Time-limited aging analyses identified for fatigue in the Auxiliary Systems are evaluated in Section 4.3.4.

3.3.2.2.2 Reduction of Heat Transfer due to Fouling As described in Table 3.3.1, the Fuel Pool Cooling System has stainless steel heat exchanger tubes in treated water which are evaluated under item number 3.3.1-03.

Fouling of stainless steel heat exchanger tubes in treated water is managed by the BWR Water Chemistry Program, in conjunction with the Heat Exchangers Inspection.

3.3.2.2.3 Cracking due to Stress Corrosion Cracking (SCC) 3.3.2.2.3.1 BWR Standby Liquid Control System The treated water environment for the Standby Liquid Control System uses an aqueous solution of sodium pentaborate decahydrate. The system is normally in standby with the fluid temperature maintained above the 601F saturation temperature in an area where the ambient temperature is less than 1000 F during normal plant operation. Since the temperature is below 1401F during normal plant operation, cracking due to SCC is not an aging effect requiring management for the stainless steel components of the Standby Liquid Control System.

3.3.2.2.3.2 Heat Exchanger Components As described in Table 3.3.1, there are no components compared to item number 3.3.1-

05. The Reactor Water Cleanup regenerative and non-regenerative heat exchangers at Columbia have no stainless steel components subject to AMR. Therefore, cracking of these components due to stress corrosion cracking is not an aging effect requiring management. Refer to item 3.3.1-48 (no further evaluation required) for the aging effects that do require management for these components.

3.3.2.2.3.3 Diesel Engine Exhaust Piping, Piping Components, and Piping Elements During normal plant operations, diesel exhaust piping, piping components, and piping elements are exposed to diesel exhaust infrequently and for short durations. For the remaining time, these components are exposed internally to outdoor air. As such, temperatures above 140OF occur only infrequently and for short durations. Therefore, cracking due to SCC is not identified as an aging effect requiring management for Aging Management Review Results Page 3.3-50 ,4*--

9it

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information 3.3.2.1.45 Heating Steam System Materials The materials of construction for subject mechanical components of the Heating Steam System are:

o Copper alloy

" Gray cast iron

" Stainless steel

• Steel Environments Subject mechanical components of the Heating Steam System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

• Steam Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Heating Steam System:

• Cracking

• Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Heating Steam System:

• Bolting Integrity Program

• BWR Water Chemistry Program

• Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program Aging Management Review Results Page 3.3-50a Amendment 1

60 Columbia Generating Station License Renewal Application Technical Information

• Flow-Accelerated Corrosion (FAC) Program

" Selective Leaching Inspection 3.3.2.1.46 Heating Steam Condensate System Materials The materials of construction for subject mechanical components of the Heating Steam Condensate System are:

" Copper alloy

" Gray cast iron

• Steel Environments Subject mechanical components of the Heating Steam Condensate System are exposed to the following normal operating environments:

• Air-indoor uncontrolled o Moist Air

• Steam

• Treated water > 60 'C (140 'F)

Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Heating Steam Condensate System:

• Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Heating Steam Condensate System:

• Bolting Integrity Program Aging Management Review Results Page 3.3-50b Amendment 1

Columbia Generating Station License Renewal Application Technical Information an aggressive environment. Therefore, loss of material due to pitting and crevice corrosion is not an aging effect requiring management for these components.

3.3.2.2.10.7 Stainless Steel Piping, Piping Components, and Piping Elements - Soil As-desearibgdn-a4ýý4,eree-a-ae~-r¢omponents-Gempared-to-,i-tem--pmber-3-. *-

29-.Th ee-is-n-tainless-steel-piping-subje4t-to--AMR-for-Oolumbia-that-isexposed-to ssotin-the-Au.x-iliar-y-system - Replace with Insert A on page 3.3-55a 3.3.2.2.10.8 BWR Standby Liquid Control System Loss of material due to pitting and crevice corrosion for stainless steel piping components and tanks exposed to sodium pentaborate solution is managed by the BWR Water Chemistry Program. The BWR Water Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Program Effectiveness Inspection will provide a verification of the effectiveness of the tBWR Water Chemistry Program to manage loss of material due to pitting and crevice corrosion through examination of stainless steel piping components and tanks exposed to sodium pentaborate solution.

3.2.2.11 Loss of Material due to Pitting, Crevice, and Galvanic Corrosion As-der~bed--T-ab~le-..*hew -e- n-c mpent-~aredi~tem nwumber 3-3-.1-3-- eopper-alloy-piping,-piping-components-.or-piping-elem~ents-in t~he-Au~xifiary.-syste ms-t-ha-t-are-e~xposed-to--r-ea~ted-w-ater-.

3.3.2.2.12 Loss of Material due to Pitting, Crevice, and Microbiologically Influenced Corrosion 3.3.2.2.12.1 Piping, Piping Components, and Piping Elements - Fuel Oil There are no aluminum piping components exposed to fuel oil that are subject to AMR.

Loss of material due to pitting and crevice corrosion and MIC for stainless steel and copper alloy piping components exposed to fuel oil is managed by the Fuel Oil Chemistry Program. The Fuel Oil Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Program Effectiveness Inspection will provide a verification of the effectiveness of the Fuel Oil Chemistry Program to manage loss of material through examination of piping and components exposed to fuel oil.

3.3.2.2.12.2 Piping, Piping Components, and Piping Elements - Lubricating Oil Loss of material due to pitting and crevice corrosion and MIC for stainless steel piping components and heat exchanger components exposed to lubricating oil is managed by the Lubricating Oil Analysis Program. The Lubricating Oil Analysis Program manages aging effects through periodic monitoring and control of contaminants, including water.

The Lubricating Oil Inspection will provide a verification of the effectiveness of the Aging Management Review Results Page 3.3-55 January.2010 lAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.3.2.2.10.7 The Buried Piping Thanks Inspection Program, with enhancement, manages loss of material due to pitting and crevice corrosion and microbiologically influenced corrosion (MIC) for stainless steel piping and piping components buried in soil.

Insert B to LRA Section 3.3.2.2.11 Loss of material due to pitting, crevice, and galvanic corrosion for copper alloy piping, piping components, or piping elements exposed to treated water is managed by the BWR Water Chemistry Program. The BWR Water Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Program Effectiveness Inspection will provide a verification of the effectiveness of the BWR Water Chemistry Program to manage loss of material due to pitting, crevice, and galvanic corrosion through examination of copper alloy piping and piping components exposed to treated water.

Aging Management Review Results Page 3.3-55a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801 e AFurther Item Component/Commodity Aging Aging Management Evaluation Discussion Number Effect/Mechanism Programs Recommended 3.3.1-94 Stainless steel and nickel alloy None None NA - No AEM or Consistent with NUREG-1 801.

piping, piping components, and AMP piping elements exposed to No aging effects requiring air - indoor uncontrolled management are identified for (external) stainless steel piping, piping Sns ert: components, and piping "nheat elements in the auxiliary systems that are exposed to air-indoor exchanger uncontrolled (external).

components,"

cThis item is also applied to stainless steel accumulators, bolting, drain pans, duct, screens, and tanks that are exposed to air-indoor uncontrolled (external). A Note C is applied.

3.3.1-95 Steel and aluminum piping, None None NA - No AEM or Not applicable.

piping components, and piping AMP elements exposed to air- There are no steel or aluminum indoor controlled (external) piping, piping components, or piping elements in the auxiliary systems that are exposed to air-indoor controlled (external) All air-indoor environments were conservatively evaluated as uncontrolled environments.

Aging Management Review Results Page 3.3-115 [Aarenaet2&1-Amendment I

(A) ;L3 -

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-44 Aging Management Review Results - Traversing Incore Probe System Component Intended Aging Effect Aging NUREG-Row No. Type Function(s) Material Environment Requiring Management 1801 Table Notes Management Program Volume 1 Item 2 Intem 10 Piping Structural Stainless Air-indoor3.3.1-uncontrolled None None VII.J-15 33.1-A 0A 10 Piping integrity Steel (Internal) 94 0306 11 Piping Structural Stainless Gas None None VII J19 3.3.1- A integrity Steel (Internal) 97 Air-indoor Structural Stainless Ai-nor3.3.1-12 Piping Stegructu Stale uncontrolled None None VII.J-15 31 A gintegrity Steel (External)

Pressure Stainless Air-indoor3.3.1- A 13 Valve Body uncontrolled None None VII.J-15 3.3.1-6 13 ValveBy boundary Steel (Internal) 94 0306 14 Valve Body Pressure boundary Stainless Steel Gas (Internal) None None VII.J19 3.3.1-97 A Pressure Stainless Air-indoor 3.3.1-15 Valve Body uncontrolled None None VII.J-15 A yboundary Steel (External)

Air-indoor Structural Stainless Ai-nor3.3.1- A 16 Valve Body Stegrutua Stale uncontrolled None None VII.J-15 3.3.1-6 16 ValveBy integrity Steel (Internal) 94 0306 17 Valve Body Structural Stainless Gas None None VIIJ.19 3.3.1- A integrity Steel (Internal) 97 Structural Stainless Air-indoor 3.3.1-18 Valve Body uncontrolled None None VII.J-15 A yintegrity Steel (External)

Insert new LRA Tables 3.3.2-45, 3.3.2-46, and 3,3.2-47 after this page Aging Management Review Results Page 3.3-397 -Janrrua2010-j~menment

Way-Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-45 Aging Management Review Results - Heating Steam System Component Intended Aging Effect NUREG-Row Material Environment Requiring Aging Management 1801 Table Notes No. Type Function(s) Management Program 1 Volume Item 2 Item Structural Air-indoor Loss of 3.3.1-1 Bolting integrity itgiy(External)

Steel uncontrolled material Bolting Integrity VII.I-4 43 B Structural Loss of 3.3.1-2 Bolting integrity Steel uncontrolled pre-load Bolting Integrity VII.-5 B (External) 45 Heat 3 Exchanger Structural Steel Steam Loss of BWR Water N/A N/A G (header) integrity (Internal) material Chemistry (WOA-HC-1)

Heat Chemistry Program 4 Exchanger Structural Steel Steam Loss of Effectiveness N/A N/A G (header) integrity (Internal) material Inspection (WOA-HC-1)

Heat 5 Exchanger Structural Steel Steam Loss of Flow-Accelerated N/A N/A G (header) integrity (Internal) material Corrosion (FAC)

(WOA-HC-1)

Heat Air-indoor Exchanger Structural Steel uncontrolled Loss of External Surfaces VII.1-8 3.3.1- A (header) integrity (External) material Monitoring 58 (WOA-HC-1)

Heat Exchanger Structural Steam Loss of BWR Water 7 (header)SteN/ NA G (WRA-SUH-4, integrity (Internal) material Chemistry 5,6)

Heat Exchanger Structural Steam Loss of Chemistry Program 8 (header) rucr Steel Steam Lossrofl Effectiveness N/A N/A G (WRA-SUH-4, (Internal) material Inspection 1 5,6) 1 1 1 1 1 Aging Management Review Results Page 3.3-397a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-45 Aging Management Review Results - Heating Steam System nAging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801 Table Notes No. Type Function(s) Management Program Volume 1 Item 2 Item Heat Exchanger Structural Steam Loss of Flow-Accelerated 9 (header) integrity Steam Loss of Fo Acc N/A N/A G (WRA-SUH-4, Corrosion (FAC) 5,6)

Heat Exchanger Structural Air-indoor Loss of External Surfaces 3.3.1-10 (header) Steel uncontrolled VII.I- 8 A (WRA-SUH-4, integrity (External) material Monitoring 58 5,6)

Heat 1 Exchanger Structural Copper Alloy Steam Loss of BWR Water N/A N/A G (tubes) integrity (Internal) material Chemistry.

(WOA-HC-1) _

Heat Steam Loss of Chemistry Program 12 Exchanger Structural Copper Alloy teal sEffectiveness N/A N/A G (tubes) integrity (Internal) material N/A (WOA-HC-1)

Heat Air-indoor 13 Exchanger Structural Copper Alloy uncontrolled None None N/A N/A G (tubes) integrity (External)

(WOA-HC-1)

Heat Exchanger Structural Stainless Steam BWR Water 14 (tubes) Cakn / /

(WRA-SUH-1, integrity Steel (Internal) Cracking Chemistry N/A N/A G 3,4, 5)

Heat Exchanger Structural Stainless Steam Chemistry Program 15 (tubes) Cracking Effectiveness N/A N/A G (WRA-SUH-1, integrity Steel (Internal) Inspection 3,4,5)

Aging Management Review Results Page 3.3-397b Amendment 1

Columbia Generating Station License Renewal Application Technical Information Row No.

Component Type Table 3.3.2-45 Ro opnnneddAging Intended Function(s)

Aging Management Review Results - Heating Steam System Material Environment Requiring Management Aging Effect ffectNUREG-aaeet Aging Management Program 10 1801 Volume al Table 1 Item

{gn Notes 2 Item Heat Exchanger Structural Stainless Steam Loss of BWR Water 16 (tubes) integrity Steel (Internal) material Chemistry (WRA-SUH-1, 3,4, 5)

Heat Exchanger Structural Stainless Steam Loss of Chemistry Program 17 (tubes) material Effectiveness N/A N/A G (WRA-SUH-1, integrity Steel (Internal) Inspection 3,4,5)

Heat Exchanger Structural Stainless Air-indoor 331-18 (tubes) uncontrolled None None VII.J-15 C Steel (External) 94 (WRA-SUH-1, integrity 3,4. 5)

Humidifier 19 (WMA-HU-6, Structural Gray Cast Steam Loss of BWR Water N/A N/A G WOA-HU-4, integrity Iron (Internal) material Chemistry 5, 9)

Humidifier 20 (WMA-HU-6, Structural Gray Cast Steam Loss of Chemistry Program N/A N/A G WOA-HU-4, integrity Iron (Internal) material Effectiveness 5,9)

Humidifier 21 (WMA-HU-6, Structural Gray Cast Steam Loss of Flow-Accelerated N/A N/A G WOA-HU-4, integrity Iron (Internal) material Corrosion (FAC) 5,9)

Humidifier 22 (WMA-HU-6, Structural Gray Cast Steam Loss of Selective Leaching N/A N/A G WOA-HU-4, integrity Iron (Internal) material Inspection 5, 9)

Aging Management Review Results Page 3.3-397c Amendment 1

bU X-Xý Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-45 Aging Management Review Results - Heating Steam System RowMaterial Environment TAgiRequiring ng Effect Aging Management NUREG-1801 Table Notes No. Type Function(s) Management Program Volume 2 Item 1 Item Humidifier Air-indoor 23 (WMA-HU-6, Structural Gray Cast uncontrolled Loss of External Surfaces VII.I-8 3.3.1- A WOA-HU-4, integrity Iron (External) material Monitoring 58 5,9) 24 Piping Structural Steel Steam Loss of BWR Water N/A N/A G integrity (Internal) material Chemistry Structural Steam Loss of Chemistry Program 25 Piping integrity Steel (internal) material Effectiveness N/A N/A G Inspection 26 Piping Structural Steel Steam Loss of Flow-Accelerated N/A N/A G integrity (Internal) material Corrosion (FAC)

Structural Air-indoor Loss of External Surfaces 3.3.1-27 Piping integrity Steel uncontrolled (Etra) material Monitoring VII.I-8 VI-8 58 A 27 Ppinginterity(External) 28 Strainer Structural Copper Alloy Steam Loss of BWR Water N/A N/A G (body) integrity (Internal) material Chemistry Strainer Structural Steam Loss of Chemistry Program 29 (body) integrity Copper Alloy (Internal) material Effectiveness N/A N/A G Inspection Strainer Structural Air-indoor 30 Copper Alloy uncontrolled None None N/A N/A G (body) integrity (External) 31 Trap Body Structural Gray Cast Steam Loss of BWR Water N/A N/A G integrity Iron (Internal) material Chemistry Aging Management Review Results Page 3.3-397d Amendment 1

W ;JT- I Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-45 Aging Management Review Results - Heating Steam System Row Component Intended Material Aging Effect }NUREG-Environment Requiring Aging Management 1801 Table Notes No. Type Function(s) Management Program Volume I Item 12 Item Structural Gray Cast Steam Loss of Chemistry Program 32 Trap Body integrity Iron (Internal) material Effectiveness N/A N/A G Inspection 33 Structural Gray Cast Steam Loss of Flow-Accelerated N/A N/A G Trap Body integrity Iron (Internal) material Corrosion (FAC) 34 Structural Gray Cast Steam Loss of Selective Leaching N/A N/A G Trap Body integrity Iron (Internal) material Inspection Structural Gray Cast Air-indoor Loss of External Surfaces VI.-8 3.3.1- A 35 Trap Body integrity Iron uncontrolled material Monitoring 58

________(External) 36 Tubing Structural Stainless Steam C BWR Water N/A N/A G integrity Steel (Internal) Cracking Chemistry Structural Stainless Steam Chemistry Program 37 Tubing integrity Steel (internal) Cracking Effectiveness N/A N/A G Inspection 38 Tb Structural Stainless Steam Loss of BWR Water N/A N/A G integrity Steel (Internal) material Chemistry 3 TuigEffectiveness Structural Stainless Steam Loss of Chemistry Program N/A N/A G 39 Tubing integrity Steel (Internal) material Inspection Structural Stainless Air-indoor 3.3.1-40 Tubing Steel uncontrolled None None VII.J-15 A integrity 40 Tubing Steel (External) 94 Amendment 1 Review Results Management Review Aging Management Results Page 3.3-397e Page 3.3-397e Amendment 1

6W ;L Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-45 Aging Management Review Results - Heating Steam 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 41 Valve Body Structural Copper Alloy Steam Loss of BWR Water N/A N/A G integrity (Internal) material Chemistry Structural Steam Loss of Chemistry Program 42 Valve Body integrity Copper Alloy (Internal) material Effectiveness N/A N/A G Inspection Structural Air-indoor 43 Valve Body Copper Alloy uncontrolled None None N/A N/A G integrity 43 Valve Body (External) 44 Structural Gray Cast Steam Loss of BWR Water N/A N/A G Valve Body integrity Iron (Internal) material Chemistry 4 VavBoyEffectiveness Structural Gray Cast Steam Loss of Chemistry Program N/A N/A G 45 Valve Body integrity Iron (Internal) material Inspection 46 Valve Body Structural Gray Cast Steam Loss of Flow-Accelerated N/A N/A G integrity Iron (Internal) material Corrosion (FAC) 47 Structural Gray Cast Steam Loss of Selective Leaching N/A N/A G Valve Body integrity Iron (Internal) material Inspection Structural Gray Cast Air-indoor Loss of External Surfaces V.-8 3.3.1- A 48 Valve Body integrity Iron (External)ial Monitoring 58 49 Valve 4lve o Structural integrity Steel Steam (Internal) Loss of material BWR Water Chemistry N/A N/A G Amendment 1 Results Review Results Aging Management Review Page 3.3-397f Page 3.3-397f Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-45 Aging Management Review Results - Heating Steam System Component Intended Material Environment SAging Effect Requiring Aging Management NUREG-1801 Table Notes No. Type Function(s) Management Program Volume 1 Item 2 Item Chemistry Program 5 VavBoy Structural Steel Steam Loss of Effectiveness N/A N/A G 50 Valve Body integrity (Internal) material Ensection Inspection 51 Valve Body Structural Steel Steam Loss of Flow-Accelerated N/A N/A G integrity (Internal) material Corrosion (FAC) 52 Valve Body Structural integrity Steel Air-indoor uncontrolled (External) Loss of mtraMoirngVII.1-8 material MonitoringSurfaces External 3.3.1-58 58 A Aging Management Review Results Page 3.3-397g ArM~endment 1

(AJ _-7.1o B.2,47 Selective Leaching Inspection Columbia Generating Station License Renewal Application Technical Information inspection includes a visual examination and hardness measurement, or NRC approved alternative, of a sample set of components to determine whether selective leaching is occurring or is likely to occur in the period of extended operation.

The aging management activity is credited for the following systems:

" Auxiliary Steam (AS) System

• Circulating Water (CW) System

• Containment Nitrogen (CN) System

• Control Rod Drive (CRD) System

• Diesel Building HVAC Systems (DMA)

• Diesel Fuel Oil (DO) System "Heating Steam (HS) System

• Fire Protection (FP) System Heating Steam Condensate (HCO) System"

• High Pressure Core Spray (HPCS) System

• Low Pressure Core Spray (LPCS) System o Main Steam (MS) System

• Plant Service Water (TSW) System

• Potable Cold Water (PWC) System

• Potable Hot Water (PWH) System

• Process Sampling (PS) System

• Radwaste Building Chilled Water (WCH) System

• Radwaste Building HVAC Systems (WEA, WMA, WOA, WRA)

• Reactor Building HVAC Systems (REA, ROA, RRA)

• Residual Heat Removal (RHR) System

• Standby Service Water (SW) System

• Tower Makeup Water (TMU) System Preventive Actions No actions are taken as part of the Selective Leaching Inspection to prevent aging effects or to mitigate aging degradation. Although the control of water chemistry may reduce selective leaching in treated water environments, no specific credit is taken for water chemistry control as part of this program.

Aging Management Programs Page B-1 79 -4apuaFy-2044-jAmendment 1 1

Columbia:Generating Station License Renewal Application

_______________

___________________ echIcanformation Table 2.241 License Renewal Scoping Results for Mechanical Systems (continued)

Screening Results System Name In Scope?

Section Floor Drain Radioactive Yes 2:3.3.24 Fuel Oil Yes 2:23.3'18

+ ------ 4----

Fuel Pool.Cooling. Yes 2.3.325 Glycol ______________ __ No Guard H~ouse.Exhaust Air No Guard House Fire Protection No 4-Guard House Mixed Air No Guard House Outside Air No Guard House Potable Hot Water No Guard House Return Air No

- - -f

---

__ _ _ _- -II Heater Drain No Heater Vents No Heating Hot Water No .............

_ 11,-f Heating Steamr I> 2.13,4 Heating Steam Condensate .. .. i4 Heating Steam Vent L -~ '44o.. ___

High-Pressure Core Spray Yes 2.3.2.3 Hydrogen No Hydrogen Water Chemistry No Independent Spent Fuel Sto'rage Installation No Instrument Rack Yes 2.3.3.40 lsophase. Bus Duct Cooling Laboratory Equipment (Permanent Plant) No

--- 4-Leak Detection Yes 2.3.3126 i i - -

Local. Power Range Monitor Yes 2.3.1.2 Low-Pressure Core Spray Yes 2.3.2.4 Machine Shop Equipment No Main Steam Yes 2.3.4.4 Plant-Level Scoping Results Page 22-4 nt AmT .dmn T I rL

Columbia Generating Station 2.3.3 Auxiliary Systems License Renewal Application Technical Information Leak Detection (LD) System (Section 2,3.3.26)

Miscellaneous Waste Radioactive (MWR) System (Section 2.3.3,27)

Plant Sanitary Drains (PSD) System (Section 2.3.3,28)

Plant Service Water (TSW) System (Section 2.3.3,29)

Potable Cold Water (PWC) System (Section 2.3.3,30)

Potable Hot Water (PWH) System (Section 2.338.31)

Primary Containment (C) System (Section, 2.3;3.32)

Process Sampling (PS) System (Section 2.3.3.33)

Process Sampling Radioactive (PSR) System (Section 2.3.3.34)

Pump House HVAC Systems (Section, 2.313.35)

Radwaste Building Chilled Water (WCH) System (Section 2.3.3.36) A Radwaste Building HVAC Systems (Section 2.3.3.37)

Reactor Building. HVAC Systems (Section 2.3.3.38)

Reactor Closed Cooling Water (RCC) System (Section 2.3.3.39)

Reactor Protection System (RPS) (Section 2.3.3.40)

Reactor Water Cleanup (RWCU) System, (Section 2.3.3.41)

Service Air (SA) System (Section 2.3.3.42)

Standby Liquid Control (SLC) System (Section 2.3.3.43)

Standby Service Water (SW) System (Section 2,3.3.44)

Suppression Pool Temperature Monitoring (SPTM) System (Section 2.3.3,45)

Tower Makeup Water (TMU) System (Section 2.3.3.46),

Traversing Incore Probe (TIP) System (Section 2.3.3.47)

A brief system description, reason for scope determination,, associated FSAR references, associated license renewal drawings, and components subject to AMR information are provided for each system.

Insert:

"Heating Steam (HS) System (Section 2.3,3.48)

Heating Steam Condensate (HCO) System (Section 2.3.3.49)

Heating Steam Vent (HSV) System (Section 2.3.3.50)"

Scoping and Screening Results Page 2.3-35 40--

'Amendment1

bU ý-e?

Columbia.Generating Station License. Renewal Application Technical Information Table 23.3344 Traversing Incore Probe System Components Subject to Aging Management Review Component Type: Intended Function (as defined in Table 2.0-i)

Bolting Pressure Boundary Structural Integrity Chamber shield Structural: Integrity Piping Pressure Boundary Structural Integrity_

Valve body Pressure Boundary Structural Integrity t L9Ages 2.3-1G~ th'iirough '2.3162f

! 'rgthispage Scoping and Screening Results Page 2.3-162 4,-

IArnendmnent 1

W 'd 7-?

Columbia Generating Station License Renewal Application Technical Information 2.3.3.49 Heating Steam Condensate System

System Description

The condensate of the Heating Steam Condensate (HCO) System originates from the HS System and is returned to the auxiliary boiler condensate return tank located in the auxiliary boiler room of the Turbine Generator Building. Condensate from the Reactor Building, Turbine Generator Building, and upper level of the Service Building is returned to the auxiliary condensate return tank by gravity.

In the Radwaste Building and lower level of the Service Building, the condensate returns are below the level of the auxiliary condensate return tank. A. condensate pump-set is, therefore, -provided in each of these areas to pump the condensate: to the return tank.

Reason for Scope Determination The HCO System does not perform any safety-related system intended functions that meet the scoping criteria of 10 CFR 54.4(a)(1).

The HCO System does not contain any NSR components that perform a 10 CFR.54.4(a)(1) function. The HCO System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatiall interaction that could pr'event the satisfactory accomplishment of one or more of the functions identified in 10 CFR'54.4(a)(1).

Therefore, the HCO System meets the scoping criteria of 10 CFR 54,4(a)(2).

The. HCO System is not relied upon to demonstrate compliance, with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events,.

FSAR References Section 9.4.16.2 of the FSAR describes the Heating Steam Condensate System.

License Renewal Drawinas The following license renewal drawing depicts the evaluation boundaries for the system components within the scope of license renewal:':

LR-M514-1 Components Subiect to AMR Table 2.3.3-46 lists the component types that require AMR and their intended functions.

Table 3,.3.246, Aging Management Review Results - Heating Steam. Condensate System, provides the results of the AMR.

Scoping and Screening Results Page 2.3-162c Amendment 1

wi ý1-3 Columbia Generating Station License Renewal Application Technical Information Table 2.3.3-46 Heating Steam Condensate System Components Subject to-Aging Management Review, Component Type Intended Function (as defined in Table 2.0-1)

Bolting Structural integrity Piping Structural integrity Pump casing Structuralintegrity Strainer,(body)ý Structural integrity Tank Structural integrity Trap body Structural integrity Tubing Structural integrity Valve body Structural integrity Amendment 1 Scoping and Screening, Results PageResults Page Scoping and Screening 23~162d Z3-162d Amendment 1

Columbia Generating Station 3.3 Aging Management of Auxiliary Systems License Renewal Application Technical Information

• Fire Protection System (Section 2.3.3.22)

• Floor Drain System (Section 2.3.3.23)

• Floor Drain Radioactive System (Section 2.3.3.24)

" Fuel Pool Cooling System (Section 2.3.3.25)

" Miscellaneous Waste Radioactive System (Section 2.3.3.27)

• Plant Sanitary Drains System (Section 2.3.3.28)

• Plant Service Water System (Section 2.3.3.29)

• Potable Cold Water System (Section 2.3.3.30)

• Potable Hot Water System (Section 2.3.3.31)

" Primary Containment System (Section 2.3.3.32)

" Process Sampling System (Section 2.3.3.33)

• Process Sampling Radioactive System (Section 2.3.3.34)

• Pump House HVAC Systems (Section 2.3.3.35)

" Radwaste Building Chilled Water System (Section 2.3.3.36)

• Radwaste Building HVAC Systems (Section 2.3.3.37)

• Reactor Building HVAC Systems (Section 2.3.3.38)

" Reactor Closed Cooling Water System (Section 2.3.3.39)

• Reactor Water Cleanup System (Section 2.3.3.41)

• Service Air System (Section 2.3.3.42)

• Standby Liquid Control System (Section 2.3.3.43)

• Standby Service Water System (Section 2.3.3.44)

Add Insert A from

• Tower Makeup Water System (Section 2.3.3.46) page 3.3-2a

• Traversing Incore Probe System (Section 2.3.3.47) _3 Table 3.3.1, Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801, provides the summary of the programs evaluated in NUREG-1801 that are applicable to component and commodity groups in this section.

Text addressing summary items requiring further evaluation is provided in Section 3.3.2.2.

Aging Management Review Results Page 3.3-2Janu.ry 20u10

!Amendment 1

4-Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.3.1

• Heating Steam System (Section 2.3.3.48)

• Heating Steam Condensate System (Section 2.3.3.49)

• Heating Steam Vent System (Section 2.3.3.50)

Results Page 3.3-2a Amendment 1 Aging Review Results Management Review Aging Management Page 3.3-2a Amendment 1

h3 2q9-5 Columbia Generating Station 3.3.2 Results License Renewal Application Technical Information Table 3.3.2-39 Aging Management Review Results - Reactor Water Cleanup System Table 3.3.2-40 Aging Management Review Results - Service Air System Table 3.3.2-41 Aging Management Review Results - Standby Liquid Control System Table 3.3.2-42 Aging Management Review Results - Standby Service Water System Table 3.3.2-43 Aging Management Review Results - Tower Makeup Water System Table 3.3.2-44 Aging Management Review Results - Traversing Incore Probe System 3.3.2.1 Materials, Environments, Aging Effects Requiring Management, and Aging Management Programs The materials from which specific components and commodities are fabricated, the environments to which they are exposed, the aging effects requiring management, and the aging management programs used to manage these aging effects are provided for each of the above systems in the following sections.

3.3.2.1.1 Circulating Water System Materials The materials of construction for subject mechanical components of the Circulating Water System are:

• Concrete

" Gray cast iron

• Stainless steel

• Steel Environments Subject mechanical components of the Circulating Water System are exposed to the following normal operating environments:

" Air-outdoor

" Raw water

" Soil Aging Management Review Results Page 3.3-5 JdnIa, y 2010

Amendment 1

W1-5 Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.3.2 Table 3.3.2-45 Aging Management Review Results - Heating Steam System Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate System Table 3.3.2-47 Aging Management Review Results - Heating Steam Vent System Aging Management Review Results Page 3.3-5a Amendment 1

Columbia Generating Station 3.3.2 Results License Renewal Application Technical Information

! ....--- *dd new sections 3.3.2.1.45 through 47

• External Surfaces Monitoring Prograrh- as shown on pages 3.3-50a through d 3.3.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1801 For the Auxiliary Systems, those items requiring further evaluation are addressed in the following sections.

3.3.2.2.1 Cumulative Fatigue Damage Fatigue is a time-limited aging analysis, as defined in 10 CFR 54.3. Time-limited aging analyses are required to be evaluated in accordance with 10 CFR 54.21(c). Time-limited aging analyses identified for fatigue in the Auxiliary Systems are evaluated in Sectio n 4.3.4.

3.3.2.2.2 Reduction of Heat Transfer due to Fouling As deIscribed in Table 3.3.1, the Fuel Pool Cooling System has stainless steel heat exchaniger tubes in treated water which are evaluated under item number 3.3.1-03.

Fouling' of stainless steel heat exchanger tubes in treated water is managed by the BWR Water Chemistry Program, in conjunction with the Heat Exchangers Inspection.

3.3.2.2.3 I Cracking due to Stress Corrosion Cracking (SCC) 3.3.2.2.3.1 BWR Standby Liquid Control System The treated water environment for the Standby Liquid Control System uses an aqueous solution of sodium pentaborate decahydrate. The system is normally in standby with the fluid temperature maintained above the 60OF saturation temperature in an area where the ambient temperature is less than 1000 F during normal plant operation. Since the temperature is below 1401F during normal plant operation, cracking due to SCC is not an aging effect requiring management for the stainless steel components of the Standby Liquid Control System.

3.3.2.2.3.2 Heat Exchanger Components As described in Table 3.3.1, there are no components compared to item number 3.3.1-

05. The Reactor Water Cleanup regenerative and non-regenerative heat exchangers at Columbia have no stainless steel components subject to AMR. Therefore, cracking of these components due to stress corrosion cracking is not an aging effect requiring management. Refer to item 3.3.1-48 (no further evaluation required) for the aging effects that do require management for these components.

3.3.2.2.3.3 Diesel Engine Exhaust Piping, Piping Components, and Piping Elements During normal plant operations, diesel exhaust piping, piping components, and piping elements are exposed to diesel exhaust infrequently and for short durations. For the remaining time, these components are exposed internally to outdoor air. As such, temperatures above 1401F occur only infrequently and for short durations. Therefore, cracking due to SCC is not identified as an aging effect requiring management for Aging Management Review Results Page 3.3-50 Januar" 2010 1Amendment 1 7-":L

W )ýY Columbia Generating Station License Renewal Application Technical Information 3.3.2.1.45 Heating Steam System Materials The materials of construction for subject mechanical components of the Heating Steam System are:

o Copper alloy

• Gray cast iron

• Stainless steel

• Steel Environments Subject mechanical components of the Heating Steam System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

• Steam Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Heating Steam System:

• Cracking

• Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Heating Steam System:

" Bolting Integrity Program

• BWR Water Chemistry Program

• Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program Aging Management Review Results Page 3.3-50a Amendment 1

W)

Columbia Generating Station License Renewal Application Technical Information

• Flow-Accelerated Corrosion (FAC) Program

• Selective Leaching Inspection 3.3.2.1.46 Heating Steam Condensate System Materials The materials of construction for subject mechanical components of the Heating Steam Condensate System are:

• Copper alloy o Gray cast iron o Steel Environments Subject mechanical components of the Heating Steam Condensate System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

• Moist Air

" Steam

" Treated water > 60 'C (140 'F)

Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Heating Steam Condensate System:

• Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Heating Steam Condensate System:

• Bolting Integrity Program Aging Management Review Results Page 3.3-50b Amendment 1

wi ;Iq-7 Columbia Generating Station License Renewal Application Technical Information an aggressive environment. Therefore, loss of material due to pitting and crevice corrosion is not an aging effect requiring management for these components.

3.3.2.2.10.7 Stainless Steel Piping, Piping Components, and Piping Elements - Soil As-descbGd ab,19- -heannents-c mpared to-item-numbe,.3-.3-.

2N-. There-is-n o-stain-less-steekpping-sub ecot-te-AM4R-f -Ceumbia-that-is-expos ed-to il-inh-ia-eReplace with Insert A on page 3.3-55a 3.3.2.2.10.8 BWR Standby Liquid Control System Loss of material due to pitting and crevice corrosion for stainless steel piping components and tanks exposed to sodium pentaborate solution is managed by the BWR Water Chemistry Program. The BWR Water Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry 1Program Effectiveness Inspection will provide a verification of the effectiveness of the tBWR Water Chemistry Program to manage loss of material due to pitting and crevice corrosion through examination of stainless steel piping components and tanks exposed to sodium pentaborate solution.

3.3.2.2.11 Loss of Material due to Pitting, Crevice, and Galvanic Corrosion As-des¢,r-ied-in-T-able-*3.-1-T--t~her-e-vwere-no-cemponents-*,mpared-to-4temv-num

• 3-1-3-1. T--here-are-no-copper-al Ioy-piping, -piping-componentsT-,-r--pipi~ng-elements-in the-Aux-iiary-systems-that-are-exposed4ot4reated-water-.

3.3.2.2.12 Loss of Material due to Pitting, Crevice, and Microbiologically Influenced Corrosion 3.3.2.2.12.1 Piping, Piping Components, and Piping Elements - Fuel Oil There are no aluminum piping components exposed to fuel oil that are subject to AMR.

Loss of material due to pitting and crevice corrosion and MIC for stainless steel and copper alloy piping components exposed to fuel oil is managed by the Fuel Oil Chemistry Program. The Fuel Oil Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Program Effectiveness Inspection will provide a verification of the effectiveness of the Fuel Oil Chemistry Program to manage loss of material through examination of piping and components exposed to fuel oil.

3.3.2.2.12.2 Piping, Piping Components, and Piping Elements - Lubricating Oil Loss of material due to pitting and crevice corrosion and MIC for stainless steel piping components and heat exchanger components exposed to lubricating oil is managed by the Lubricating Oil Analysis Program. The Lubricating Oil Analysis Program manages aging effects through periodic monitoring and control of contaminants, including water.

The Lubricating Oil Inspection will provide a verification of the effectiveness of the Aging Management Review Results Page 3.3-55 January. 2010 JAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.3.2.2.10.7 The Buried Piping Thanks Inspection Program, with enhancement, manages loss of material due to pitting and crevice corrosion and microbiologically influenced corrosion (MIC) for stainless steel piping and piping components buried in soil.

Insert B to LRA Section 3.3.2.2.11 Loss of material due to pitting, crevice, and galvanic corrosion for copper alloy piping, piping components, or piping elements exposed to treated water is managed by the BWR Water Chemistry Program. The BWR Water Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Program Effectiveness Inspection will provide a verification of the effectiveness of the BWR Water Chemistry Program to manage loss of material due to pitting, crevice, and galvanic corrosion through examination of copper alloy piping and piping components exposed to treated water.

Review Results Page 3.3-55a Amendment 1 Management Review Aging Management Aging Results Page 3.3-55a Amendment 1

tA)

Columbia Generating Station License Renewal Application Technical Information Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1 801 Further Item Component/Commodity Aging Aging Management Evaluation Discussion Number Effect/Mechanism Programs Recommended 3.3.1-31 Copper alloy piping, piping Loss of material Water Chemistry and Yes, detection of Not-applicable.

components, and piping due to pitting, One-Time Inspection aging effects is elements exposed to treated crevice, and to be evaluated T-here-aremucrppertl1y piping, water galvanic corrosion . pnts-erptpiR§--

e!mi~snf~

• hauxifi-ay ystems Replace discussion tt-re-expose-terea*ed with Insert A from waref.*

page 3.3-77a ,.,N-4*-444ei 3.3.1-32 Stainless steel, aluminum and Loss of material Fuel Oil Chemistry and Yes, detection of Consistent with NUREG-1801, copper alloy piping, piping due to pitting, One-Time Inspection aging effects is with exceptions.

components, and piping crevice, and to be evaluated elements exposed to fuel oil microbiologically The Fuel Oil Chemistry Program, influenced in conjunction with the Chemistry corrosion Program Effectiveness Inspection, is credited to manage I loss of material for stainless steel and copper alloy piping and piping components in the auxiliary systems that are exposed to fuel oil. There are no aluminum piping, piping components, or piping elements in the auxiliary systems that are exposed to fuel oil.

Refer to Section 3.3.2.2.12.1 for further information.

Aging Management Review Results Page 3.3-77 -- Aamdare-2nt1 JAmondment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Table 3.3.1 Item 3.3.1-31 Consistent with NUREG-1801.

The BWR Water Chemistry Program, in conjunction with the Chemistry Program Effectiveness Inspection, is credited to manage loss of material for copper alloy piping and piping components in the auxiliary systems that are exposed to treated water.

Refer to Section 3.3.2.2.11 for further information.

Amendment 1 Results Review Results Aging Management Review Page 3.3-77a Page 3.3-77a Amendment 1

WýL-"

Columbia Generating Station License Renewal Application Technical Information Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1 801 Further Item C I d tAging Aging Management Evaluation Discussion Component/Commodity Number Effect/Mechanism Programs Recommended 3.3.1-71 Steel piping, piping Loss of material Inspection of Internal No The following programs are components, and piping due to general, Surfaces in credited to manage loss of elements exposed to moist air pitting, and crevice Miscellaneous Piping material for steel piping, piping or condensation (Internal) corrosion and Ducting components, and tanks in the Components auxiliary systems that are exposed to moist air or condensation (internal):

" Cooling Units Inspection for drain piping in HVAC systems exposed to condensation (internal)

" Monitoring and Collection Systems Inspection for air-water interfaces in Plant Sanitary Drain System piping evaluated as exposed to moist air (internal)

Replace deletednpt" f - eh-text with Insert A Int-e^.o in in d taRk*

from page 33-101 a e valuated as epose4 to mOnis A Note E is applied in each case.

Aging Management Review Results Page 3.3-101 j~enment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Table 3.3.1 Item 3.3.1-71

• Supplemental Piping/Tank Inspection for air-water interfaces in piping, piping components, and tanks evaluated as exposed to moist air (internal)

Aging Management Review Results Page 3.3-101 a Amendment 1

WA ý_q1l Columbia Generating Station License Renewal Application Technical Information Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1 801 Further Item ComponentlCommodity Aging Aging Management Evaluation Discussion Number Effect/Mechanism Programs Recommended 3.3.1-85 Gray cast iron piping, piping Loss of material Selective Leaching of No Consistent with NUREG-1801.

components, and piping due to selective Materials elements exposed to soil, raw leaching The Selective Leaching water, treated water or closed- Inspection is credited to detect cycle cooling water and characterize loss of material due to selective leaching for gray cast iron piping, piping components, and piping elements in the auxiliary systems exposed to soil, raw water,d closed-cycle cooling water. insert:

"treated This item is also applied to gray water" cast iron heat exchanger components that are exposed to raw water and closed cycle cooling water, and to gray cast iron tank components exposed to raw water. A Note C is applied.

3.3.1-86 Structural steel (new fuel Loss of material Structures Monitoring No Not applicable.

storage rack assembly) due to general, Program exposed to air - indoor pitting, and crevice There is no structural steel (new uncontrolled (external) corrosion fuel storage rack assembly) exposed toair-indoor uncontrolled (external).

3.3.1-87 PWR Only 3.3.1-88 PWR Only 3.3.1-89 PWR Only Aging Management Review Results Page 3.3-113 jAmendment 1

1k) t9q-I I Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-44 Aging Management Review Results - Traversing Incore Probe System Aging Effect Aging NUREG-Row Component IntendedAinEfetgng80 Tal Row Copoen Fntionded Material Environment Requiring Management 1801 Table Notes No. Type Function(s) Maaeetjrga Management Program Volume 2 Item

~1 Item Air-indoor Structural Stainless 3.3.1- A 10 Piping integrity Steel uncontrolled None None VII.J-15 94 0306 (Internal) 11 Piping Structural Stainless Gas None None VIIJ19 3.3.1- A integrity Steel (Internal) 97 Structural Stainless Air-indoor 33.1-12 Piping uncontrolled None None VII.J-15 A integrity Steel (External) 94 Air-indoor Pressure Stainless 3.3.1- A 13 Valve Body boundary Steel uncontrolled None None VII.J-15 94 0306 (Internal) 14 Valve Body Pressure Stainless Gas None None VII J19 3.3.1- A boundary Steel (Internal) 97 Pressure Stainless Air-indoor3.3.1-15 Valve Body y boundary Steel uncontrolled (External) None None VII.J-15 3. A Air-indoor Structural Stainless 3.3.1- A 16 Valve Body integrity Steel uncontrolled None None VII.J-15 94 0306 (Internal)

Structural Stainless Gas None None VIIJ19 3.3.1- A 17 Valve Body integrity Steel (Internal) 97 Structural Stainless Air-indoor 3.3.1-18 Valve Body uncontrolled None None VII.J-15 A integrity 18 Valve Body Steel (External) 94 Inisert new LRA Tables 3.3.2-45, 3.3.2-46, and 3.3.2-47 after th is page Aging Management Review Results Page 3.3-397 Aamendmne4t lAmnendmnent 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate System Row Component Intended Material Environment 1Aging Effect Requiring Aging Management NUREG-1801 Table Notes No. Type Function(s) Management Program Volume 1 Item 2 Item 1 Bolting Structural Air-indoor Loss of 3.3.1-integrity Steel uncontrolled (External) material maeil4 Bolting Integrity VII.I-4 B Bolting Structural integrity Steel uncontrolled Loss of pre-load Bolting Integrity VII.-5 3.3.1- B (External) 3 Structural Steam Loss of BWR Water N/A N/A G Piping integrity Steel (Internal) material Chemistry 4 Piping Structural integrity Steel Steam Loss of Chemistry Program (Internal) material Effectiveness N/A N/A G Inspection Structural Steel Steam Loss of Flow-Accelerated N/A N/A G ping integrity (Internal) material Corrosion (FAC)

Treated water Piping Structural integrity Steelmaterial Trete w Loss of BWR Water Chemistry VII.E3-18 3.3.1-17 A 0305 6F) (Internal) 7 Structural Treated water Loss of Chemistry Program VII.E3- 3.3.1- A Piping integrity Steel > 60 °C (140 m Effectiveness IF) (Internal) Inspection 8 Piping Structural, inert Steel Steel uAir-indoor uncontrolled Loss of n(External)material External MonitoringSurfaces VII.I-8 3.3.1-58 A 8 Pimping intertCasing Pump (Extr-nal)r Air-tndoor Loss of External Surfaces 3.3.1- C (WHCO-P-1A, A Structural Gray 1 C) integrity Iron Cast uncontrolled (Internal) material material Monitoring Monitoring_58_0302 VI-8 58 0302 Aging Management Review Results Page 3.3-397h Amendment 1

614 P-qIf Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate System Aging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801 Table Notes No. Type Function(s) Management Program Volume 1 Item M m 2 Item Pump Casing Structural Gray Cast Moist air Loss of Supplemental VII.H2- 3.3.1- E 10 (WHCO-P-1A, Strutu Gray CIsteair Lossrofl Piping/Tank 21 71 0303 1B) integrity Iron (Internal) material Inspection Pump Casing Treated water 11 (WHCO-P-1A, Structural Gray Cast >Loss of BWR Water VII.E3- 3.3.1-(

integrity Iron IF) (Internal) material Chemistry 18 17 0305 1B)

Pump Casing Treated water Chemistry Program VIIE3- 3.3.1- A 12 (WHCO-P-1A, integrity Iron Ce> 60 aC (140 material Effectiveness 18 17 0305 1B) OF) (Internal) Inspection Pump Casing Structural Gray Cast Treated 0water Loss of Selective Leaching VII.E37 3.3.1- A 13B)WHCO -P , integrity Iron F60 (C 4 material Inspection 12 85 0305 13 B)CP-A inerty IoIF) (internal)_____

Pump Casing Structural Gray Cast Air-indoor Loss of External Surfaces 3.3.1-14 (WHCO-P-1A, integrity Iron uncontrolled material Monitoring VII.I-8 31 A 1B) intCri(External) 58 15 Strainer Structural Gray Cast Steam Loss of BWR Water N/A N/A G (body) integrity Iron (Internal) material Chemistry Strainer Structural Gray Cast Steam Loss of Chemistry Program 16Effectiveness N/A N/A G (body) integrity Iron (Internal) material Insection Inspection 17 Strainer Structural Gray Cast Steam Loss of Flow-Accelerated N/A N/A G (body) integrity Iron (Internal) material Corrosion (FAC) 18 Strainer Structural Gray Cast Steam Loss of Selective Leaching N/A N/A G (body) integrity Iron (Internal) material Inspection Aging Management Review Results Page 3.3-397i Amendment 1

&J ~-9-II Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate System TAging Effect NUREG-Row Component Intended Material Aging Management 1801 Table Notes No. Type Function(s) Management Program Volume 1 Item 2 Item 19 Strainer Structural Gray Cast Air-indoor Loss of External Surfaces V.I-8 33.1- A (body) integrity Iron uncontrolled material Monitoring 58 (External)

Air-indoor Loss of External Surfaces 3.3.1- C 20 Tank (WHCO- Structural Steel uncontrolled material Monitoring V.-8 58 0302 CU-i) integrity (Internal)

Tank (WHCO- Structural Moist air Loss of Supplemental VII.H2- 3.3.1- E 21 Steel Piping/Tank 21 71 0303 21 CU-i ) integrity Steel (Internal) material Inspection Treated water Tank (WHCO- Structural Steel > 60 '140 wC Loss of BWR Water VII.E3- 3.3.1- C 22 CU-1) integrity material Chemistry 18 17 0305 OF) (Internal)

Tank (WHCO- Structural Treated water Loss of Chemistry Program VIIE3- 3.3.1- C 23 CU-1 ) integrity Steel > 60 °C (140 material Effectiveness 18 17 0305 CF) (Internal) Inspection 24 Tank (WHCO- Structural Steel Steam Loss of BWR Water N/A N/A G CU-1) integrity (Internal) material Chemistry Tank (WHCO- Structural tSteam Loss of Chemistry Program 25 Tnk(HC-Srutra telSea os f Effectiveness N/A N/A G CU-1) integrity (Internal) material Insection Inspection 26 Tank (WHCO- Structural Steel Steam Loss of Flow-Accelerated N/A N/A G CU-1) integrity (Internal) material Corrosion (FAC)

Tank (WHCO- Structural Steel Air-indoor Loss of External Surfaces VII.I-8 3.3.1- A 27 CU-1) integrity uncontrolled material Monitoring 58

_____ ___

______ __ ______ _ ____ ______ (External) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Amendment 1 Aging Management Aging Review Results Management Review Results Page 3.3-397j Page 3.3-397j Amendment 1

U ~~-H Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate System Row Component Material Environment 1Aging Effect Requiring Aging Management NUREG-1801 Table Notes Function(s) Management Program Volume 1 Item No. Type Mn t 12 Item 28 Trap Body Structural Gray Cast Steam Loss of BWR Water N/A N/A G integrity Iron (Internal) material Chemistry Structural Gray Cast Steam Loss of Chemistry Program 29 Trap Body integrity Iron (Internal) material Effectiveness N/A N/A G interityInspection 30 Trap Body Structural Gray Steam Loss of Flow-Accelerated N/A N/A G integrity Iron Cast (Internal) material Corrosion (FAC) 31 Trap Body Structural Gray Cast Steam Loss of Selective Leaching N/A N/A G integrity Iron (Internal) material Inspection Structural Gray Cast Air-indoor Loss of External Surfaces VI.-8 3.3.1- A 32 Trap Body integrity Iron uncontrolled material Monitoring 58 (External) Mntrn 33 Tubing Structural Copper Alloy Steam Loss of BWR Water N/A N/A G integrity (Internal) material Chemistry 34Structural Tbn Steam oprAlyEffectiveness Loss of Chemistry Program N/A N/A G 34 Tubing integrity Copper Alloy (Internal) material Inspection Structural Loss of BWR Water 3.3.1- A 35 Tubing integrity Copper Alloy >

TF)60(Internal)

IC (140 material Chemistry VII.E3-9 1 0305 Structural Treated water Loss of Chemistry Program 331- A 36 Tubing integrity Copper Alloy 3F)60(Internal)

> IC (140 material Effectiveness materialInspection VII.E3-9 31 0305 Page 3.3-397k Amendment 1 Review Results Management Review Aging Management Results Page 3.3-397k Amendment 1

LU c;~9-II Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate System Row Component Intended Material Enio Aging gg Effecte NUREG- 1Notes Management Aging ProgramManagement 1801 Table No. Type Function(s) Volume I Item 1nage n 12 Item Structural Air-indoor 37 Tubing Strity gintegrity Copper Alloy uncontrolled (External) None None N/A N/A G Structural Cp Steam Loss of BWR Water N/A N/A G 38 Valve Body integrity Copper Aoy nternal) material Chemistry Structural Steam Loss of Chemistry Program 39 Valve Body integrity Copper Alloy (internal) material Effectiveness N/A N/A G Inspection Structural e Loss of BWR Water 3.3.1- A 40 Valve Body integrity Copper Alloy > 60 'C (140 VIIE3-9 iF) (Internal) material Chemistry 31 0305 Structural Treated water Loss of Chemistry Program 3.11- A 41 Valve Body integrity Copper Alloy > 60 'C (140 Lossrofl Effectiveness VII.E3-9 31 0305 F) (Internal) erial Inspection Structural Air-indoor 42 Valve Body integrity Copper Alloy uncontrolled None None N/A N/A G (External) 43 Structural Steel Steam Loss of BWR Water N/A N/A G Valve Bdy 3 integrity (Internal) material Chemistry Structural Steam Loss of Chemistry Program 44 Valve Body integrity Steel (Internal) material Effectiveness N/A N/A G Inspection 45 Valve Body Structural Steel Steam Loss of Flow-Accelerated N/A N/A G integrity (Internal) material Corrosion (FAC)

Amendment 1 Review Results Aging Management Review Results Page 3.3-3971 Page 3.3-3971 Amendment 1

WA )-q- 11 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate System Intended Aging Effect NUREG-Row Component I Material Environment Requiring Aging Management 1801 Table Notes No. Type Function(s)

SManagement Program Volume 2 Item 1 Item Structural Treated water Loss of BWR Water VII.E3- 3.3.1- A 46 Valve Body integrity Steel > 60(internal)

IF) °C (140 maeil C e ity1170 5 Structural Treated water Loss 0 Chemistry Program VII.E3- 3.3.1- A 47 Valve Body integrity Steel > 60 °C (140 material Effectiveness 18 17 0305 iF) (Internal) Inspection 48 Valve Body Structural integrity Steel Air-indoor uncontrolled Loss of mtraMoirngVII.I-8 External Surfaces 3.3.1-58 A (External) material Monitoring 58 Page 3.3-397m Amendment 1 Review Results Aging Management Review Results Page 3.3-397m Amendment 1

B.2.47 Selective Leaching Inspection Columbia Generating Station License Renewal Application Technical Information inspection includes a visual examination and hardness measurement, or NRC approved alternative, of a sample set of components to determine whether selective leaching is occurring or is likely to occur in the period of extended operation.

The aging management activity is credited for the following systems:

• Auxiliary Steam (AS) System

• Circulating Water (CW) System

• Containment Nitrogen (CN) System

• Control Rod Drive (CRD) System

• Diesel Building HVAC Systems (DMA)

Insert:

• Diesel Fuel Oil (DO) System "Heating Steam (HS) System

• Fire Protection (FP) System Heating Steam Condensate (HCO) System"

• High Pressure Core Spray (HPCS) System

• Low Pressure Core Spray (LPCS) System

• Main Steam (MS) System

• Plant Service Water (TSW) System

• Potable Cold Water (PWC) System

• Potable Hot Water (PWH) System

• Process Sampling (PS) System

• Radwaste Building Chilled Water (WCH) System

• Radwaste Building HVAC Systems (WEA, WMA, WOA, WRA)

• Reactor Building HVAC Systems (REA, ROA, RRA)

• Residual Heat Removal (RHR) System

• Standby Service Water (SW) System

• Tower Makeup Water (TMU) System Preventive Actions No actions are taken as part of the Selective Leaching Inspection to prevent aging effects or to mitigate aging degradation. Although the control of water chemistry may reduce selective leaching in treated water environments, no specific credit is taken for water chemistry control as part of this program.

Aging Management Programs Page B-179 -Jaf.if-2 'Arnendment 1 _.

Colmbia Genera*,ing S~athon B.2.51 Supplemental Piping/Tank Inspection LicenseTechnical-tnformqtior RenewaI Appticaion

_________ _____________ __________ .

a Fire Protec-i- n (FP)System

Floor Drain (FD) System I Floor oc Drain R adioactive (FDR.)Systtem

• .... (P)

Fuel Pool* Cooling System '*-4-x----.H Ad. Hating . <~sm..Cond ~a~:

oHigh Pre~ssure Core Spray (HPCS) System (C **~m Low.s Pressure. Gore Spray (LPCS): System Main Steam (MS) System SMiscellaneous Drain (MD) System

,, Process. Sampling Radioactive (PSR) System SReacTor Building Outside Air (ROA)Sy ten

, :Reacor Closed ( oohhg.W Wtr (RCC} Sysem.

• Reactor Core: Itsolation Cooliin (ROCO) System

,,Residual =Heat. Remov'al (RHR): System

• , Standby Liquid Con rol (SLC).System' o, Standby.Service Water (SW) System

,,Tower Makeup Water (TMU) System A representative sample of .components at susceptible: locatioris wil be examined: for evidence of lOSs of material (due to crevice, galvanic, general, .or pitting corrosion, orf MIC),.or to confirm.a lack thereof The Supplemental Piping/Tank Inspection focuses on a limited but represenative sample population of subject components at susceptible .locations to be defined in the implemen ing documents, to include external piping surfaces and internal ank.

and piping surfacXes at air-water interfaces: The inspections provide symptomati6.

evidence of loss of material at the other susceptible, but possibly inaccessible, locations (such as intemat surfaces of piping) due to the similariies in materials and environmental conditions.

Preventive Actions N.o actions are taken as part of the Supplemental Piping/Tank inspection to prevent aging, effects or to mitigate aging degradation.

Pararmeters Monitored orInspected The paraer to be inspeed by the Supparm eta! Pipii gilank I pectio'i include wall thickness or visial evidence of internal and external surface degradation, as measures of loss of material. Inspections will be performed by qualified personnel Aging Management Programs Page 8- 98, -4 JAmendment 1

J 30-Columbia Generating Station License Renewal Application Technical Information Table 2.2-1 License Renewal Scoping Results for Mechanical Systems, (continued)

System Name Screening Results SystemNameJn Scope? I ~Section FloorDrain Radioactive Yes 23.3.24 Fuel Oil. Yes 2:3.3:18 Fuel Pool Cooling -Yes 2.3.3.25 Glycol No Guard House Exhaust Air No.

Guard House Fire Protection Noý Guard House Mixed Air No Guard House Outside Air No "4 Guard House Potable Hot Water No '~: ~," 4 Guard House Return Air No Heater Drain No .

Heater Vents No Heating Hot Water No Heating Steam 48 Heating Steam Condensate ~'Ves Heating Steam Vent High-Pressure Core Spray Yes 2, 3.23 Hydrogen No-Hydrogen Water Chemistry No Independent Spent Fuel Storage Installation No Instrument Rack yes 2.3.3.40 Isophase Bus Duct Cooling No Laboratory Equipment (Permanent Plant) No, Leak Detection Yes 2.3.3.26 Local Power Range. Monitor Yes 2.3.1.2 Low-Pressure Core Spray Yes 2.3,2.4 Machine Shop Equipment No Main Steam Yes: 23.4.4 Plant-Level Scoping Results Page 2.2-4 -4,J it 1'mendneret I

_j

Wj 30~

Columbia Generating Station 2.3.3 Auxiliary Systems License Renewal Application Technical Information Leak Detection (LD) System (Section 2.3.3.26)

Miscellaneous Waste Radioactive (MWR) System (Section 2.3.3.27)

Plant Sanitary Drains (PSD) System (Section 2.3.3.28)

Plant Service Water (TSW) System (Section 2.3.3.29)

Potable Cold Water (PWC) System (Section 2.3.3.30)

Potable Hot Water (PWH) System (Section 2.3.3.31)

Primary Containment (C) System (Section 2.3.3.32)

Process Sampling (PS) System (Section 2.3.3.33)

Process Sampling Radioactive (PSR) System (Section 2.3.3.34)

Pump House HVAC Systems (Section 2.3.3.35)

Radwaste Building Chilled Water (WCH) System (Section 2.3.3.36)

Radwaste Building HVAC Systems (Section 2.3.3.37)

Reactor Building HVAC Systems (Section 2.3.3.38)

Reactor Closed Cooling Water (RCC) System (Section 2.3.3.39)

Reactor Protection System (RPS) (Section 2.3.3.40)

Reactor Water Cleanup (RWCU) System (Section 2.3.3.41)

Service Air (SA) System (Section 2.3.3.42)

Standby Liquid Control (SLC) System (Section 2.3.3.43)

Standby Service Water (SW) System (Section 2.3.3.44)

Suppression Pool Temperature Monitoring (SPTM) System (Section 2.3.3.45)

Tower Makeup Water (TMU) System (Section 2.3.3.46)

Traversing Incore Probe (TIP) System (Section 2.3.3.47)

A brief system description, reason for scope determination, associated FSAR references, associated license renewal drawings, and components subject to AMR information are provided for each system.

Insert:

"Heating Steam (HS) System (Section 2.3.3.48)

Heating Steam Condensate (HCO) System (Section 2.3.3.49)

Heating Steam Vent (HSV) System (Section 2.3.3,50)"

Scoping and Screening Results Page 2.3-35,, .... .2949-,

lAmnendment 1

W 30-3 Columbia Generating. Station License. Renewal Application Technical Information Table 2.3.3-44.

Traversing Incore Probe System Components Subject to-Aging Management Review Component Type Intended Function (as defined in Table 2.0-4)

Bolting PressUr:eBoundary Structural Integrity Chamber shield Structural Integrity Piping Pressure Boundary Structural Integrity Valve body Pressure Boundary Structural integrity Insert pa ge-s 2312ahag 212 following thi~p Scoping and Screening Results Page 2.3-162

[Amendment 1

,W 30- 3 Columbia Generating Station License RenewalApplication Technical Information 2.3.3.50 Heating: Steam Vent. System

System Description

The Heating Steam Vent (HSV) System provides a vent through the roof of the]

respective buildings of the relief valves and tanks of the HS and HCO systems'.

Reason for Scope Determination The HSV System does not perform any safety-related system intended functions that meet: the scoping criteria of I0 CFR 54.4(a)(1).

The HSV System does not contain any NSR compoinents that perform a 10 CFR 54.4(a)(1) function. The HSV System does,. however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for ýspatial interaction. that could prevent the satisfactory accomplishment of one. or more of the functions identified in 10 CFR 54A4(a)('1).

Therefore, the HSV System meets the scoping criteria of 10 CFR 5414(a)(2).

The HSV- System is not. relied upon to demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events.,

FSARý References Figure 9.4-9'.1 of the FSAR describes the Heating Steam Vent System.

License Renewal Drawings The following license renewal drawing depicts the evaluation boundaries for the system components within the scope of license renewal:

LR-M514-1 Components Subiect to AMR Table 2.3.3-47 lists the component types that require AMR and their intended functions.

Table provides3.3.2-47, Aging Management Review Results - Heating Steam Vent System, the results of the AMR.

Amendment 1 and Screening Scoping and Results Screening Results Page 23-162e Page 2.3-162e Amendment 1

W 30-3 Columbia Generating Station License:Renewal Applicatioff Technical Information Table 2.3.3-47 Heating Steam Vent System Components Subject ,toAging Management Review Component Type Intended FUnction (as defined in Table 2.0-1)

Bolting Structural integrity Piping StructUrall integrity Page 2~3-i62f Amendment 1 Scoping Screening Results and Screening Scoping and Results Page 2.3-162f Amendment 1

L0J30 3.3 Aging Management of Auxiliary Systems Columbia Generating License Renewal Station Application Technical Information

• Fire Protection System (Section 2.3.3.22)

• Floor Drain System (Section 2.3.3.23)

" Floor Drain Radioactive System (Section 2.3.3.24)

• Fuel Pool Cooling System (Section 2.3.3.25)

• Miscellaneous Waste Radioactive System (Section 2.3.3.27)

" Plant Sanitary Drains System (Section 2.3.3.28)

• Plant Service Water System (Section 2.3.3.29)

• Potable Cold Water System (Section 2.3.3.30)

• Potable Hot Water System (Section 2.3.3.31)

• Primary Containment System (Section 2.3.3.32)

" Process Sampling System (Section 2.3.3.33)

• Process Sampling Radioactive System (Section 2.3.3.34)

" Pump House HVAC Systems (Section 2.3.3.35)

• Radwaste Building Chilled Water System (Section 2.3.3.36)

• Radwaste Building HVAC Systems (Section 2.3.3.37)

" Reactor Building HVAC Systems (Section 2.3.3.38)

" Reactor Closed Cooling Water System (Section 2.3.3.39)

• Reactor Water Cleanup System (Section 2.3.3.41)

" Service Air System (Section 2.3.3.42)

• Standby Liquid Control System (Section 2.3.3.43)

• Standby Service Water System (Section 2.3.3.44)

JAdd Insert A from

• Tower Makeup Water System (Section 2.3.3.46) page 3.3-2a (Section 2.3.3.47) 3

• Traversing Incore Probe System Table 3.3.1, Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801, provides the summary of the programs evaluated in NUREG-1801 that are applicable to component and commodity groups in this section.

Text addressing summary items requiring further evaluation is provided in Section 3.3.2.2.

Aging Management Review Results Page 3.3-2 January 2010

'Amendment 1 i

wJ 3o- '-1 Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.3.1 o Heating Steam System (Section 2.3.3.48)

• Heating Steam Condensate System (Section 2.3.3.49)

" Heating Steam Vent System (Section 2.3.3.50)

Amendment 1 Aging Management Aging Review Results Management Review Results Page 33-2a Page 3.3-2a Amendment 1

W6-Columbia Generating Station 3.3.2 Results License Renewal Application Technical Information Table 3.3.2-39 Aging Management Review Results - Reactor Water Cleanup System Table 3.3.2-40 Aging Management Review Results - Service Air System Table 3.3.2-41 Aging Management Review Results - Standby Liquid Control System Table 3.3.2-42 Aging Management Review Results - Standby Service Water System Table 3.3.2-43 Aging Management Review Results - Tower Makeup Water System Table 3.3.2-44 Aging Management Review Results - Traversing Incore Probe System

< IAdd Insert A from page 3.3-5a 3.3.2.1 Materials, Environments, Aging Effects Requiring Management, and Aging Management Programs The materials from which specific components and commodities are fabricated, the environments to which they are exposed, the aging effects requiring management, and the aging management programs used to manage these aging effects are provided for each of the above systems in the following sections.

3.3.2.1.1 Circulating Water System Materials The materials of construction for subject mechanical components of the Circulating Water System are:

• Concrete

" Gray cast iron

• Stainless steel

• Steel Environments Subject mechanical components of the Circulating Water System are exposed to the following normal operating environments:

• Air-outdoor

• Raw water

• Soil Aging Management Review Results Page 3.3-5 Jaiudi y 2010 Arnendmeni1FA

W 30- 5" Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.3.2 Table 3.3.2-45 Aging Management Review Results - Heating Steam System Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate System Table 3.3.2-47 Aging Management Review Results - Heating Steam Vent System Review Results Page 3.3-5a Amendment I Management Review Aging Management Aging Results Page 3.3-5a Amendment 1

S30"-6 Columbia Generating Station 3.3.2 Results License Renewal Application Technical Information

• External Surfaces Monitoring Progra 'as shown on pages 3.3-50a through d 3.3.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1801 For the Auxiliary Systems, those items requiring further evaluation are addressed in the following sections.

3.3.2.2.1 Cumulative Fatigue Damage Fatigue is a time-limited aging analysis, as defined in 10 CFR 54.3. Time-limited aging analyses are required to be evaluated in accordance with 10 CFR 54.21(c). Time-limited aging analyses identified for fatigue in the Auxiliary Systems are evaluated in Section 4.3.4.

3.3.2.2.2 Reduction of Heat Transfer due to Fouling As described in Table 3.3.1, the Fuel Pool Cooling System has stainless steel heat exchanger tubes in treated water which are evaluated under item number 3.3.1-03.

Fouling of stainless steel heat exchanger tubes in treated water is managed by the BWR Water Chemistry Program, in conjunction with the Heat Exchangers Inspection.

3.3.2.2.3 Cracking due to Stress Corrosion Cracking (SCC) 3.3.2.2.3.1 BWR Standby Liquid Control System The treated water environment for the Standby Liquid Control System uses an aqueous solution of sodium pentaborate decahydrate. The system is normally in standby with the fluid temperature maintained above the 60OF saturation temperature in an area where the ambient temperature is less than 1 000 F during normal plant operation. Since the temperature is below 140OF during normal plant operation, cracking due to SCC is not an aging effect requiring management for the stainless steel components of the Standby Liquid Control System.

3.3.2.2.3.2 Heat Exchanger Components As described in Table 3.3.1, there are no components compared to item number 3.3.1-

05. The Reactor Water Cleanup regenerative and non-regenerative heat exchangers at Columbia have no stainless steel components subject to AMR. Therefore, cracking of these components due to stress corrosion cracking is not an aging effect requiring management. Refer to item 3.3.1-48 (no further evaluation required) for the aging effects that do require management for these components.

3.3.2.2.3.3 Diesel Engine Exhaust Piping, Piping Components, and Piping Elements During normal plant operations, diesel exhaust piping, piping components, and piping elements are exposed to diesel exhaust infrequently and for short durations. For the remaining time, these components are exposed internally to outdoor air. As such, temperatures above 1401F occur only infrequently and for short durations. Therefore, cracking due to SCC is not identified as an aging effect requiring management for Aging Management Review Results Page 3.3-50 Januar' 2010 lAmendment _1__7

) 3O- ,

Columbia Generating Station License Renewal Application Technical Information

• BWR Water Chemistry Program

• Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program

" Flow-Accelerated Corrosion (FAC) Program

• Selective Leaching Inspection

• Supplemental Piping/Tanks Inspection 3.3.2.1.47 Heating Steam Vent System Materials The materials of construction for subject mechanical components of the Heating Steam Vent System are:

• Steel Environments Subject mechanical components of the Heating Steam Vent System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

• Steam Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Heating Steam Vent System:

• Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Heating Steam Vent System:

• Bolting Integrity Program

• BWR Water Chemistry Program Aging Management Review Results Page 3.3-50c Amendment 1

Columbia Generating Station License Renewal Application Technical Information

• Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program

• Flow-Accelerated Corrosion (FAC) Program Page 33-50d Amendment 1 Review Results Management Review Aging Management Results Page 3.3-50d Amendment 1

Columbia Generating Station License Renewal Application Technical Information an aggressive environment. Therefore, loss of material due to pitting and crevice corrosion is not an aging effect requiring management for these components.

3.3.2.2.10.7 Stainless Steel Piping, Piping Components, and Piping Elements - Soil As-deseibed-in-Table-3-.-.-,here-are-no-comlonen ts-rnpare ile umb 29-. There-is-no--stainless-stee-piping-subject-to-AMR-for-Columbia-that-is--exposed-to soif14he-AuxA1iary-sys4em& -Replace with Insert A on page 33s-55a 3.3.2.2.10.8 BWR Standby Liquid Control System Loss of material due to pitting and crevice corrosion for stainless steel piping components and tanks exposed to sodium pentaborate solution is managed by the BWR Water Chemistry Program. The BWR Water Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Replace Program Effectiveness Inspection will provide a verification of the effectiveness of the with Insert BWR Water Chemistry Program to manage loss of material due to pitting and crevice B from corrosion through examination of stainless steel piping components and tanks exposed page to sodium pentaborate solution.

3.3-55a 3.3.2.2.11 Loss of Material due to Pitting, Crevice, and Galvanic Corrosion As-d escribedl-n--Table3.3.*3,3-rthere-were-no-com-ponents-compared-toitem-u mber 3-31--3-1-. There- are-no-copper-alloy-pi pin g.-piping-,components&-o-r-pipi n g- elements-4n t he-Auxi~liar-y-,systems,,hat-are-eaxposed-to4rea-ted-w-at,er-.

3.3.2.2.12 Loss of Material due to Pitting, Crevice, and Microbiologically Influenced Corrosion 3.3.2.2.12.1 Piping, Piping Components, and Piping Elements - Fuel Oil There are no aluminum piping components exposed to fuel oil that are subject to AMR.

Loss of material due to pitting and crevice corrosion and MIC for stainless steel and copper alloy piping components exposed to fuel oil is managed by the Fuel Oil Chemistry Program. The Fuel Oil Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Program Effectiveness Inspection will provide a verification of the effectiveness of the Fuel Oil Chemistry Program to manage loss of material through examination of piping and components exposed to fuel oil.

3.3.2.2.12.2 Piping, Piping Components, and Piping Elements - Lubricating Oil Loss of material due to pitting and crevice corrosion and MIC for stainless steel piping components and heat exchanger components exposed to lubricating oil is managed by the Lubricating Oil Analysis Program. The Lubricating Oil Analysis Program manages aging effects through periodic monitoring and control of contaminants, including water.

The Lubricating Oil Inspection will provide a verification of the effectiveness of the Aging Management Review Results Page 3.3-55 January.20.10 Amendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.3.2.2.10.7 The Buried Piping Thanks Inspection Program, with enhancement, manages loss of material due to pitting and crevice corrosion and microbiologically influenced corrosion (MIC) for stainless steel piping and piping components buried in soil.

Insert B to LRA Section 3.3.2.2.11 Loss of material due to pitting, crevice, and galvanic corrosion for copper alloy piping, piping components, or piping elements exposed to treated water is managed by the BWR Water Chemistry Program. The BWR Water Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Program Effectiveness Inspection will provide a verification of the effectiveness of the BWR Water Chemistry Program to manage loss of material due to pitting, crevice, and galvanic corrosion through examination of copper alloy piping and piping components exposed to treated water.

Aging Management Review Results Page 3.3-55a Amendment 1

W 3-Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-44 Aging Management Review Results - Traversing Incore Probe System Row Component Intended Aging Effect Aging TaNUREG-Row Cmpnen Fnctiondd Material Environment Requiring Management 1801 Table Notes Arno Tp FManagement Program 2 Item Structural Stainless Air-indoo3.3.1- A 10 Piping integrity Steel uncontrolled None None VII.J-15 940306 (internal) 11 Piping Structural Stainless Gas None None VIIJ-1 3.3.1- A integrity Steel (Internal) 97 Structural 1 Piiguncontrolled 1Piigintegrity Stainless Steel Air-indoor (External) None None VII.J-1 5A 331-94 Air-indoor Pressure Stainless 3.3.1- A 13 Valve Body boundary Steel uncontrolled None None VII.J-15 94 0306 (Internal) 14 Valve Body Pressure Stainless Gas None None VII J19 3.3.1- A boundary Steel (Internal) 97 Pressure Stainless Air-indoor3.3.1-15 Valve Body uncontrolled None None VII.J-15 3. A 15 V y boundary Steel (External) 94 Structural Stainless Air-indoor33.1- A 16 Valve Body uncontrolled None None VII.J-15 3.301-6 16 ValveBy integrity Steel (Internal) 94 0306 17 Valve Body Structural integrity Stainless Steel Gas (Internal) None None VIIJ19 3.3.1-97 A Air-indoor Structural Stainless None VII.J-15 3.3.1-A 18 Valve Body uncontrolled None integrity Steel- 94 (External)

Insert new LRA Tables 3.3.2-45, 3.32-46, and 3.3.2-47 after this page Aging Management Review Results Page 3.3-397 Amendment 1

61j 30 -Y Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-47 Aging Management Review Results - Heating Steam Vent System No.

Row Tympoen Component IFnctionds)

Intended Material Environment 1Aging Effect Requiring Aging Management NUREG-ProgamgVolmefeIte 1801 Table Notes No. Type Function(s) Management Program Volume I Item 2 Item Structural Air-indoor Loss of 3.3.1-1 Bolting integrity Steel uncontrolled material Bolting Integrity VII.I-4 3 B (External) material 43 Air-indoor 3.3.1-Structural Ai-nor Loss of pre-2 Bolting integrity Steel uncontrolled load Bolting Integrity VII.I-5 45 B integrity (External) la 3 P Pipi Structural integrity Steel Steam Loss of BWR Water N/A N/A G U (Internal) material Chemistry Structural Steam Loss of Chemistry Program Piping integrity Sintegructu Steel Stera (Internal) material Effectiveness Inspection N/A N/A G 5 Piping Structural Steel Steam Loss of Flow-Accelerated N/A N/A G integrity (Internal) material Corrosion (FAC)

Structural Air-indoor Loss of External Surfaces 3.3.1-Piping integrity Steel uncontrolled (External) material Monitoring I -8 I IA Page 3.3-397n Amendment 1 Aging Review Results Management Review Aging Management Results Page 3.3-397n Amendment 1

Columbia Generating Station License Renewal Application Technical Information 2.3.3.27 Miscellaneous Waste Radioactive (MWR) System

System Description

The MWR System is designed to collect water in the Reactor, Turbine, and Radwaste buildings that can contain potentially radioactive detergent and transfer the fluid directly by gravity to the Radwaste Building sump or the detergent drain tanks. It is also used to drain the decontamination solution in the Reactor Building from the decontamination pit and Reactor Closed Cooling Water chemical addition tank to the chemical waste tanks.

Additionally the system also consists of SLC System drains. These equipment and floor drains collect borated water from the SLC System and direct it to 55-gallon drums located in the Reactor Building.

Reason for Scope Determination The MWR System provides Primary Containment isolation and integrity, and secondary containment isolation and integrity. These system-intended functions are safety-related.

Therefore, the MWR System meet the scoping criteria of 10 CFR 54.4(a)(1).

The MWR System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The MWR System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1).

Therefore, the MWR System meets the scoping criteria of 10 CFR 54.4(a)(2).

The MWR System is not relied upon to demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events.

FSAR References Section 11.2 of the FSAR describes the Liquid Waste Management System, evaluated for license renewal as the MWR System License Renewal Drawings The following license renewal drawing depicts the evaluation boundaries for the system components within the scope of license renewal:

In-sert: ", LR-M531, LR-M533-1, LR-M539 -------- LR-M533-2" Components Subiect to AMR Table 2.3.3-26 lists the component types that require AMR and their intended functions.

Table 3.3.2-26, Aging Management Review Results - Miscellaneous Waste Radioactive System, provides the results of the AMR.

Scoping and Screening Results Page 2.3-108 ,a art-

[Amendment 1

W- 3)- I

.323.31 Potable Hot Water (PWH) System Columbia Generating Station License Renewal Application Technical Information before adverse consequences (i.e., interaction with safety-related structures and components) would manifest. Therefore, plumbing fixtures are not subject to AMR.

Table 2.3.3-30 Potable Hot Water System Components Subject to Aging Management Review Intended Function Component Type (as defined in Table 2.0-1)

Piping Structural Integrity Shock suppressor Structural Integrity Valve body Structural Integrity Insert A from page 2.3-1 7a Scaping and Screening Resuits Page 2.3-117

Columbia Generating Station License Renewal Application Technical Information Insert A to Table 2.3.3-30:

Tubing Structural Integrity Page 2.3-117a Supplement 1 Scoping Screening Results and Screening Scoping and Results Page 2.3-117a Supplement 1

LAi 3a- a Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-30 Aging Management Review Results - Potable Hot Water System Row Component Intended SAging Effect AingEfct Aging Aig1801 NUREG- Table No. Type Function(s) Material Environment Requiring Management Voum Tabte Notes

__. _ _ _e _ __c_ __n_ _Management Program Volume 1 Item 2 Item Structural Copper Alloy Air-indoor 10 Valve Body uncontrolled None None VIII.l-2 3.4.1- A integrity >15% Zn (External) 41 Insert new table rows 11 through 13 for Table 3.3.2-30, as show on page 3.3-291Ia Aging Management Review Results Page 3.3-291 EAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-30 Aging Management Review Results - Potable Hot Water System NUREG-Row Component Intended Aging Effect Aging 1801 Table No. Type Function(s) Material EnvironmentMaRequiring Management Volume 2 1 Item Notes Item Tubing Structural Copper Alloy Raw water Loss of Potable Water VII.C1-9 3.3.1- E 11 integrity > 15% Zn (Internal) material Monitoring 81 Tubing Structural Copper Alloy Raw water Loss of Selective VII.C1- 3.3.1- A 12 integrity > 15% Zn (Internal) material Leaching 10 84 Inspection Tubing Structural Copper Alloy Air-indoor None. None VIII.I-2 3.4.1- A 13 integrity > 15% Zn uncontrolled 41 (External)

Amendment 1 Management Review Aging Management Results Review Results' Page 3.3-291a Page 3.3-291 a Amendment 1

U)3;-

Columbia Generating Station B.2.43 Potable Water Monitoring Program License Renewal Application Technical Information

" Parameters Monitored or Inspected The Potable Water Monitoring Program monitors the water treatment plant performance and the overall status of the potable water system, including water quality.

• Detection of Aging Effects The Potable Water Monitoring Program will be enhanced to use a combination of established volumetric and visual examination techniques performed by qualified personnel on locations within the PWC, PWH, and ROA systems, as determined by engineering evaluation, to identify evidence of a loss of material, or to confirm a lack thereof. At least one inspection will be conducted within the 10-year period prior to the period of extended operation.

Based on operating experience, it is necessary that inspections be conducted at least once every five years, and include components of the PWC and PWH systems that are located in the Reactor Building and components associated with the ROA air washer (ROA-AW-1), including the a washer housing.

Insert: "or Radwaste Building (including corridors)"

" Monitoring and Trending The Potable Water Monitoring Program monitors the water treatment plant performance and the overall status of the potable water system, including water quality, and the results are recorded and trended.

" Acceptance Criteria The acceptance criteria for potable water system inspections are: indications or relevant conditions of degradation detected during the inspection will be compared to pre-determined acceptance criteria. If the acceptance criteria are not met, then the indications and conditions will be evaluated under the corrective action program to determine whether they could result in a loss of component intended function during the period of extended operation.

Acceptance criteria have been established for potable water quality, which minimizes the presence of impurities that could cause degradation.

" Corrective Actions This element is common to Columbia programs and activities that are credited with aging management during the period of extended operation and is discussed in Section B.1.3.

• Confirmation Process This element is common to Columbia programs and activities that are credited with aging management during the period of extended operation and is discussed in Section B.1.3.

Aging Management Programs Page B-167 n -4ad maPe-n

ýAýn dment1

2.3.3.41 Reactor Water Cleanup (RWCU) System Columbia Generating Station License Renewal Application Technical Information FSAR References Section 5.4.8 of the FSAR describes the Reactor Water Cleanup System.

License Renewal Drawints The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

Insert: ", LR-M536" LR-M523-1, LR-M523-2 Portions of the RWCU System are in the Radwaste Building and outside of the control room tower boundary; as such these components are outside the scope of license renewal. This includes the filter demineralizer subsystem and its associated demineralizers, piping, pumps, and tanks.

Components Subiect to AMR Table 2.3.3-39 lists the component types that require AMR and their intended functions.

Table 3.3.2-39, Aging Management Review Results - Reactor Water Cleanup System, provides the results of the AMR.

The external subcomponents (shell and channel covers) of the RWCU heat exchangers will contain fluid leakage in the event of a failure of an internal subcomponent (tubes and tubesheet). Failure of an internal subcomponent will therefore not create the potential for spatial interaction that could prevent a safety-related SSC from performing its intended function. Therefore, the RWCU heat exchanger tubes and tubesheets are not subject to AMR.

Class 1 components of the RWCU System that are part of the reactor coolant pressure boundary are evaluated in Section 2.3.1.3.

Scoping and Screening Results Page 2.3-146 -January-2G+G--

JAmendment 1

J 3J -I Columbia Generating Station License Renewal:Application Technical Inforniation Table 2.2-1 License Renewal Seoping Results ifor Mechanical Systems (continued)

Screening Resuts11 System Name In Scope? Section Radwaste Building ThilcdWater Yes 2.3.&36 Radwaste Building ExhaustcAir Yes 2.3.3.37 Radwaste Building Heating Condensate No Radwaste Building Mixed Air Yes. 2.3.3.37 Radwaste Building Outside Air Yes: 2.3.3.37 Radwaste Building Potable Hot Water No No, -I Radwaste Building Refrigeration Radwaste.Building Return-Air Yes 2.33.37 i

Reactor Building Exhaust Air Yes: 2.3;3.38 4

Reactor Building Outside Air. Yes 2.3.3138

-'I Reactor Building Return Air (Emergency Cooling) Yes :2 3 3 38 Reactor Closed Cooling Water Yes 2.3.3.39:

Reactor Core Isolation. Cooling Yes 213.12.

Reactor Feedwater Yes 2.34.7 Reactor Feedwater Turbine: No .

Reactor Protection System* Yes. 2.3.3.40 Reactor Recirculation Yes 2.3.1.3-Reactor Service Equipment, No Reactor Water Cleanup Yes 2.3.3.41 Residual Heat Removal Yes 2.3.2.1 Roof Drains Yes 2.3.3,23 Reactor Recirculation Hydraulic Control No Sampling Yes 23, 3.34 Seal Oil No Sealing Steam Service Air 1.f-m 1+7> Yes 2.3,3.42 2 48 Service Building Chilled Water No Plant-Level Scoping Resuits Page.2.2-6

[Amendment !

WA 3-Columbia Generating Station License Renewal Application:

Technical Information 2.3.4 Steam and Power Conversion Systems The steam and power conversion systems are those systems used as a heat .sink to remove. heat from the reactor and: convert the heat generated: in the reactor to the electrical'output produced by the plant. Theq fol.lowing CoLumbia., systems are addressed in this section:

• Auxiliary Steam (AS) System (Secti.on.3.4.1)

• Condensate (Auxiliary) (GO) System (Section-2.3R4.2)

'Condensate (Nuclear) (COND) System (Section 2.3A4.3)

• Main Steam (MS) System (Section -2.3.4:4)

Main Steamr Leakage Control (MSLC) System (Section 2.3.4.5)

" Miscellaneous Drain (MD) System (Section,2.3.4.6)

" Reactor Feedwater (RFW) System (Section 2.3.4.7) - , 3. ,

A brief system cdescription, reason for scope determination, associated PSAR references, associated license,- renewal drawings,, and components. subject to AMR information is provided for each system..

Scoping and Screening Results Page 2.3116ý3.

JAmendment 1K

Columbia Generating.Station License Renewal Application:

Technical Inforrmation The ASME Class I portions of the RFW System are addressed with the reactor coolant pressure boundary in Section.2.3.1.3.

Comoonents Subiect to AMR Table,.2.3.4-7 lists-the component types that require AMR and their intended functions.

Table 3.4.2ý7, Aging Management Review Results Reactor Feedwater System, provides the results of the AMR.

The small-bore lines to flow. transmitters: RFWVFT-802A and 802B are decoupled from:

the piping analysis, and are therefore not in scope.

The flow meter section is in scope only for NSAS; therefore, the internals, including the in scope.

flow straighteners and, the nozzles are.not Table 123.447 Reactor Feedwater System Components Subject to Aging Management Review:

intendedd Function Component Type (as defined'in Table 2.0-1)

Bolting Structural integrity:

Flow element Structural, integrity Piping: Structural integrity SValve body- Structural integrity

~~~-~ ~1Oad3 n 0 "'4' 18 S copingand Screening Res-tts Pageý2~3-'FWi8

[Amendment 1

6.3)

Columbia Generating Station License Renewal Application Technical Information 2.14.8 Sealing Steam System

System Description

The Sealing Steam (SS) System consists of two 100%-capacitY gland seal steam!

evaporators, seal, steam pressure regulators, seal steam header, gland seal steam condenser, exhauster blowers, and the associated piping, valves, and instrumentation, Sealing steam for turbine shaft sealrglands and valve stem seal glands (stop, control, reheat stop, intercept, and bypass valves)I is supplied from the seal steam header at 200. psig, The source of sealing steam is from the gland seal steam evaporators or the aUxiliary steam boiler. The sealing steam is produced in an evaporator which; is heated by extraction steam taken from the high pressure turbine. The condensate fed. to the evaporator is taken from the, suction header of the reactor feedwater pumps in the feedwater system. During. startup and. low load operations, a branch line taken off the main steam header supplies the necessary heating steam for the evaporator.,

Separate seal. steam regulators are provided to regulate the. pressure of sealing steam for the high pressure turbine, each low pressure turbine, each reactor feed pump turbine shaft seal, the bypass valve assembly, and the main stop: and control valve assembly stems.

Since the low, pressure (LP) turbine and reactor feedwater pump turbine exhaust pressures are at a vacuum, sufficient sealing steam is supplied%to maintain positive pressure in the glands to prevent air inleakage along the shaft. The high pressure (HP) turbine exhaust. pressure varies with load and is approximately 177 psia at its maximum.

The system is designed to. maintain the seal steam supply to the HP turbine glands at a

'pressure of 16 to 20 psi above HP turbine exhaust to prevent HP turbine exhaust.steam leakage through the shaft gland-seal.

The outer leak.off of all glands: is routed to theý gland seal steam condenser which is maintained at a slight vacuum by the exhauster blower. During, plant operation, the gland seal steam condenser and: one motor-driven blower is in operation. The exhauster blower discharges gland air inleakage to the atmosphere via the reactor building elevated release duct.. The gland: seal steam condenser is cooled by the main condensate flow, The steam evaporator is a shell-and-ube heat exchanger designed, to provide a continuous supply of clean sealing steam to the seal steam header.

Reason for Scope Determination.

The SS System does not perform any safety-related system intended functions that meet the scoping criteria of 10 CFR 54.4(a)(1)'.

Page 23-lBOa Amendment 1 Scoping and Screening Results Screening Results Page 2.3-180a Amendment 1

Columbia Generating Station License Renewal Application Technical Information The SS System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The SS System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10.CFR 54.4(a)(1). Therefore, the SS System meets the scoping criteria of 10 CFR 54.4(a)(2).

The SS System is not relied upon to demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events.

FSAR References Section 10.4.3.2 of the FSAR describes the Sealing Steam System.

License Renewal Drawings The following license renewal drawing depicts the evaluation boundaries for the system components within the scope of license renewal:

LR-M502-3 Components Subject to AMR Table 2.3.4-8 lists the component types that require AMR and their intended functions.

Table 3.4.2-8, Aging Management Review Results - Sealing Steam System, provides the results of the AMR.

Table 2.3.4-8 Sealing Steam System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Piping Structural integrity Results Page 2.3-180b Amendment I Scoping and Screening Results and Screening Page 2.3-180b Amendment 1

Columbia Generating, Station License Renewal Application Technical: Information 3,4 AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEMS 3.4.1. Introduction Section 3A4 provides the results. of the aging, management, reviews (AMRs) for those, components identified in Section 2%34, Steam and Power Conversion Systems, as subject to AMR, The systems or portions of systems are described6in the indicated sections of the Application.

o Auxiliary ýSteam System (Sectiqni 2:3.41.1')

• Condensate (Auxiliary) System:r (Se tion 2,3-4,.2) o Condensate (Nuclear) System (Section2,34:4.3) o Main Steam System (Section 2.3.4.4),

, Main Steam Leakage Control System ,(Section 2:3.45)

• Miscellaneous Drain System:(S tion 2ý3.4A6)

• Reactoor.Feedwater System (Selction 2.3A47) i, a A.rot1pagte7 3i-3Ia4 Table 3,4t, Summary of Aging Management Program.s. for Steam and: Power Conve~rsion System sEvalated in Chaper VIII of NUREG4P  ! 801, provides the summary of the programs evaluated in. NUREGL1801 that .are applicable to. component and commodity groups, in this section. Text addressing summary items.requiring further evaluation is provided in Section 3.4.2.2.

3.4.2 Results The following tables summarize the results of the AMR for thea Steam and Power; Conversion Systems.

Table 3.4.2-1 Aging Management Review Results - Auxiliary. Steam System Table 3.4.2-2 Aging Management Review Results: - Condensate (Auxiliary) System Table 3.4.2--3 Aging Management Review Results - Condensate (Nuclear) System Table 3.4.2-4 Aging Management Review Results -Main Steam System Table 3.4.2-5 Aging Management Review Results.- Main Steam Leakage Control System Table 3,4,2.6 Aging Management Review Results - Miscellaneous Drain System Table 3.4.2-7 Aging Management Review Resuilts - Reactor Feed*arSstem Aging Management Review Rc uis Page 3.4-1 iAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.4.1 o Sealing Steam System (Section 2.3.4.8)

Insert B to LRA Section 3.4.2 Table 3.4.2-8 Aging Management Review Results - Sealing Steam System Page 3.4-la Amendment 1 Aging Review Results Management Review Aging Management Results Page 3.4-1 a Amendment 1

LJ35-5 Columbia Generating.Station 3.4.2.1,7 Reactor Feedwater System License Renewal Application Technical Information Aging IManagement Programs The: following aging management programs manage: the aging, effects for the subject mechanical components of the Reactor Feedwater System:

Bolting Integrity Program

• BWR Water Chemistry Program

, Chemistry Program Effectiveness. Inspection nertn:

. o 2.;

• External"Surfaces Monitoring Program ... :e... 2;..

• Flow-Accelerated Corerosion (FAC), Program 3.4.2.2, Further Evaluation of Aging Management as Recommended by NUREG-:1801 For the Steam and Power: Conversion systems;, those items. requiring further evaluation are addressed in the following sections.

3.4.2.2.1: Cumulative Fatigue Damage-Fatigue is a time-limited aging ianalysis, as defined in 10 CFR ,54.3. Timelimited aging analyses are required to be evaluated in accordance with 10 CFR 5412,(c*). Time-limited aging analyses identified. for fatigue in. the Steam and Power Conversion systems are evaluated in etin 4.3.4.

3.4.2.2.2 Loss of Material due to General, Pitting,_and Crevice Corrosion 3.4.2.2,2.1 Piping, Piping iping Elements, Tanks, and Heat Exchangers Loss ofý material due to general, pitting, and crevice corrosion for steel piping components and tanks exposed to treated water (including steam) in the Steam, and Power Conversion: systems is managed by the BWR. Water Chemistry:Program. The BWR Water Chemistry Program, manages aging effects through periodic rnonitoring and control of contaminants, The Chemistry Program Effectiveness inspection will provide a verification of the effectiveness of the 8WR Water Chemistry Program to manage loss of material due to general, pitting, and crevice corrosion through examination of steel piping components and tanks, exposed to treated water.

3.4.2.2.2.2 Piping, Piping Components, and Piping Elements--Lubricating Oil As described in Table 3.4.1, there are no components compared to item number 3.4.1-

07. There are no steel components exposed to a lubricating oil environment that are subject to AMR for the'Steam and Power Conversion systems.

Aging Management Review Resilts Page 3.4-9

[Amendment 1

L 57-Columbia Generating Station License Renewal Application Technical Information 3.4.2.1.8 Sealing Steam System Materials The materials of construction for subject mechanical components of the Sealing Steam System are:

• Steel Environments Subject mechanical components of the Sealing Steam System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

• Steam Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Sealing Steam System:

• Loss of material Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Sealing Steam System:

• BWR Water Chemistry Program o Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program

" Flow-Accelerated Corrosion (FAC) Program Aging Management Review Results Page 3.4-9a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.4.2-7 Aging Management Review Results - Reactor Feedwater System

.... . NUREGý-

Row Component Intended AginE Not-s Row Compnen Iuntonds Material Environment Requiring Agi.ng Managerment 1 801 Table Notes No. Type Functon.(s) Management Program iVolume. 1 Item

_____________ 2 temn Treated Treated Chemnistry Proga Structural water > 60 PC .material Loss of C p ti0 . ..o3.4.1.

iEffectiveness .. 04 A 0403 17Valve Body integrity !ite riy te {

Steel (1:40 'F): V1II..D2-7 3*o1

_ _ _(Internal).

Treated.

Structural. water> 60 PC: Loss of Flow-Accelerated 34A- A integrity Ste' (140 OF) .... material: Corrosion: (FAC): ViD2"8 ý9 0403 18 Valve. Sody interit I

'(Internal) .

Structura Air-indoor LoSS of External Surfaces 3141i 19 Valve Body Sterutu Steel u.ncontrolled m rM i "7 VIII H7 .

2Monitoring 28 A A

integrity (External) nse New TabI

.4.2~8fro~r~pag 3,4~7~a Results Review Results Page 3.4-76 Management Review Aging Management Page 3.4-756 j~enment 1 .Jnuf

LAJ 3S--s Columbia Generating Station License Renewal Application Technical Information Table 3.4.2-8 Aging Management Review Results - Sealing Steam System Aging Effect NUREG-Row Component Intended MaterialAging Management 1801 Table Notes No. Type Function(s) Management Program Volume '1 Item 2 Item 1 Piping Structural Steel Steam Loss of BWR Water VIII.C-4 3.4.1- A integrity (Internal) material Chemistry 02 2 Piping Structural Steel Steam Loss of Chemistry Program VIII.C-4 3.4.1- A integrity (Internal) material Effectiveness 02 Inspection 3 Piping Structural Steel Steam Loss of Flow-Accelerated VIII.C-5 3.4.1- A integrity (Internal) material Corrosion (FAC) 29 4 Piping Structural Steel Air-indoor Loss of External Surfaces VIII.H-7 3.4.1- A integrity uncontrolled material Monitoring 28 (External)

Amendment 1 Management Review Aging Management Results Review Results Page 3.4-76a Page 3.4-76a Amendment 1

w ss-i Columbia Generating Station Generic Notes Table 3.4.2-xx .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-&1801 determination for an Air-indoor uncontrolled (External) environment because the material is the sameiariand theintemal environment is equivalent tothe external. environmenttevaluated 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 s4ppression :pool..

0406 This steel compohent has an external surface temperature > 212 1F. 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 wil also manage cracking for the carbon and. low-aloy (steel) bolting at the base and foundation of the;CSTs due to potentialtfor ponding or pooling of water.

0408 The.Buried Pipingand Tankstlnsp ction Program will manage loss ofmaterial 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 ofematerial 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 isthe same and the internal environmentjis equivalent to the extemal environment evaluated in the'NUREG-1801 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.

.. ............. ....

j041 2 The 1orrnai. ovironrie~nt 'of the ea ling, Steam-Sysltem is evaltuatedt as a steam environment o.m *hen* the

• t anevaporat or re ief.Valves a ,'a actv ted . ... . . .. .

Aging Manapment-Review Reýsults "Mtaf:

Page 3...4-7 8 Emenment 1

JAJ 76O 2.3.3.29 Plant Service Water (TSW) System Columbia Generating Station License Renewal Application Technical Information License Renewal Drawinqs The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

LR-M508-1, LR-M548-2 Components Subject to AMR Table 2.3.3-28 lists the component types that require AMR and their intended functions.

Table 3.3.2-28, Aging Management Review Results - Plant Service Water System, provides the results of the AMR.

Table 2.3.3-28 Plant Service Water System Components Subject to Aging Management Review Intended Function Component Type J(as defined in Table 2.0-1)

Annubar Structural Integrity Bolting Structural Integrity Flow indicator (inline) Structural Integrity Orifice Structural Integrity Piping Structural Integrity Strainer (body) Structural Integrity Tubing Structural Integrity Valve body Structural Integrity Scoping and Screening Results Page 2.3-113 Amendment 1 ,I

WA. 3-5?

Columbia Generating Station 2.3.3.1 Circulating Water (CW) System License Renewal Application Technical Information Table 3.3.2-1, Aging Management Review Results - Circulating Water System, provides the results of the AMR.

Insert A from page 2.3-37a Table 2.3.3-1 Circulating Water System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Bolting Pressure Boundary Piping Pressure Boundary 4-ýWrP di-A ................ j Valve body Pressure Boundary Scoping and Screening Results Page 2.3-37 -JaTTu`a`rY-20TO-Amendment 1

WJ Columbia Generating Station License Renewal Application Technical Information Insert A to page 2.3-37 Per FSAR Section 9.2.5.3, if the service water spray headers are damaged by a tornado-generated missile, cooling is provided by a feed-and-bleed mode of operation.

In the feed-and-bleed mode, cooling water is supplied to the spray ponds from the makeup water pump house. The service water system takes suction from the spray ponds to provide cooling to safe shutdown equipment. The cooling water is then routed to tornado-protected underground circulating water piping and discharged to the circulating water basin. Since rupture disks CW-RD-1A/B are located in the circulating water basin, their failure will not prevent the Circulating Water System from performing its intended function. Since the rupture disks do not perform a license renewal intended function, they are not subject to AMR.

Amendment 1 Scoping and Screening Results and Screening Results Page 23-37a Page 2.3-37a Amendment 1

UA~) 3~

Columbia Generating Station 3,3,2,1,1 Circulating Water System License Renewal Application Technical Information Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Circulating Water System:

o Loss of material '---ýAdd: "Cracking"

" Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Circulating Water System:

• Bolting Integrity Program

• Buried Piping and Tanks Inspection Program

• External Surfaces Monitoring Program

" Open-Cycle Cooling Water Program

• Selective Leaching Inspection 3.3.2.1.2 Condensate Processing Radioactive (Demineralizer) System Materials The material of construction for subject mechanical components of the Condensate Processing Radioactive (Demineralizer) System is:

• Steel Environments Subject mechanical components of the Condensate Processing Radioactive (Demineralizer) System are exposed to the following normal operating environments:

" Air-indoor uncontrolled

• Treated water Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Condensate Processing Radioactive (Demineralizer) System:

o Loss of material

" Loss of pre-load Aging Management Review Results Page 3.3-6 --Janua 0 'y-2013

!Amendment 1

AJ3?-3 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-1 Aging Management Review Results - Circulating Water System Aging Effect NUREG-Row Component Intended Material Environment Requiring Table Notes No. Type Function(s) Management Program Volume Item 2 Item Bolting Pressure Steel Air-outdoor Loss of material Bolting Integrity VII.I-1 3.3.1-43 B boundary (External)

Pressure Air-outdoor Loss of 2 Bolting boundary Steel (External) pre-load Bolting Integrity N/A N/A H Piping Pressure Concrete water None None N/A N/A G boundary (Internal) 4 Pressure Concrete Soil I Piping boundary (External) None None II.B12-1 3.5.1-2 0301 Pressure Steel Raw water Loss of material Open-Cycle Cooling VI1.C1-19 3.3.1-76 B Piping boundary (Internal) Water PrsueAir-outdoor External3.Surfaces 6Pressure Steel Loss of material External Surfaces3.3.1-58 A

• boundary (External) Monitoring 7 Piping Pressure Steel Soil Loss of material Buried Piping and VII.Ce-18 3.3.1-19 A boundary (External) Tanks Inspection Pressure Stainless Raw water 0p eOn-Cyc olino 3, i 7 ..

boundary Steel (Internal) Water Pressure Stainless Raw water L.s of material Open-Cycle Cooling V11.C1-15 3. 4 B boundary -Steel (External) Water I

DLelete rows 8 and 9 __ _ _ __ _ _

Aging Management Review Results Page 3.3-118 jAmendment 1

6j Y-5 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-1 Aging Management Review Results - Circulating Water System TAging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801 Table 1 Notes No. Type Function(s) Management Program Volume Item 2 Item 10 Valve Body Pressure Gray Cast Raw water Loss of material Open-Cycle Cooling VII.C1-19 3.3.1-76 B boundary Iron (Internal) Water 11 Valve Body Pressure boundary Gray Iron Cast Raw water (Internal) Losofmteil3,3.1-85 Loss of material spectiVelonLeaching A 12 Valve Body Pressure Gray Cast Air-outdoor Loss of material External Surfaces VII.I-9 3.3.1-58 A boundary Iron (External) Monitoring 13 Valve Bd Pressure Raw water Loss of material Open-Cycle Cooling VII.C1-19 3.3.1-76 B boundary Steel (Internal) Water 14 Valve Body Pressure Steel Air-outdoor Loss of material External Surfaces VII.l-9 3.3.1-58 A boundary (External) Monitoring Insert new rows 15 through 21 for Table 3.3.2-1 as shown on page 3,3-119a Aging Management Review Results Page 3.3-119 A-meanudme01n0-jAmnendment 1"

1,J 37 -q Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-1 Aging Management Review Results - Circulating Water System NUREG-Row Component Intended Aging Effect Aging 1801 Table No. Type Function(s) Material Environment Requiring Management Volume I Item Notes Management Program 2 Item Pressure Soil Buried Piping 15 Bolting boundary Steel (External) Cracking and Tanks N/A N/A G Inspection Pressure Soil Buried Piping 16 Bolting boundary Steel (External) Loss of material and Tanks N/A N/A G Inspection Pressure Soil Loss of pre- Buried Piping 17 Bolting boundary Steel (External) loadand Tanks N/A N/A G

__...._ ..... boundary. trn l load (E .............. Inspection_ __ ___

Pressure Stainless Soil Buried Piping 18 Bolting boundary Steel (External) Cracking and Tanks N/A N/A F Inspection Pressure Stainless Soil Buried Piping 19 Bolting boundary Steel (External) Loss of material and Tanks N/A N/A F Inspection Pressure Stainless Soil Loss of pre- Buried Piping 20 Bolting boundary Steel (External) load and Tanks N/A N/A F Inspection Pressure Soil Buried Piping VII.C1-18 3.3.1- A 21 Valve body boundary Steel (External) Loss of material and Tanks 19 Inspection r 3.3-1 Wa Amendment 1 Review Results Aging Management Review Results 3.3-119a Amendment 1

Lk) 35"-I Columbia Generating Station License Renewal Application Technical Information an aggressive environment. Therefore, loss of material due to pitting and crevice corrosion is not an aging effect requiring management for these components.

3.3.2.2.10.7 Stainless Steel Piping, Piping Components, and Piping Elements - Soil As-desGr~bd-in-T-able-3 here- ar-e-*,Gmponents--Gmpared-toenimbe 29- There-is-no-stainless-steei-piping-subject-to-AMPR4or-oliumbia-4hats-exposed-o seai14n-the-Auxiliar-y-system& - Replace with Insert A on page 3,3-55a 3.3.2.2.10.8 BWR Standby Liquid Control System Loss of material due to pitting and crevice corrosion for stainless steel piping components and tanks exposed to sodium pentaborate solution is managed by the BWR Water Chemistry Program. The BWR Water Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Replace Program Effectiveness Inspection will provide a verification of the effectiveness of the with Insert 3WR Water Chemistry Program to manage loss of material due to pitting and crevice B from ý,orrosion through examination of stainless steel piping components and tanks exposed page to sodium pentaborate solution.

3.3-55a 3.3.2.2.11 Loss of Material due to Pitting, Crevice, and Galvanic Corrosion SAs,-desGrbeti-m-T-able-3-3-4,-thg~e-w~e-e-a-.Grmponents-Cempa-redto-tem-nmb 3-.3-.-34-. The re-are-no-copper--al loy-piping-piping -orponants-, -r--pip ing-elements-in the-Au-xiliary-systems-that-are-exposed-to-t-reated-vwate-..

3.3.2.2.12 Loss of Material due to Pitting, Crevice, and Microbiologically Influenced Corrosion 3.3.2.2.12.1 Piping, Piping Components, and Piping Elements - Fuel Oil There are no aluminum piping components exposed to fuel oil that are subject to AMR.

Loss of material due to pitting and crevice corrosion and MIC for stainless steel and copper alloy piping components exposed to fuel oil is managed by the Fuel Oil Chemistry Program. The Fuel Oil Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Program Effectiveness Inspection will provide a verification of the effectiveness of the Fuel Oil Chemistry Program to manage loss of material through examination of piping and components exposed to fuel oil.

3.3.2.2.12.2 Piping, Piping Components, and Piping Elements- Lubricating Oil Loss of material due to pitting and crevice corrosion and MIC for stainless steel piping components and heat exchanger components exposed to lubricating oil is managed by the Lubricating Oil Analysis Program. The Lubricating Oil Analysis Program manages aging effects through periodic monitoring and control of contaminants, including water.

The Lubricating Oil Inspection will provide a verification of the effectiveness of the Aging Management Review Results Page 3.3-55 January-2010 Amendment 1

W 3-Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.3.2.2.10.7 The Buried Piping Thanks Inspection Program, with enhancement, manages loss of material due to pitting and crevice corrosion and microbiologically influenced corrosion (MIC) for stainless steel piping and piping components buried in soil.

Insert B to LRA Section 3.3.2.2.11 Loss of material due to pitting, crevice, and galvanic corrosion for copper alloy piping, piping components, or piping elements exposed to treated water is managed by the BWR Water Chemistry Program. The BWR Water Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Program Effectiveness Inspection will provide a verification of the effectiveness of the BWR Water Chemistry Program to manage loss of material due to pitting, crevice, and galvanic corrosion through examination of copper alloy piping and piping components exposed to treated water.

Review Results Page 3.3-55a Amendment 1 Aging Management Review Aging Management Results Page 3.3-55a Amendment 1

W ND.

Columbia Generating Station License Renewal Application Technical Information Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1 801 Further Item Component/Commodity Aging Aging Management Evaluation Discussion Number Effect/Mechanism Programs Recommended 3.3.1-28 Copper alloy fire protection Loss of material A plant-specific aging Yes, plant Not applicable.

piping, piping components, and due to pitting and management program specific piping elements exposed to crevice corrosion is to be evaluated. There are no copper alloy fire condensation (internal) protection piping, piping components, or piping elements in the auxiliary systems that are exposed to condensation (internal).

Refer to Section 3.3.2.2.10.6 for further information.

3.3.1-29 Stainless steel piping, piping Loss of material A plant-specific aging Yes, plant NotappIc*able components, and piping due to pitting and management program specific elements exposed to soil crevice corrosion is to be evaluated. T-h" 'tainlest piping, piping opnnc Refer to Section 3.3.2.2.10.7 for further information.

Replace with Insert A on page 3.3-75a Aging Management Review Results Page 3.3-75 -dlu-at 2onI-

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Table 3.3.1 Item 3.3.1-29 The Buried Piping and Tanks Inspection Program, with enhancement, is credited to manage loss of material for stainless steel piping, piping components and piping elements (with or without coating or wrapping) in the auxiliary systems that are exposed to soil.

3.3-75a Amendment 1 Review Results Aging Management Review Results 3.3-75a Amendment 1

LA.)2T-3 Columbia Generating Station License Renewal Application Technical Information A.1.2.4 Bolting Integrity Program The Bolting Integrity Program is a combination of existing activities that, in conjunction with other credited programs, address the management of aging for the bolting of mechanical components and structural connections within the scope of license renewal.

The Bolting Integrity Program relies on manufacturer and vendor information and industry recommendations for the proper selection, assembly, and maintenance of bolting for pressure-retaining closures and structural connections. The Bolting Integrity Program includes, through the Inservice Inspection (ISI) Program, Inservice Inspection (1SI) Program - IWF, Structures Monitoring Program, and External Surfaces Monitoring Program, the periodic inspection of bolting for indications of degradation such as leakage, loss of material due to corrosion, loss of pre-load, and cracking due to stress corrosion cracking (SCC) and fatigue. Replace deleted text with to Ine rt Ateetonpage A 9a

-T-h IT id ne [tr's C 4 hup ei n. The Buried Piping and Tanks Inspection Program is a combination of a mitigation program (consisting of protective coatings) and a condition monitoring program (consisting of visual inspections).

An inspection of buried piping will be performed within the 10-year period prior to entering the period of extended operation. An additional inspection of buried piping will be performed within 10 years after entering the period of extended operation.

The Buried Piping and Tanks Inspection Program is an existing program that requires enhancement prior to the period of extended operation.

A.1.2.6 BWR Feedwater Nozzle Program The BWR Feedwater Nozzle Program is an existing program that manages cracking due to stress corrosion cracking and intergranular attack (SCC/IGA) and flaw growth of the feedwater nozzles. The BWR Feedwater Nozzle Program is in accordance with ASME Section XI and NRC augmented requirements.

The BWR Feedwater Nozzle Program consists of: (a) enhanced inservice inspection in accordance with the requirements of the ASME Boiler and Pressure Vessel Code, Section Xl, Subsection IWB, Table IWB 2500-1 (2001 edition including the 2002 and 2003 Addenda) and the recommendations of General Electric report NE-523-A71-0594-A [Reference A.1.4-1], and (b) system modifications, as described in FSAR Section 5.3.3.1.4.5, to mitigate cracking. The program specifies periodic ultrasonic inspection of critical regions of the feedwater nozzles.

Final Safety Analysis Report Supplement Page A-9 -Januar-201T lAmendme..nt] _'7

.

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section A.1.2.5 The Buried Piping and Tanks Inspection Program manages the effects of loss of material due to corrosion on the external surfaces of piping, piping components and tanks exposed to a buried environment. The program also manages the effects of cracking, loss of material and loss of pre-load for bolting exposed to a buried environment.

Page A-9a Amendment 1 Final Safety Analysis Final Safety Report Supplement Analysis Report Supplement Page A-9a Amendment 1

1,)J 37- '-

Columbia Generating Station License Renewal Application Technical Information Table A-1 Columbia License Renewal Commitments FSAR Enhancement Commitment Supplement or Item Number Location Implementation (LRA App. A) Schedule

5) Buried Piping The Buried Piping and Tanks Inspection Program is an existing A.1.2.5 Enhancement and Tanks program that will be continued for the period of extended operation, prior to the period Inspection with the following enhancements: of extended Program

• Revise the site program document to include the buried portions operation.

of the Radwaste Building Outside Air (WOA) piping. Then ongoing.

" Require that an inspection of a representative sample of buried piping be performed within the 10-year period prior to entering the Add Insert A period of extended operation (i.e., between year 30 and year 40). from page

• Require an additional inspection of a representative sample of A-43a buried piping be performed within 10 years after entering the period of extended operation (i.e., between year 40 and year 50).

6) BWR The BWR Feedwater Nozzle Program is an existing program that will A.1.2.6 Ongoing Feedwater be continued for the period of extended operation.

Nozzle Program

7) BWR The BWR Penetrations Program is an existing program that will be A.1.2.7 Ongoing Penetrations continued for the period of extended operation.

Program

8) BWR Stress The BWR Stress Corrosion Cracking Program is an existing program A.1.2.8 Ongoing Corrosion that will be continued for the period of extended operation.

Cracking Program Final Safety Analysis Report Supplement Page A-43 j~edent 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Table A-1 Item Number 5

• Revise the site program document to include cracking, loss of material and loss of pre-load of bolting as aging effects managed by the program.

• Revise the site program document to include loss of material of stainless steel piping and piping components as an aging effect managed by the program.

Final Safety Analysis Report Supplement Page A-43a Amendment 1

Columbia Generating Station License Renewal Application Technical Information B.2.5 Buried Piping and Tanks Inspection Program Program Description Tl~ uidPping-and a-s nspeetion- Ploldl Vil I e-dy~tnt're-ei-tid ius u of

[Replace with Insert A on page B-39a The Buried Piping and Tanks Inspection Program is a combination of a mitigation program (consisting of protective coatings) and a condition monitoring program (consisting of visual inspections). Integrity of coatings will be inspected when components are excavated for maintenance or other reasons. If an opportunistic inspection has not occurred between year 30 and year 38, an excavation of a section of buried piping for the purpose of inspection will be performed before year 40. An additional inspection of buried piping will be performed within 10 years after entering the period of extended operation.

The Buried Piping and Tanks Inspection Program will continue to ensure that the pressure boundary integrity of the subject components is maintained consistent with the current licensing basis during the period of extended operation.

NUREG-1801 Consistency The Buried Piping and Tanks Inspection Program is an existing Columbia program that, with enhancement, will be consistent with the 10 elements of an effective aging management program as described in NUREG-1801,Section XI.M34, "Buried Piping and Tanks Inspection."

Exceptions to NUREG-1801 None.

Required Enhancements Prior to the period of extended operation the enhancements listed below will be implemented in the identified program element:

Scope of Program -

Revise the site program document to include the buried portions of the Radwaste Building Outside Air (WOA) piping.

<------Add Insert B on page B-339a Aging Management Programs Page B-39 - t-y-2&

Amendment 1

WJ 3F-5' Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section B.2.5, page B-39 The Buried Piping and Tanks Inspection Program will manage the effects of loss of material due to corrosion on the external surfaces of piping, piping components and tanks exposed to a buried environment. The program also manages cracking, loss of material and loss of pre-load for bolting exposed to a buried environment.

Insert B to LRA Section B.2.5, page B-39 Revise the site program document to include cracking, loss of material and loss of pre-load of bolting as aging effects managed by the program.

Revise the site program document to include loss of material of stainless steel piping and piping components as an aging effect managed by the program.

Amendment 1 Aging Management Aging Programs Management Programs Page 8-39a Page B-39a Amendment 1

Columbia Generating Station 82.5 Buried Piping and Tanks Inspection Program License Renewal Application Technical Information o Detection of Aging Effects -

Require that an inspection of a representative sample of buried piping be performed within the 10-year period prior to entering the period of extended operation (i.e., between year 30 and year 40).

Require an additional inspection of a representative sample of buried piping be performed within 10 years after entering the period of extended operation (i.e.,

between year 40 and year 50).

Operating Experience No history of piping degradation due to external corrosion of buried piping was identified for Columbia through searches of operating experience or discussions with program owners. Columbia operating experience demonstrates that the coating of buried steel piping and tanks is effective in managing the effects of aging. Plant design considerations addressed the potential for degradation of buried piping components through the application of protective coatings.

A review was conducted of station piping failures, and it was determined that there had been no documented failures attributed to externally-initiated corrosion. Identified instances of leakage associated with buried piping have been the result of internal corrosion.

The environmental conditions at Columbia are very good based on the sandy soil and electrolyte resistivity of the soil which is considered very high. This has resulted in minimal degradation of buried piping as evidenced by excavations of certain sections of piping for examination. There have been no significant areas of degradation caused by protective coating failure. This was determined after a section of buried Standby Service Water (SW) System piping was excavated and evaluated in 2007.

Conclusion Replace with insert

[A on Page B-40a

-cooonr ous-metftibe- png-bennts-atried---ei-unreMiners- The Buried Piping and Tanks Inspection Program, with the required enhancements, provides reasonable assurance that the aging effects will be managed such that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Aging Management Programs Page B-40 -- JaRuarfy-24-1

[Amendment 1 /A

61 3y- 6 Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section B.2.5, page B-40 The Buried Piping and Tanks Inspection Program will manage cracking and loss of pre-load of bolting and loss of material due to corrosion for susceptible bolting, piping, piping components and tanks in buried environments.

Page B-40a Amendment 1 Aging Programs Management Programs Aging Management Page B-40a Amendment 1

W 3q Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-18 Aging Management Review Results - Diesel Fuel Oil System Row Component Intended Maeil Eniomnt Aging Rqiing Effect Aging Mfet angemnt TNUREG-1801 Table Noe No. Type Function(s) Material Environment Requiring Management Volume 2 1 Item Notes Management Program Item 73 T Pressure Stainless Fuel oil Loss of Fuel Oil VII.H1 6 3.3.1- B ubing boundary Steel (Internal) material Chemistry 32 Pressure Stainless Air-indoor 3.3.1-74 Tubing boundary Steel uncontrolled None None VII.J-15 A 74_____ Td(External)

Chemistry 75 Valve Body Pressure Steel Fuel oil Loss of Program VII.H1- 3.3.1- A boundary (Internal) material Effectiveness 10 20 Inspection 76 Valve Body Pressure Steel Fuel oil Loss of Fuel Oil VII.H1- 3.3.1- B boundary (Internal) material Chemistry 10 20 Air-indoor External Pressure Loss of Surfac 3.3.1-77 Valve Body boundary Steel uncontrolled materialSurfaces VII-8 58 A (External) Monitoring Chemistry 78 Valve Body Structural Steel Fuel oil Loss of Program VII.H1- 3.3.1- A integrity (Internal) material Effectiveness 10 20 Inspection 79 Valve Structural Steel Fuel oil Loss of Fuel Oil VII.H1- 3.3.1- B 7 Vav integrity (Internal) material Chemistry 10 20 1 Structural Air-outdoor Loss of External 3.3.1-80 Valve Body integrity Steel (External) material Surfaces VII.n-9 58 80 integrity Valve Body ~~Monitoring ______________

Insert new rows 81 through 86 for Table 3.3.2-18 as shown on page 3.3-215a Aging Management Review Results Page 3.3-215

[Amendment 1

i2 3q Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-18 Aging Management Review Results - Diesel Fuel Oil System Aging Effect Aging NUREG-Row Component Intended Aging Magint 1801 Table No. Type Function(s) Material Environment Requiring Management Volume I Item Notes Management Program 2 Item Pressure Soil Buried Piping 81 Bolting boundar Steel (External) Cracking and Tanks N/A N/A G ny Inspection Pressure Soil Buried Piping 82 Bolting boundary Steel (External) Loss of material and Tanks N/A N/A G Inspection Pressure Soil Loss of pre- Buried Piping 83 Bolting boury Steel load and Tanks N/A N/A G boundary (External) .oad Inspection Structural Soil Buried Piping 84 Bolting Steel Cracking and Tanks N/A N/A G integrity (External) Inspection Structural Soil Buried Piping 85 Bolting integrity Steel (External) Loss of material and Tanks N/A N/A G Inspection lLoss of pre- Buried Piping 86 Bolting integrity Steel (External) load Tanks N/A N/A G Structral Stel(Eternal loadInspection ____

Aging Management Review Results 3.3-215a Amendment 1

W 440o Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-22 Aging Management Review Results -Fire Protection System TAging Effect Aging NUREG-Row Component Intended Aging Management 1801 Table No. Type Function(s) Material Environment Requiring Management Volume 1 Item Notes Management

_ Program 2 Item 17 Vlv Bdy boundary Pressure Sel(internal) Raw water material Loss of FrWaeVtG-4 68A 3.3.1- A Air-idoorExternal Pressure Air-indoor Loss of Surfac V3.31-178 Valve Body boundary Steel uncontrolled (External) material maeilMonitoring Surfaces VII.-8 58 5 A (External)

Pressure Air-outdoor Loss of External 3.3.1-179 Valve Body Steel Surfaces VII.1-9 58 179 Va y boundary (External) material Monitoring 180Pressure PresureSoi alveBod Soil Loss Los of ofand Buried Piping Tanks VII. G-25 3.3.1-331 180 Valve Body boundary Steel (External) material Inspection 19 neret new rows 181 t rougi- 183 for Tabe 31.32-22 as shown on page 3,3-256a Aging Management Review Results Page 3.3-256 zamxraryT2OtOfr FAmendme -t1

jqo Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-22 Aging Management Review Results - Fire Protection System Row Component Intended Aging Effect Aging NUREG-Now Type Function(s) Material Environment Requiring Management 1801 Table Notes Manaemen Proram 2 Item Pressure Soil Buried Piping 181 Bolting boundary Steel (External) Cracking and Tanks N/A N/A G Inspection Pressure Soil Buried Piping 182 Bolting boundary Steel (External) Loss of material and Tanks N/A N/A G Inspection PresureSoil Loss of pre- Buried Piping BuidPpn 183 Bolting Peure Soil loss and Tanks N/A N/A G Iboundary (External) load Inspection 3.3-256a Amendment 1 Aging Review Results Aging Management Review Results 3.3-256a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-36 Aging Management Review Results - Radwaste Building HVAC Systems Row Component IntendedAinEfetgng11 Aging Effect Aging NUREG- Tal1 Row Type Intended Material Environment Requiring Management 1801 Table 1 Notes No.Management Program Volume Item 2 Item 92 Valve Body Structural integrity Air-indoor Loss of External 3.3.1-58A 9 Steel uncontrolled (External) material Surfaces Monitoring VII.I-8 58 Structural Condensation Loss of External 3.3.1-93 Valve Body integrity Steel (External) 9 material Surfaces VII.l-1 1 58A Monitoring 58 Insert new rows 94 through 99 for Table 3.3.2-36 as shown on page 3.3-328a Page 3.3-328 Aging Management Review Results Management Review Results Page 3.3-328 Amendment 1 _ January-204-0

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-36 Aging Management Review Results - Radwaste Building HVAC Systems Row Component Intended Aging Effect Aging NUREG-Row Cmponent Fnteone Material Environment No.Management Requiring Management 1801 Table I Notes Program Volume Item 2 Item Air-Handling Air-indoor External 94 Unit Housing Pressure Steel uncontrolled Loss of Surfaces VII.I-8 3.3.1- C0302 (WMA-AH-51A/B)(ntra)Mntig boundary (Internal) material Monitoring58 Air-Handling Unit Housing Pressure Condensation Loss of Cooling Units Vll.G-23 3.3.1- E0326 (WMA-AH- boundary (Internal) material Inspection 71 51 A/B)

Air-Handling Air-indoor External 96 Unit Housing Pressure Steel uncontrolled Loss of Surfaces VII.I-8 3.3.1-(WMA-AH-51 A/B) boundary (External) material Monitoring 58 A (EtmlIMntrn Pressure Soil Buried Piping 97 Bolting boundary Steel (External) Cracking and Tanks N/A N/A G Inspection Pressure Soil Loss of Buried Piping 98 Bolting boundary Steel (External) material and Tanks N/A N/A G

____ ____ _______ ____ ___ Inspection Pressure Soil Loss of Buried Piping 99 Bolting boury boundary Steel (External) pre-load and Tanks, I N/A Inspection I N/A G Aging Management Results Review Results Management Review Page Page 3.3-328a 3.3-328a Amendment 1 Amendment I

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-42 Aging Management Review Results - Standby Service Water System Row Component Intended TAging Aging Effect Aging Magint NUREG-1801 Table 1 No. Type Function(s) Material Environment Requiring Management Volume Item Notes Management Program 2 Item Air-indoor Structural Stainless 3.3.1- A 105 Valve Body integrity Steel uncontrolled None None VII.J-15 94 0306 (Internal) 106 Valve Body Structural Stainless Raw water Loss of Open-Cycle VII.C1-15 331- B integrity Steel (Internal) material Cooling Water 79 Structural Stainless Air-indoor 3.3.1-107 Valve Body integrity Steel uncontrolled None None VII.J-15 A 0 ntgrt V eod Stee(External)

Air-indoor External 108 Valve Body Strity Steel uncontrolled Surfaces VII.l-8 3.3.1- C integrity (Internal) material Monitoring 58 0302 109 Valve Body Structural Steel Raw water Loss of Open-Cycle V11.C1-19 3,3.1- B integrity (Internal) material Cooling Water 76 Air-indoor External Structural Ai-nor Loss of Exenl3.3.1- A 110 Valve Body Strity Steel uncontrolled Surfaces VII.l-8 8A (External) material Monitoring 58 Add new rows 111 through 116 shown on page 3.3-390a Aging Management Review Results Page 3.3-390 FAmendment e

(A)4 )

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-42 Aging Management Review Results - Standby Service Water System IAging eEffect Aging NUREG-Row No. Component Type Intended Function(s) Material N

Environment Evrnet Requiring Management Management Mngemn Program jVlm 1801 Volumem Table Itm Item Notes 2 Item Pressure Soil Buried Piping ill Bolting boundary Steel (External) Cracking and Tanks Inspection N/A N/A G Pressure Soil Buried Piping 112 Bolting boundary Steel (External) Loss of material and Tanks N/A N/A G Inspection Buried Piping Soil Loss of pre- and Tanks N/A N/A G Pressure 113 Bolting boundary Steel (External) load Inspection Pressure Stainless Soil Buried Piping 3.3.1-114 Orifice Loss of material and Tanks VII.C1-16 E boundary Steel (External) Inspection 29 Pressure Stainless Soil Buried Piping 3.3. --

115 Piping boundary Steel (External) Loss of material and Tanks VII.C1-16 29 E Inspection Pressure Stainless Soil Buried Piping 3.3.1-116 Valve body boundary Steel (External) Loss of material and Tanks VII.C1-16 29 E Inspection 3.3-390a Amendment 1 Review Results Aging Management Review Results 3.3-390a Amendment 1

W q3 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-43 Aging Management Review Results - Tower Makeup Water System SAging Effect Aging NUREG-Row Component Intended Material Environment Requiring Management 1801 Table 1 Notes No. Type Function(s) mtent Manvi Manam Volume Item

_Management Program 2 Item 37 Valve Body Pressure Steel Raw water Loss of Open-Cycle VII.C1-19 33.1- B boundary (Internal) material Cooling Water 76 Pressure Air-indoor Loss of External 3.3.1- A 38 Valve Body boundary Steel uncontrolled material Surfaces VII.l-8 58A (External) Monitoring 58 Pressure Air-outdoor Loss of External 3.3.1-39 Valve Body boundary Steel (External) material Surfaces VII.n9 58A

________Monitoring Pressure Condensation Loss of External 3.3.1-40 Valve Body boundary Steel (External) material Surfaces VIIiI-gl 58

________ __________________________Monitoring_________

Insert new rows 41 through 44 for Table 3.3.2-43 as shown on page 3.3-395a Aging Management Review Results Page 3.3-395 January 2010

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-43 Aging Management Review Results - Tower Makeup Water System Row Component Intended Material Environment SAgiRequiring ng Effect Aging Management NUREG-1801 Table Notes No. Type Function(s) Management Program Volume 1 Item Manaemet Prgra 2 Item Pressure Soil Buried Piping 41 Bolting boundary Steel (External) Cracking and Tanks N/A N/A G Inspection Soil Buried Piping Pressure N/A N/A G 42 Bolting boundary Steel (External) Loss of material and Tanks Inspection Pressure SelSoil Loss of pre- Burid Pipnks NAgi 43 Bolting boundary (External) load Inspection Pressure Soil Buried Piping 3 3 1-44 Valve Body boundary Steel (External) Loss of material and Tanks VII.C1-18 19 A boundary__ (External)__ Inspection 19 33-395a Amendment I Review Results Aging Management Review Results 3.3-395a Amendment 1

W~ LmL-Cokrmbi' 3eneratbng Statio-n License RenewaM Application Technical hntfrmation stuctural components that are safetyelated and are relied upon to remain fulnctional during and followng design basis events.

SStructural component~s that are NSR whose failure could,.prevent satisfactory accomplishment of safety-re d~ed f mnction:s.

Strutdural components that are relied on during postulated fires, anticipated transients without scram, and station blackout events.

FSAR References Section 37.84 of the FSAR describes the Diesel Generator Building.

COmponents Subiect to.AMR Table 244-5 lists the component types that require AMR and their intended functions.

The structural commodities for the Diesel Generator Building are addressed in the bulk commodities evaluation in Section 2.4.'3.

Table 3.5.2-5, Aging Management Review Results - Diesel Generator Building, provides the results .of the AMR.

Table 2.4-5 Diesel Generator Building Components Su.ject to Aging Management Review Component Type Intended Function (as defined in Table 2- 1)

Battery Racks SSR Diesel Generator Exhaust Plenums ENMBSRESSR Diesal Generator Intake Plenumcs EN, MB, SRE, SSR Diesel. Cnerator Pedestals __EXPEN, SSR Walls (abo~e grade)

)~air ____ L EN____?B, SRE, S ans EN, PXP SRE, ...

Reinforced

_Roof Concrete: Walls, Floors, and Ceilings i EN, EN, HB, MB, fvB, SRE,SRE, SSRSSR SS dctural Steel: Beams, Columns, Plates, and Trusses EN SSR (includes welds and bolted connections) -

d.on anww ble fs m ........... age .....

2. 4-24 Scaping and Screening Results Page 2,4-24

• e@

\mendment 1

Columbia Generating Station License Renewal ApplicatiOn Technical Information InsertA to pace 2.4-24 Table 2A4-5

!iesel Generator Building CGrnponents Subject to Aging Management Review Iompondrt Type

.'Intended Component Type Function (as defined in.Tble.2.0-1)

{South Exterior Slab JSRE __ _

2age 2.4-24a Amendment 1 Scoping Screeninq Results and Screening Scopinq and ReSUlf.5 Page 2.4-24a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3ý6.2-5 Aging Maniagerment Review Results - Diesel Generator Building Aging Effect NRG Row Component I intended Material Environment Aging Aging Management 1801 Table I No. Commodity Function 1 MEnng Program Volume 2 Item Notes

• ~Management*

_ __ _ _ _Item ENMBt Structures Monitoring 10 Roof Concrete Air-indoor None Program N/A N/A 001 o n0526 1 Refer to Table 2.0-1 for intended function descriptions.

Amendment 1 Aging Management Review Results Page 3.5-98

0 1_1 1 D, Columbia GerteatiriciStation License 'venewal Application T'echnica Information Insert A to page 3.5-9 Tabile35,-

Aging Management Review Results Page 3,5-98a Amendment 1

W 19 Columbia Generating Station License Renewal Application

_ !CTechnicallf fomIation TabWe 21 14 License; Renewal ,Seeping Results for M lchanical Systems (continued)}

Sys em Name In Scope? Screening Results Section Radwa ste Building CJhGed Water Yes Radwaste Building Exhaust: Air" Radwaste Building Heting Coindesate Yes=

No Radwas e B!ilding Mixed Air Ye Radwaste Buildinig Outside Ai Z3,3,,37 Radwaste Building Potable Hot Water No Radwaste Building Refrig eration Radwaste Building Return Air "Yes

~Reactor Building: Exhaust: Air Yes 2,3. 338, Reactor Building Outsid Air Yes Z'3, 3,38 Reac tr Building.Retur Ai (Erergenc. Ccolinj). Yes 2.3.38 Reactor Closed Cooling Water Yes j 2.33g Reactor Core Isolation Cooling Yes 7 23,32.2 Re ctor.Feedwater Yes 2.3A,7 Reactor Feedwater Turbine Reactor Protection System* Yes

'IA Reactor Recirculation Yes Reactor Service Equipme.nt No Reactor Water Cleanup Yes Residual Heat Removal Yes 2.3.24 2.33.23 Roof Drains Yes Reactor Recirculation Hydraulic Control No Sampling Yes Seal Oil No 2,3:342 Sealing Steam VK~7Ii Service Air Yes

~Ser~ice Building Chilled Water

.............................

'~1

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 1 of 15 License Renewal Application Amendment 1

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 2 of 15 Changed Sections and Page Number Section Page Change

• Number Number Type Table 2.2-1 2.2-4 28 W Table 2.2-1 2.2-4 29 W Table 2.2-1 2.2-4 30 W Table 2.2-1 2.2-6 48 W Table 2.2-1 2.2-6 35 W 2.3.2.3 2.3-24 13 R 2.3.2.3 2.3-24a 13 R 2.3.3 2.3-35 28 W 2.3.3 2.3-35 29 W 2.3.3 2.3-35 30 W 2.3.3.1 2.3-37 37 W Table 2.3.3-1 2.3-37 37 W 2.3.3.1 2.3-37a 37 W 2.3.3.2 2.3-38 24 W 2.3.3.10 2.3-57 21 W 2.3.3.18 2.3-80 14 R 2.3.3.18 2.3-80a 14 R E=Editorial - Summarized in Attachment I 0= Operating experience update review - Summarized in Attachment 2 R=Reference revision review update - Summarized in Attachment 3 W=Walkdown changes - Summarized in Attachment 4

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 3 of 15 Chanqed Sections and Paqe Number Section Page Change

• Number Number Type 2.3.3.21 2.3-90 26 W Table 2.3.3-21 2.3-91 26 W Table 2.3.3-21 2.3-91a 26 W 2.3.3.22 2.3-95 45 R 2.3.3.22 2.3-96 45 R 2.3.3.22 2.3-96 49 E Table 2.3.3-22 2.3-97 45 R Table 2.3.3-22 2.3-97a 45 R 2.3.3.23 2.3-98 25 W 2.3.3.24 2.3-101 27 W Table 2.3.3-24 2.3-102 27 W Table 2.3.3-24 2.3-102a 27 W 2.3.3.27 2.3-108 31 W 2.3.3.29 2.3-113 36 W Table 2.3.3-30 2.3-117 32 W Table 2.3.3-30 2.3-117a 32 W 2.3.3.41 2.3-146 34 W 2.3.3.48 2.3-162 28 W 2.3.3.48 2.3-162a 28 W

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• Number Number Type 2.3.3.48 2.3-162b 28 W 2.3.3.49 2.3-162c 29 W 2.3.3.49 2.3-162d 29 W 2.3.3.50 2.3-162e 30 W 2.3.3.50 2.3-162f 30 W 2.3.4 2.3-163 35 W 2.3.4.2 2.3-166 22 W Table 2.3.4-2 2.3-167 22 W Table 2.3.4-2 2.3-167a 22 W 2.3.4.3 2.3-169 23 W Table 2.3.4-3 2.3-170 23 W Table 2.3.4-3 2.3-170a 23 W 2.3.4.8 2.3-180 35 W 2.3.4.8 2.3-180a 35 W 2.3.4.8 2.3-180b 35 W 2.4.4 2.4-21 12 R Table 2.4-5 2.4-24 44 W Table 2.4-5 2.4-24a 44 W 2.5.3 2.5-3 1 E

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 5 of 15 Changed Sections and Page Number Section Page Change

• Number Number Type 2.5.6.2 2.5-8 2 E 3.3.1 3.3-2 28 W 3.3.1 3.3-2a 28 W 3.3.1 3.3-2 29 W 3.3.1 3.3-2a 29 W 3.3.1 3.3-2 30 W 3.3.1 3.3-2a 30 W 3.3.2 3.3-5 28 W 3.3.2 3.3-5a 28 W 3.3.2 3.3-5 29 W 3.3.2 3.3-5a 29 W 3.3.2 3.3-5 30 W 3.3.2 3.3-5a 30 W 3.3.2.1.1 3.3-6 37 W 3.3.2.1.21 3.3-25 26 W 3.3.2.1.24 3.3-29 27 W 3.3.2.1.29 3.3-34 7 R 3.3.2.1.32 3.3-36 9 R 3.3.2.1.45 3.3-50 28 W

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 6 of 15 Changed Sections and Page Number Section Page Change

• Number Number Type 3.3.2.1.45 3.3-50a 28 W 3.3.2.1.45 3.3-50b 28 W 3.3.2.1.46 3.3-50b 29 W 3.3.2.1.46 3.3-50c 29 W 3.3.2.1.47 3.3-50c 30 W 3.3.2.1.47 3.3-50d 30 W 3.3.2.2.11 3.3-55 28 W 3.3.2.2.11 3.3-55a 28 W 3.3.2.2.11 3.3-55 29 W 3.3.2.2.11 3.3-55a 29 W 3.3.2.2.11 3.3-55 30 W 3.3.2.2.11 3.3-55a 30 W 3.3.2.2.10.7 3.3-55a 38 W 3.3.2.2.10.7 3.3-55a 38 W Table 3.3.1, 38 W Item 3.3.1-29 Table 3.3.1, 3.3-75a 38 W Item 3.3.1-29 Table 3.3.1, 29 W Item 3.3.1-31 Table 3.3.1, 3.3-77a 29 W Item 3.3.1-31

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 7 of 15 Changed Sections and Page Number Section Page Change Section__ Number Number Type

• Table 3.3.1, 3.3-101 29 W Item 3.3.1-71 Table 3.3.1, 3.3-101a 29 W Item 3.3.1-71 Table 3.3-1 3.3-104 26 W Item 3.3.1-76 Table 3.3.1, 3.3-113 29 W Item 3.3.1-85 Table 3.3.1 3.3-115 28 W item 3.3.1-94 Table 3.3.2-1, 3.3-118 37 W rows 8 & 9, Table 3.3.2-1, new rows 15- 3.3-119 37 W 21 Table 3.3.2-1, new rows 15- 3.3-119a 37 W 21 Table 3.3.2-14, 3.3-180 7 R row 24 Table 3.3.2-14, 3.3-181 7 R row 25 Table 3.3.2-18, new rows 81- 3.3-215 39 W 86 Table 3.3.2-18, new rows 81- 3.3-215a 39 W 86 Table 3.3.3-21, Insert new rows 3.3-232 26 W 54-60

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• Number Number Type Table 3.3.3-21, Insert new rows 3.3-232a 26 W 54-60 Table 3.3.2-22, 3.3-248 46 R Row 120 Table 3.3.2-22, Rows 123, 124, 3.3-249 46 R

& 127 Table 3.3.2-22, new rows 181- 3.3-256 40 W 183 Table 3.3.2-22, new rows 181- 3.3-256a 40 W 183 Table 3.3.2-24, new rows 42- 3.3-263 27 W 47 Table 3.3.2-24, new rows 42- 3.3-263a 27 W 47 Table 3.3.2-29, 3.3-287 7 R row 18 Table 3.3.2-29, 3.3-288 7 R row 19 Table 3.3.2-30, new rows 11- 3.3-291 32 W 13 Table 3.3.2-30 new rows 11- 3.3-291a 32 W 13 Table 3.3.2-32, 3.3-294 9 R row 16 Table 3.3.2-34, 3.3-307 7 R rows 36 & 37

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• Number Number Type Table 3.3.2-34, 3.3-308 7 R row 45 Table 3.3.2-34, 3.3-309 7 R row 46 Table 3.3.2-36, 3.3-315 16 0 rows 1 & 2 Table 3.3.2-36, 3.3-320 7 R row 41 Table 3.3.2-36, 3.3-321 7 R row 42 Table 3.3.2-36, 3.3-325 6 R row 66 Table 3.3.2-36, new rows 94, 3.3-328 16 0 95, & 96 Table 3.3.2-36, new rows 94, 3.3-328a 16 0 95, & 96 Table 3.3.2-36, new rows 97, 3.3-328 41 W 98, & 99 Table 3.3.2-36, new rows 97, 3.3-328a 41 W 98 & 99 Table 3.3.2-37, 3.3-333 7 R row 36 Table 3.3.2-37, 3.3-334 7 R rows 37 Table 3.3.2-37, 3.3-3348 R rows 37 & 38 Table 3.3.2-37, new rows 86 & 3.3-340 9 R 87

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• Number Number Type Table 3.3.2-37, new rows 86 & 3.3-340a 9 R 87 Table 3.3.2-42, new rows 111- 3.3-390 42 W 116 Table 3.3.2-42, new rows 111- 3.3-390a 42 W 116 Table 3.3.2-43, new rows 41- 3.3-395 43 W 44 Table 3.3.2-43, new rows 41- 3.3-395a 43 W 44 Table 3.3.2-45 3.3-397 28 W Table 3.3.2-45 3.3-397a 28 W Table 3.3.2-45 3.3-397b 28 W Table 3.3.2-45 3.3-397c 28 W Table 3.3.2-45 3.3-397d 28 W Table 3.3.2-45 3.3-397e 28 W Table 3.3.2-45 3.3-397f 28 W Table 3.3.2-45 3.3-397g 28 W Table 3.3.2-46 3.3-397 29 W Table 3.3.2-46 3.3-397h 29 W Table 3.3.2-46 3.3-397i 29 W

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 11 of 15 Changed Sections and Page Number Section Page Change Section__ Number Number Type

• Table 3.3.2-46 3.3-397j 29 W Table 3.3.2-46 3.3-397k 29 W Table 3.3.2-46 3.3-3971 29 W Table 3.3.2-46 3.3-397m 29 W Table 3.3.2-47 3.3-397 30 W Table 3.3.2-47 3.3-397n 30 W Table 3.3.2-xx, plant specific 3.3-400 7 R note 0325 Table 3.3.2-xx, plant specific 3.3-400a 7 R note 0325 Table 3.3.2-xx, Plant specific 3.3-400 16 0 note 326 Table 3.3.2-xx, Plant specific 3.3-400a 16 0 note 326 Table 3.3.2-xx, Plant specific 3.3-400 46 R note 327 Table 3.3.2-xx, Plant specific 3.3-400a 46 R note 327 3.4.1 3.4-1 35 W 3.4.1 3.4-1a 35 W 3.4.2 3.4-1 35 W

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 12 of 15 Changed Sections and Page Number ScinPage Change Tye Section Number Number Type 3.4.2 3.4-1a 35 W 3.4.2.1.2 3.4-3 22 W 3.4.2.1.8 3.4-9 35 W 3.4.2.1.8 3.4-9a 35 W Table 3.4.1, 3.4-14 22 W Item 3.4.1-04 Table 3.41 3.4-14a 22 W Item 3.4.1-04 Table 3.4.2-2, new rows 21- 3.4-43 22 W 25 3.4.1-04 Table 3.4.2-2, new rows 21- 3.4-43a 22 W 25 Table 3.4.2-3, new rows 84- 3.4-53 23 W 87 Table 3.4.2-3, new rows 84- 3.4-53a 23 W 87 Table 3.4.2-8 3.4-76 35 W Table 3.4.2-8 3.4-76a 35 W Table 3.4.2-xx, plant specific 3.4-78 35 W note 0412 Table 3.5.2-5, new rows 11 & 3.5-98 44 W 12 Table 3.5.2-5, new rows 11 & 3.5-98a 44 W 12

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 13 of 15 Changed Sections and Page Number Section Page Change Type*

Number Number Table 4.3-2 4.3-4 15 R Table 4.3-2 4.3-4a 15 R A.1.2.5 A-9 38 W A.1.2.5 A-9a 38 W A.1.2.17 A-13 10 R A. 1.2.39 A-21 11 R A. 1.2.42 A-22 9 R Table A-i, item 5 A-43 38 W Table A-i, item 5 A-43a 38 W Table A-I, Item 17 17A-46 10 R Table A-i, Item A-49 6 R 23 Table38A-56 A-i, Item 3 E 38 Table39A-56 A-i, Item 11 R 39 Table B-2 B-23 11 R B.2.3 B-35 17 0 B.2.5 B-39 38 W B.2.5 B-39a 38 W B.2.5 B-40 38 W

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 14 of 15 Chanqed Sections and Paqe Number Section Page Change

• Number' Number Type B.2.5 B-40a 38 W B.2.14 B-68 16 0 B.2.14 B-68a 16 0 B.2.17 B-77 10 R B.2.17 B-78 10 R B.2.23 B-101 6 R B.2.23 B-102 6 R B.2.23 B-103 6 R B.2.28 B-120 4 E B.2.29 B-123 18 0 B.2.39 B-153 11 R B.2.39 B-154 11 R B.2.39 B-154 47 0 B.2.40 B-158 19 0 B.2.41 B-160 9 R B.2.41 B-160a 9 R B.2.42 B-163 9 R B.2.43 B-167 32 W B.2.47 B-179 28 W

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 15 of 15 Changed Sections and Page Number Page Change

• Section Number Number Type B.2.47 B-179 29 W B.2.50 B-196 5 E B.2.50 B-196 20 0 B.2.50 B-196a 20 0 B.2.51 B-197 22 W B.2.51 B-198 29 W B.2.53 B-207 20 0

Columbia Generating Station License Renewal Applicaioin Technical Ihformiation Table 2.2-1 License Renewal Scoping Resultsfor Mechanical Systems (continued)

System Name .In:Scope? Screening Results

' Section Flo0r Drain Radioactive. Yes 2.3.3.24 Fuel Oil Yes 2.3.3,18 Fuel Pool Cooling 'Yes 23325 Glycol No Guard House Exhaust Air No ,

Guard House Fire Protection No Guard House, Mixed Air No

,Guard House Outside Air Nd *-

Guard House.Potablie Hot Water "No Guard' Hbuse RetUrn Air No  ;

Heater Drain No Heater Vents No *'

Heating Hot Water No -

Heating Steam Yes -Ne L",

2.3.3.48' Heating Steam Condensate Ye -N- - .. 2.3.3.49 Heating Steam Vent [Ye .-No- 2.3.3.50 High-Pressure Core Spray Yes 2.3.2.3.

Hydrogen No ~>

Hydrogen Water Chemistry No .*,, -

Independent Spent Fuel Storage Installation No Instrument Rack Yes 2.3.3.40 Isophase Bus Duct Cooling No ,., ,,- ,

Laboratory Equipment (Permanent Plat) No .

Leak Detection Yes 2.8.326 Local Power Range Monitor Yes 2:3.1.2 Low-Pressure Core Spray Yes 2.3.2.4 Machine Shop Equipment No Main Steam Yes, 2.3.4.4 PlantýLevel S9coping Results Page2.2L4 Amnendment 1

]

Columbia Generating Station License RenewalApplicatio'n

.Technical Inf6rmati6n Table 2.2-1 License Renewal Scoping ResuItsI fr Mechanicai Systems (continued)

System Name in Scope? Screening Results Section Radwaste Building Chilled Water Yes, 2.33.36 Radwaste Building Exhaust Air Yes 2.3.3"37 Radwaste.Buildin'g Heating-,ondensate No __,

Radwaste Building Mixed Ai Yes 2.3.3137 Radwaste Building Outside Air Yes 2:3.37 Radwaste .Building Potable Hot Water No,-

Radwaste'Building Refrigeration No , .

Radwaste Building Return Air Yes 2,3337' Reactobr Bulding Exhaust Air Yes 2.3.3;38 Reactor Building OUtsideAir Yes 2.3.3.38 Reactor Building Return Air (Emergency Coling) Yes 23.3.3.38 Reactor Closed Cooling Water Yes 2.313.39 Reactor Core Iso1ation -ooling, Yes 2.3.2.2 Reactor Feedwater Yes 2.3.4.7 Reactor Feedwater Turbine No Reactor Protection System Yes 2,3.3A40 Reactor Recirculation Yes 2.3.1.3 Reactor Service Equipment No, ..... . j ....

Reactor Water Cleanup Yes 2.3,3,41 Residual Heat Removal Yes 2,3,&2.1 Roof Drains Yes 2:3.323 Reactor Recircula4tion Hydraulic Control 'No '

Sampling Yes 2.3.3.34 Seal Oil No Sealing Steam YesrnNe.

Service Air Yes, 213.42 Service Building Chilled Water 'No _______-______,_

Plaht-Level Scoplng "esults Page.2;2- '6 ,

jAmendment 1

Columbia Generating Station License Renewal Application Technical Information 2.3.2.3 High-Pressure Core Spray (HPCS) System

System Description

The HPCS System consists of a motor-driven centrifugal pump, a spray sparger in the reactor vessel located above the core (separate from the LPCS sparger), and associated system piping, valves, controls, and instrumentation. The HPCS System is designed to pump water into the reactor vessel over a wide range of vessel pressures.

For small breaks that do not result in rapid depressurization, the system maintains reactor water level. For large breaks, the HPCS System cools the reactor core by spray. The HPCS System also provides for core cooling in the event of a station blackout. Suction piping is provided from the condensate storage tank and also from the suppression pool. The elevation of the HPCS pump is sufficiently below the water level of both the condensate storage tanks and the suppression pool to provide a flooded pump suction and to meet pump net positive suction head (NPSH) requirements with the containment at atmospheric pressure and post-accident debris entrained on the beds of the suction strainers.

The HPCS discharge line fill system is designed to maintain the pump discharge line in a filled condition to ensure the time between the signal to start the pump and the initiation of flow into the reactor vessel is minimized. To ensure that any leakage from the discharge line is replaced and the line is always kept full, a water leg pump system is provided. Replace paragraph with Insert A

/sp Reason for Scope Determination The HPCS System provides RPV spray cooling during a large-break LOCA tat uriGOvers the cori, rrmairntairns RPV water level during a srrill-break LOCA that does nout depressLrize the reactor vessel, provides Primary Containment isolation and integrity (including valve position indication), and maintains the rcactorF coolant prcssurce boundary integrity. All of these system-intended functions are safety-related.

Theiefoie, 1lie HPCS Systei-m ,--eets the suph,iy i itel id of 10 CFR 54.4(d)(*).

The HPCS System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The HPCS System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1).

Therefore, the HPCS System meets the scoping criteria of 10 CFR 54.4(a)(2).

The HPCS System is also relied upon to demonstrate compliance with, and meets the 10 CFR 54.4(a)(3) scoping criteria for, the Environmental Qualification (10 CFR 50.49),

Anticipated Transients Without Scram (10 CFR 50.62), and Station Blackout (10 CFR 50.63) regulated events.

Scoping and Screening Results Page 2.3-24 jAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A for LRA Page 2.3-24 The HPCS System provides RPV spray cooling during a large-break LOCA that uncovers the core, maintains RPV water level during a small-break LOCA that does not depressurize the reactor vessel, provides Primary Containment isolation and integrity (including valve position indication), provides Secondary Containment isolation and integrity (including valve position indication), and maintains the reactor coolant pressure boundary integrity. All of these system-intended functions are safety-related. Therefore, the HPCS System meets the scoping criteria of 10 CFR 54.4(a)(1).

Page 2.3-24a Amendment 1 Scoping and Scoping Results Screening Results and Screening Page 2.3-24a Amendment 1

Columbia Generating Station 2.3.3 Auxiliary Systems License.Renewal Application Technical Information Leak Detection (LD) System (Section 2.3.3.26)

Miscellaneous Waste Radioactive (MWR) System (Section 2.3.3.27)

Plant Sanitary Drains (PSD) System (Section 2.3.3.28)

Plant Service Water (TSW) System (Section 2.3.3.29)

Potable Cold Water (PWC) System (Section 2.3.3.30)

Potable Hot Water (PWH) System (Section 2.3.3.31)

Primary Containment (C) System (Section 2.3.3.32)

Process Sampling (PS) System (Section 2.3.3.33)

Process Sampling Radioactive (PSR) System (Section 2.3.3,34)

Pump House HVAC Systems (Section 2.3.3.35)

Radwaste Building Chilled Water (WCH) System (Section 2.3.3.36)

Radwaste Building HVAC Systems (Section 2.3.3.37)

Reactor Building HVAC Systems (Section 2.3.3.38)

Reactor Closed Cooling Water (RCC) System (Section 2.3.3.39)

Reactor Protection System (RPS) (Section 2.3.3.40)

Reactor Water Cleanup ,(RWCU) System (Section 2.3.3.41)

Service Air (SA) System (Section.2.3.3.42)

Standby Liquid Control (SLC) System (Section 2.3.3.43)

Standby Service Water (SW) System (Section 2.3.3.44)

Suppression Pool Temperature Monitoring (SPTM) System (Section 2.3.3,45)

Tower Makeup Water (TMU) System (Section 2.3.3.46)

Traversing Incore Probe (TIP) System (Section 2.3.3.47)

A brief system description, reason for scope determination, associated FSAR references, associated license renewal drawings, and components subject: to AMR information are provided for each system.

Insert:

"Heating Steam (HS) System (Section 2.3.3.48)

Heating Steam Condensate (HCO) System (Section 2.3.3.49)

Heating Steam Vent (HSV) System (Section 2.3.3.50)"

Scoping and Screening Results Page 2.3-35 j,,U,,.20-10

[Amendment 1 _j-

Columbia Generating Station 2.3.3.1 Circulating Water (CW) System License Renewal Application Technical Information Table 3.3.2-1, Aging Management Review Results - Circulating Water System, provides the results of the AMR.

Insert A from page 2.3-37a Table 2.3.3-1 Circulating Water System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Bolting Pressure Boundary Piping Pressure Boundary 1., L In'n~lr I=

Cin 0 zp. I I-~~Ir Valve body Pressure Boundary Page 2.3-37 JdIIudry 2010 Scoping and Scoping and Screening Results Screening Results Page 2.3-37 Jai wary 20 10

---

JAmendment 1 r

Columbia Generating Station License Renewal Application Technical Information Insert A to page 2.3-37 Per FSAR Section 9.2.5.3, if the service water -spray headers are damaged by a tornado-generated missile, cooling is provided by a feed-and-bleed mode of operation.

In the feed-and-bleed mode, cooling water is supplied to the spray ponds from the makeup water pump house. The service water system takes suction from the spray ponds to provide cooling to safe shutdown equipment. The cooling water is then routed to tornado-protected underground circulating water piping and discharged to the circulating water basin. Since rupture disks CW-RD-1A/B are located in the circulating water basin, their failure will not prevent the Circulating Water System from performing its intended function. Since the rupture disks do not perform a license renewal intended function, they are not subject to AMR.

Page 2.3-37a Amendment 1 Scoping Screening Results and Screening Scoping and Results Page 2.3-37a Amendment 1

Columbia Generating Station License Renewal Application Technical Information 2.3.3.2 Condensate Processing Radioactive (Demineralizer) (CPR) System

System Description

The CPR System, also referred to as the Condensate Filter Demineralizer System, is designed to maintain feedwater quality such that the reactor water limits are not exceeded. The system removes corrosion products, condenser inleakage impurities, and impurities present in the condensed steam. The system controls the condensate impurity concentration during plant operation. The system functions as a chemical mixing and supply system to clean the filter demineralizer units and direct the waste to the chemical waste system, as a backwash system to remove the spent resin from the filter demineralizers and direct the waste to the backwash receiving tank, and as a precoat system to circulate fresh precoat material through the filter demineralizers.

Reason for Scope Determination The CPR System does not perform any safety-related system-intended functions that meet the scoping criteria of 10 CFR 54.4(a)(1).

The CPR System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The CPR System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1).

Therefore, the CPR System meets the scoping criterion of 10 CFR 54.4(a)(2).

The CPR System is not relied upon to demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events.

FSAR References Section 10.4.6 of the FSAR describes the Condensate Filter Demineralizer System, evaluated for license renewal as the Condensate Processing Radioactive (Demineralizer) System.

License Renewal Drawinqgs The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

LR-M523-1, LR-M526-1 - l536" Components Subject to AMR Table 2.3.3-2 lists the component types that require AMR and their intended functions.

Table 3.3.2-2, Aging Management Review Results - Condensate Processing Radioactive (Demineralizer) System, provides the results of the AMR.

Scoping and Screening Results Page 2.3-38 +amtary-2 jAmendment 1

Columbia Generating Station License Renewal Application Technical Information 2.3.3.10 Control Air System (CAS)

System Description

The CAS provides oil-free, filtered, and dried instrument-quality air throughout the plant for pneumatic instrumentation, controls, and actuators. The CAS also provides air to the outboard MSIV accumulators, and to the wetwell vacuum breaker solenoid pilot valves. The system is designed to provide uninterrupted service during normal plant operation.

The air receivers store compressed air to serve associated pneumatic loads. The Cooling Jacket Water (CJW) System is a closed water system provided to cool the three CAS compressors and the two CAS refrigerated dryers. Operation of CAS is not required for the initiation of any engineered safeguard system or for safe shutdown of the reactor, but is required for continuous plant operation. Based on this, operation of the CAS is not required for mitigation of a design basis accident or abnormal operational transient.

Reason for Scope Determination The CAS provides Primary Containment isolation and integrity. This system-intended function is safety-related. Therefore, the CAS meets the scoping criteria of 10 CFR 54.4(a)(1).

The CAS does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The CAS does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1). Therefore, the CAS meets the scoping criteria of 10 CFR 54.4(a)(2).

The CAS is not relied upon to demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events.

FSAR References Sections 9.3.1.1.1 and 9.3.1.3.1 of the FSAR describe the Control Air System.

License Renewal Drawings The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

LR-M510-2, LR-M510-2A Components Subject to AMR Table 2.3.3-10 lists the component types that require AMR and their intended functions.

Scoping and Screening Results Page 2.3-57 TV-Je*,*ie'y,;201

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information 2.3.3.18 Diesel Fuel Oil (DO) System

System Description

The DO System consists of separate, independent diesel oil supply systems serving each of the diesel generators. Each of these systems consists of a fuel oil storage tank, a transfer pump, a day tank, interconnecting piping and valves, and associated instruments and controls.

The auxiliary boiler fuel oil storage tank (FO-TK-1) is used as an additional storage tank for the emergency diesel generator fuel oil storage and transfer system. This tank is maintained to the same cleanliness requirements as the other Class I fuel oil tanks.

The diesel fuel oil stored in this tank is surveyed to the same requirements as the fuel oil in the other diesel storage tanks. Replace paragraph with Insert A shown on page 2.3-80a Thel [uel ail supply [rui tlhe day Ldtaks tuto teadiesl Ullyiwut IuIistiL u[ twu tomutually r.dundant syst. Either

-s. system is capable of supplying fuel ail to the engine. Each system contains a fuel oil supplyline strainc,, fuel oil pump, dupl, x filtre pF,rss.

"augjev,and -:-el and lhe .. 'val.

One of the fuel oil supply pumps is mechanically driven by the engine and is normally used during engine operation. The other supply pump is driven by a 120-V DC motor and is used to fill the fuel oil system and fuel header prior to initial operation and after maintenance has been performed on system piping and components. The DC-motor-driven pump runs during engine operation in the event fuel supply through the engine-driven pump system fails. Add new paragraph from Insert B shown on page 2.3-80a Reason for Scope Determination The DO System provides fuel oil to enable the emergency diesel generators to start, run, and load. This system-intended function is safety-related. Therefore, the DO System meets the scoping criteria of 10 CFR 54.4(a)(1).

The DO System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The DO System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1). Therefore, the DO System meets the scoping criteria of 10 CFR 54.4(a)(2).

The DO System is relied upon to demonstrate compliance with, and meets the 10 CFR 54.4(a)(3) scoping criteria for, the Fire Protection (10 CFR 50.48), Anticipated Transients Without Scram (10 CFR 50.62), and Station Blackout (10 CFR 50.63) regulated events.

Scoping and Screening Results Page 2.3-80 January 2010 jAmendmentf1

Columbia Generating Station

'License Renewal Application Technical Information Insert A for LRA Page 2.3-80 The fuel oil supply from the day tanks to each diesel engine consists of two systems.

Either system is capable of supplying fuel oil to the engine. For diesel generator sets 1 and 2, each system contains a fuel supply line strainer, fuel oil pump, duplex filter, pressure gauge, relief and check valves, and separate fuel return lines to the day tanks.

Insert B for LRA Page 2.3-80 For the HPCS diesel generator, there are two fuel oil systems external to the engine fuel manifolds, either of which is capable of supplying fuel oil to the engine. One of the fuel oil pumps is mechanically driven by the engine and the other by a 120-V DC motor.

The systems contain the following components from the day tank: fuel supply lines, strainers, fuel oil pumps, duplex filters, and relief and check valves. The two systems join together at the manifold for the duplex filter of the engine-driven fuel oil pump and share that duplex filter, a pressure gage, fuel lines and manifolds to the injectors, injectors, and a return line to the day tank.

Page 2.3-80a Amendment 1 PageResults Scoping and Screening Results Scoping and Screening 2.3-80a Amendment 1

2.3.3.21 Equipment Drains Radioactive (EDR) System Columbia Generating Station LicenseTechnical Renewal Application Information Reason for Scope Determination The EDR System provides Primary Containment isolation and integrity (including valve position indication), and secondary containment isolation and integrity (including valve position indication). These system-intended functions are safety-related. Therefore, the EDR System meet the scoping criteria of 10 CFR 54.4(a)(1).

The EDR System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The EDR System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1).

Therefore, the EDR System meets the scoping criteria of 10 CFR 54.4(a)(2).

The EDR System is relied upon to demonstrate compliance with, and meets the 10 CFR 54.4(a)(3) scoping criteria for, the Environmental Qualification (10 CFR 50.49) regulated event.

FSAR References Section 9.3.3.2.1 of the FSAR describes the Radioactive Equipment Drainage System, evaluated for license renewal as the Equipment Drains Radioactive System.

License Renewal Drawin-qs The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal: Insert: ", LR-M53 LR-M521-2, LR-M523-2, LR-M537, LR-M539 Components Subiect to AMR Table 2.3.3-21 lists the component types that require AMR and their intended functions.

Table 3.3.2-21, Aging Management Review Results - Equipment Drains Radioactive System, provides the results of the AMR.

Solenoid pilot valves and the associated air lines provide a control air supply to actuators for the primary and secondary containment isolation valves (EDR-V-19, EDR-V-20, EDR-V-394, and EDR-V-395). Failure of the air supply places the valve in a safe position that supports the system function. Therefore, pressure boundary integrity is not a required component intended function of these solenoid valves, air supply lines, or actuators for the system to perform its intended function. Since these components have no other component intended function, they are not subject to AMR.

The external subcomponents (shell and channel covers) of the in-scope heat exchangers will contain fluid leakage in the event of a failure of an internal Scoping and Screening Results Pa e 2.3-90 .. puary 2010 JAmendment 1

Columbia Generating Station License Renewal Application Technical Information subcomponent (tubes and tubesheet). Failure of an internal subcomponent will therefore not create the potential for spatial interaction that could prevent a safety-related SSC from performing its intended function. As a result, the internal subcomponents (tubes and tubesheet) of the in-scope heat exchangers are not subject to AMR.

Table 2.3.3-21 Equipment Drains Radioactive System Components Subject to Aging Management Review Component Type Intended Function Component__Type_(as defined in Table 2.0-1)

Bolting Pressure Boundary Structural Integrity Heat exchanger (channel and shell) Structural Integrity Orifice Structural Integrity Piping Pressure Boundary Structural Integrity Sight glass Structural Integrity Tubing Structural Integrity Valve body Pressure Boundary Structural Integrity 1ý'lýý nsert ýAfromýpag~e 2.3-91 a I Scoping and Screening Results Page 2.3-91 JAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to Table 2.3.3-21:

Pump casing Tank Structural Integrity Structural Integrity Colu Gene Amendment 1 Scoping and Screening Results and Screening Results Page 2.3-91a Page 2.3-91 a Amendment 1

Columbia Generating Station 2.3.3.22 Fire Protection (FP) System License Renewal Application Technical Information The Carbon Dioxide and Dry Chemical Fire Suppression systems do not contain components that perform a license renewal intended function, and therefore are not within the scope of license renewal.

The diesel fuel oil lines that supply fuel oil to the fire protection pump diesels, designated as DO on the drawings, and the fire protection pump diesel engine exhaust piping, designated as DE on the drawings, are within the evaluation boundaries of the Fire Protection System.

Components Subiect to AMR Table 2.3.3-22 lists the component types that require AMR and their intended functions.

Table 3.3.2-22, Aging Management Review Results - Fire Protection System, provides the results of the AMR.

Portable fire extinguishers are within the scope of license renewal. However, they are periodically inspected and hydrostatically tested, and are replaced if they do not pass an inspection or test. Portable fire extinguishers are short-lived components, subject to replacement based on a qualified life or specified time period, and not subject to AMR.

Fire and smoke detectors, and alarm devices, do not perform a passive mechanical function for the purpose of license renewal. Electrical components that are subject to AMR (the cables for the detectors and alarms) are addressed in Section 2.5.

Fire barriers, fire dampers, fire doors, and fire penetration seals determined to be within the scope of license renewal and subject to AMR are addressed as structural commodities in Section 2.4.13.

Fire hoses are within the scope of license renewal. However, they are periodically inspected to ensure that they are in an acceptable operating condition. These ongoing hose station inspections (together with the associated action to repair or replace any fire hose noted to be in a deteriorated condition) establish a qualified life for the hoses.

Therefore, the fire hoses are not subject to AMR.

The pre-action sprinkler systems are connected to the Control Air System. A failure of the air system will place the sprinkler system in a safe position. That is, the fusible link closed sprinkler heads will maintain water inventory in the piping and the sprinkler system will still be able to perform its system-intended function. Therefore, since this portion of the Control Air System, and associated components, does not have any other component intended function, the portion of the air system included within the Fire Protection System boundary is not subject to AMR.

,i--Insert: "fire pump" l Thehdiese engines, except for the attached heat exchanger, are evaluated as active components and not subject to AMR.

Scoping and Screening Results Page 2.3-95

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information The jockcy pumAps arc not essential firc protection equipment per Columnbia Licensee Controlled Speeificationgs (LOS-) 1.10.1. Therofore, since the jeckey pumps de not have a omponent intended function, they are-,notsbjeCt to A,,R] (DOT)

Halon cylinders are within the scope of license renewa he principal design criterion for these bottles is Department of Transportation tandards. The halon cylinders comply with the requirements of the DOT standards. The halon cylinders are consumables, replaced periodically in accordance with DOT standards, and are not subject to AMR.

The Fire Protection bladder tank (FP-TK-110) is within the scope of license renewal.

However, it has a service life of approximately 20 years and was replaced accordingly in 2008. The replacement tank is of a similar design, with the same limited service life, and is subject to inspections to ensure its timely replacement. The bladder tank is short-lived, subject to replacement based on a qualified life or specified time period, and is not subject to AMR.

Scoping and Screening Results Page 2.3-96 -affa&y- -

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 2.3.3-22 Fire Protection System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Bolting Pressure Boundary Structural Integrity Exhaust silencer Pressure Boundary Flexible connection Pressure Boundary Heat exchanger (shell) Pressure Boundary Heat exchanger (tubes) Heat Transfer Pressure Boundary Hydrant Pressure Boundary Orifice Pressure Boundary Throttling Piping Pressure Boundary Structural Integrity Pump casing Pressure Boundary Spray nozzle Pressure Boundary Spray Sight glass Pressure Boundary Strainor (body and screen) F4ai-Prsswuro Boun..ary Tank Pressure Boundary Tubing Pressure Boundary Structural Integrity Valve body Pressure Boundary Structural Integrity I

Replace this table row with "Insert A" from page 2.3-97a Scoping and Screening Results Page 2.3-97

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A for LRA Paqe 2.3-97 Strainer (body) Pressure boundary Strainer (screen) Filtration Scoping and Screening Results Page 2.3-97a Amendment 1

Columbia Generating Station License Renewal Application Technical Information 2.3.3.23 Floor Drain (FD) System

System Description

The FD System consists of non-radioactive floor drain subsystems in the Service Building and Turbine Building.

Floor drains from normally uncontaminated areas of the Turbine Building are collected in three sumps. All three sumps are routed to the Radwaste System for processing.

Floor drains in the Service Building are collected in a single sump containing two sump pumps. Water collected in the Service Building floor drain sump is pumped to the storm water drainage system. Water collected by the storm water drainage system is conveyed by a concrete pipe to a point approximately 1,500 feet northeast of the plant.

The pipe discharges to an earthen channel that carries the water to a small unlined evaporation and percolation pond. Roof drains, which are evaluated as part of the FD System, are drained by gravity or pumped to the storm drain system.

Reason for Scope Determination The FD System contains components designated as safety-related by Columbia choice.

Therefore, the FD System meets the scoping criteria of 10 CFR 54.4(a)(1).

The FD System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The FD System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1). Therefore, the FD System meets the scoping criteria of 10 CFR 54.4(a)(2).

The FD System is not relied upon to demonstrate compliance with any regulated event and does not meet the 10 CFR 54.4(a)(3) scoping criteria.

FSAR References Section 9.3.3.2.3 of the FSAR describes the Nonradioactive Water Drainage System, and the Roof Drain System, evaluated collectively for license renewal as the Floor Drain System.

License Renewal Drawings The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

LR-M539, LR-M540, LR-M788-1, LR-M852, LR-216-01,3682-' l Scoping and Screening Results Page 2.3-98 * -Jýtta H

[Amendment 1

Columbia Generating Station 2.3.3.24 Floor Drains Radioactive (FDR) System License Renewal Application Technical Information FDR-V-3 and FDR-V-4). These system-intended functions are safety-related.

Therefore, the FDR System meets the scoping criteria of 10 CFR 54.4(a)(1).

The FDR System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The FDR System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1).

Therefore, the FDR System meets the scoping criteria of 10 CFR 54.4(a)(2).

The FDR System is relied upon to demonstrate compliance with, and meets the 10 CFR 54.4(a)(3) scoping criteria for, the Environmental Qualification (10 CFR 50.49) regulated event.

FSAR References Section 9.3.3.2.2 of the FSAR describes the Radioactive Floor Drainage Subsystem, evaluated for license renewal as the Floor Drain Radioactive System.

License Renewal Drawings The following license renewal drawing depicts the evaluation boundaries for the system components within the scope of license renewal:

LR-M539 -M 1" Components Subject to AMR Table 2.3.3-24 lists the component types that require AMR and their intended functions.

Table 3.3.2-24, Aging Management Review Results - Floor Drain Radioactive System, provides the results of the AMR.

Solenoid pilot valves and associated air lines provide a control air supply to actuators for the primary and secondary containment isolation valves (FDR-V-3, 4, and 219 through 222). Failure of the air supply places the valve in a safe position that supports the system function. Therefore, pressure boundary integrity is not a required component intended function of these solenoid valves, air supply lines, or actuators for the system to perform its intended function. Since these components have no other component intended function, they are not subject to AMR.

Spectacle flanges (FDR-SF-1 and 2) are normally open. As such the spectacle does not perform any license renewal function and is not subject to AMR. The flange portion of the component is evaluated as piping.

Scoping and Screening Results Page 2.3-101 5MeFttiEfy l0 IAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 2.3.3-24 Floor Drain Radioactive System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Bolting Pressure Boundary Structural Integrity Orifice Structural Integrity Piping Pressure Boundary Structural Integrity Tubing Structural Integrity Valve body Pressure Boundary Structural Integrity Insert A from page 2.3-102a Scoping and Screening Results Page 2.3-102 -1a JAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to Table 2.3.3-24:

Pump casing Structural Integrity Tank Structural Integrity Page 2.3-102a Amendment 1 Scoping Screening Results and Screening Scoping and Results Page 2.3-102a Amendment 1

Columbia Generating Station License Renewal Application Technical Information 2.3.3.27 Miscellaneous Waste Radioactive (MWR) System

System Description

The MWR System is designed to collect water in the Reactor, Turbine, and Radwaste buildings that can contain potentially radioactive detergent and transfer the fluid directly by gravity to the Radwaste Building sump or the detergent drain tanks. It is also used to drain the decontamination solution in the Reactor Building from the decontamination pit and Reactor Closed Cooling Water chemical addition tank to the chemical waste tanks.

Additionally the system also consists of SLC System drains. These equipment and floor drains collect borated water from the SLC System and direct it to 55-gallon drums located in the Reactor Building.

Reason for Scope Determination The MWR System provides Primary Containment isolation and integrity, and secondary containment isolation and integrity. These system-intended functions are safety-related.

Therefore, the MWR System meet the scoping criteria of 10 CFR 54.4(a)(1).

The MWR System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The MWR System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1).

Therefore, the MWR System meets the scoping criteria of 10 CFR 54.4(a)(2).

The MWR System is not relied upon to demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events.

FSAR References Section 11.2 of the FSAR describes the Liquid Waste Management System, evaluated for license renewal as the MWR System License Renewal Drawings The following license renewal drawing depicts the evaluation boundaries for the system components within the scope of license renewal:

Insert: ", LR-M531, LR-M533-1, LR-M539 <LR-M533-2" Components Subject to AMR Table 2.3.3-26 lists the component types that require AMR and their intended functions.

Table 3.3.2-26, Aging Management Review Results - Miscellaneous Waste Radioactive System, provides the results of the AMR.

Scoping and Screening Results Page 2.3-108 -Januelar-204-jAmendment 1 L

2.3.3.29 Plant Service Water (TSW) System Columbia Generating Station License Renewal Application Technical Information License Renewal DrawinQs The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

LR-M508-1, LR-M548-2 -. nset: ", LR-M-2" Components Subiect to AMR Table 2.3.3-28 lists the component types that require AMR and their intended functions.

Table 3.3.2-28, Aging Management Review Results - Plant Service Water System, provides the results of the AMR.

Table 2.3.3-28 Plant Service Water System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Annubar Structural Integrity Bolting Structural Integrity Flow indicator (inline) Structural Integrity Orifice Structural Integrity Piping Structural Integrity Strainer (body) Structural Integrity Tubing Structural Integrity Valve body Structural Integrity Scoping and Screening Results Page 2.3-113 IAmendment 1

! l

2.3.3.31 Potable Hot Water (PWH) System Columbia Generating Station License Renewal Application Technical Information before adverse consequences (i.e., interaction with safety-related structures and components) would manifest. Therefore, plumbing fixtures are not subject to AMR.

Table 2.3.3-30 Potable Hot Water System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Piping Structural Integrity Shock suppressor Structural Integrity Valve body Structural Integrity Insert A from page 2.3-117a Scoping and Screening Results Page 2.3-117 denuay--

JAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to Table 2.3.3-30:

Tubing Structural Integrity Page 2.3-1 17a Amendment 1 Scoping Screening Results and Screening Scoping and Results Page 2.3-117a Amendment 1

2.3.3.41 Reactor Water Cleanup (RWCU) System Columbia Generating Station License Renewal Application Technical Information FSAR References Section 5.4.8 of the FSAR describes the Reactor Water Cleanup System.

License Renewal Drawings The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

• ___..___..- Insert: ", LR-M536"I LR-M523-1, LR-M523-2 Portions of the RWCU System are in the Radwaste Building and outside of the control room tower boundary; as such these components are outside the scope of license renewal. This includes the filter demineralizer subsystem and its associated demineralizers, piping, pumps, and tanks.

Components Subiect to AMR Table 2.3.3-39 lists the component types that require AMR and their intended functions.

Table 3.3.2-39, Aging Management Review Results - Reactor Water Cleanup System, provides the results of the AMR.

The external subcomponents (shell and channel covers) of the RWCU heat exchangers will contain fluid leakage in the event of a failure of an internal subcomponent (tubes and tubesheet). Failure of an internal subcomponent will therefore not create the potential for spatial interaction that could prevent a safety-related SSC from performing its intended function. Therefore, the RWCU heat exchanger tubes and tubesheets are not subject to AMR.

Class 1 components of the RWCU System that are part of the reactor coolant pressure boundary are evaluated in Section 2.3.1.3.

Scoping and Screening Results Page 2.3-146 Amendment 1 L-

Columbia Generating Station Lice-nseRenewal Application Technical: lInformation Table 2.3.3-44 Traversing Incore Probe. System Components Subject to Aging Management Review Intended Function (as defined in Table 2.90-1)

Bolting Pressure Boundary StructUra! Integrity Chamber shield Structural Integrity Piping Pressuroe Boundary Structural Integrity Valve, body Pressure Boundary Structural Integrity gInsert Pages 243A162a64trough 2,3y462-f folloi6,,ng his, page ...

Scoping and Screening kesults Page 2.3-ý162 daripary Mfyý

Columbia Generating Station License Renewal Application Technical Information

.2.3.3.48 Heating Steam System

System Description

The Heating Steam (HS) System originates from four pressure reducing stations (two in the Turbine Generator Building and one each in the Reactor and Radwaste buildings).

Steam at 200 psig pressure is supplied to these pressure reducing stations from either the auxiliary boiler or the gland steam evaporator. At the pressure reducing stations, the steam pressure is reduced to 50 psig and this steam is fed to the heating coils, humidifiers, steam unit heaters, and hotwater heat exchanger.

Reason for Scope Determination The HS System does ýnot perform any safety-related system intended functions that meet the scoping criteria of 10 CFR 54.4(a)(1).

The HS System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The HS System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1). Therefore, the HS System meets the. scoping criteria of 10 CFR 54.4(a)(2).

The HS System is not relied upon to demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events.

FSAR References Section 9.4.16.2 of the FSAR describes the Heating Steam System.

License Renewal Drawings The following license. renewal drawing depicts the evaluation boundaries for the system components within the scope of license renewal:

LR-M514-1 Components assigned by equipment piece number (EPN) to the Radwaste Building Mixed Air (WMA), Radwaste Building Outside Air (WOA), and Radwaste Building Return Air (WRA) systems are included within the evaluation boundaries of the HS System for completeness (see LR-M514-1).

Page 2.3-162a Amendment I Scoping Screening Results and Screening Scoping and Results Page 2.3-162a Amendment 1

Columbia. Generating Station License ReneWal Application Technical Information Components Subject to AMR Table 2.3.3-45 lists the component types that require AMR and their intended functions.

Table 3.3.2-45, Aging Management Review Results - Heating, Steam System, provides the results of the AMR.

Table 2.3.3-45 Heating Steam System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Bolting Structural integrity Heat exchanger (heating coil headers) Structural integrity Heat exchanger (heating coil tubes) Structural integrity Humidifier Structural integrity Piping Structural ihtegrity Strainer (body) Structural integrity Trap body Structural integrity Tubing Structural integrity Valve body Structural integrity Page 2.3-162b Amendment 1 Scopingand Screening Results Scoping and Screening Results Page,2.3-1'62b Amendment 1

Columbia Generating Station License Renewal .Application Technical Information 2.3.3.49 Heating Steam Condensate- System

System Description

The condensate of the Heating Steam Condensate (HCO) System originates from the HS System and is returned to the auxiliary boiler condensate return tank located in .the auxiliary boiler room of the Turbine Generator Buildin4g. Condensate from the Reactor Building, Turbine Generator Building, and ýupper level of the Service Building is returned to the auxiliary condensate return tank by gravity.

In the Radwaste Building and lower level of the Service Building, the condensate returns are below the level of the auxiliary condensate return tank. A condensate pump-set is, therefore, provided in each of these areas to pump the condensate to the return tank.

Reason for Scope Determination The HCO System does notl perform any safety-related system intended functions that meet the scoping criteria of 10 CFR 54.4(a)(1).

The HCO System does not, contain any NSR components that perform a 10 CFR 54.4(a)(!), function. The HCO System does,, however, contain, NSR components that are attached to or located near safety-related SSCs, whose failure.

creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1).

Therefore, the HCO System' meets the scoping criteria of 10 CFR 54.4(a)(2).

The HCO System is not relied upon to demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events.

FSAR References Section 9.4.16.2,of the FSAR describes the Heating Steam Condensate System.

License Renewal Drawings The following license renewal drawing depicts the evaluation boundaries for the system components within the scope of license renewal:.

LR-M514-1 Components SUbiect to AMR Table 2.3.3-46 lists the component types that require AMR and their intended functions.

Table 3.3.2-46, Aging Management Review Results - Heating Steam Condensate System, provides the results of the AMR.

Scoping and Screening Results ,Page 2.3-162c Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 2.3,3-46 Heating Steam Condensate System Components Subject to Aging Management Review Component Type Intended Function Component_______e_(as defined in Table 2.0-1)

Bolting Structural integrity Piping Structural integrity Pump casing Structural integrity Strainer (body) Structural integrity Tank Structural integrity Trap body Structural integrity Tubing Structural integrity Valve body Structural integrity Scoping and Screening Results Page 2.3-16.2,d Amendment 1

Columbia Generating Station License Renewal Application Technical Information 2.3.3.50 Heating Steam Vent System

System Description

The Heating Steam Vent (HSV) System provides a vent through the roof of the respective buildings of-the relief valves and tanks of the HS and HCO systems.

Reason for Scope Determination The HSV System does not perform any safety-related system intended, functions that meet the scoping criteria of 10 CFR 54.4(a)(1).

The HSV System does not contain any NSR components that perform a 10 CFR54.4(a)(1) function. The HSV System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1).

Therefore, the HSV System meets the scoping criteria of 10 CFR 54A(a)(2).

The HSV System is not relied upon to 'demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria -forany regulated events.

FSAR References IFigure 9.4-9.1 of the FSAR describes the Heating Steam Vent System.

License Renewal Drawings The following license renewal drawing depicts the evaluation boundaries for the system components within the scope of license renewal:

LR-M514-1 Components Subiect to AMR Table 2.3.3-47 lists the component types that require AMR and their intended functions.

Table 3,3.2-47, Aging Management Review Results - Heating Steam Vent System, provides the results of the AMR.

Results Page 2.3-162e Amendment 1 Scoping and Scoping Screening Results and Screening Page 2.3-162e Amendment I

Columribia Generating Station License Renewal Application Technical Information Table 2.3.3-47 Heating Steam Vent System Components Subject to Aging Management'Review Component Type Intended Function (as defined in Table 2.0-1)

Bolting Structural integrity Piping Structural integrity Page 2.3-162f Amendment 1 Scoping Screening, Results and Screening Scoping and Resultý Pqge 2.3-162f Amendment 1

Columbia Generating Statibn License Renewal Application Technical Information 2.3.4 Steam and Power Conversion Systems The steam and power conversion systems are those systems used as a heat sink to remove heat from the reactor and convert the heat generated in the reactor to, the electrical output produced by, the plant. The following Columbia systems are addressed in this. section:

" -Auxiliary Steam (AS) System (Section '2.3.4.1)

• Condensate (Auxiliary) (CO) System (Section'2.3.4.2) o Condensate (Nuclear) (COND) System (Section,2.,3.4.3) o Main Steam (MS) System (Section 2.3.4.4) o Main Steam Leakage Control (MSLC) System (Section 2.3.4.5)

• Miscellaneous Drain (MD) System (Section 2.3.4.6) 1n ser.t:

I.Sealing Steam (SS) System o Reactor Feedwater (RFW) System (Section 2.3.4.7) (Section 2348)

A brief system description, reason for scope determination, associated FSAR references, associated license renewal drawings, and components subject to AMR information is provided for each system.

Scoping and Screening Results Page 2.3-163 ~jaA~~y2O-jAmendment 1 t

Columbia Generating Station License Renewal Application Technical Information 2.3.4.2 Condensate (Auxiliary) (CO) System

System Description

The CO System returns condensate from the Auxiliary Steam System, which operates only when the heating steam evaporators are inoperative during plant shutdown, to the Condensate Return Tank, by means of either the Radwaste Building Heating Condensate Pump Set (WHCO-CU-1) or the Condensate Pump Set (SHCO-CU-1).

Reason for Scope Determination The CO System does not perform any safety-related system intended functions that meet the scoping criteria in 10 CFR 54.4(a)(1).

The CO System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The CO System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1). Therefore, the CO System meets the scoping criteria of 10 CFR 54.4(a)(2).

The CO System is not relied upon to demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events.

FSAR References Section 1.2.2.12.16 of the FSAR describes the CO System.

License Renewal Drawings The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

LR-M513, LR-M783 Components Subiect to AMR Table 2.3.4-2 lists the component types that require AMR and their intended functions.

Table 3.4.2-2, Aging Management Review Results - Condensate (Auxiliary) System, provides the results of the AMR.

Scoping and Screening Results Page 2.3-166 - .... e...9.."-

[Amendment 1 I

Columbia Generating Station License Renewal Application Technical Information Table 2.3.4-2 Condensate (Auxiliary) System Components Subject to Aging Management Review Component Type Intended Function Component__Type_(as defined in Table 2.0-1)

Bolting Structural integrity Condenser Structural integrity Piping Structural integrity Pump casing Structural integrity Valve body Structural integrity Insert A from page 2.3-167a 3-1 67 Scoping and Screening Results Page 2.3-167 r-WI Amendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to Table 2.3.4-2:

I Tank Structural integrity Page 2.3-167a Amendment 1 Scoping Screening Results and Screening Scoping and Results Page 2.3-167a Amendment 1

Columbia Generating Station 2.3.4.3 Condensate (Nuclear) (COND) System License Renewal Application Technical Information License Renewal Drawings The following license renewal drawings depict the evaluation boundaries for the system components within the scope of license renewal:

I Iinsert: ", LR-M504-1, LR-M527-2, LR-M532, LR-M504-2, LR-M526-1, LR-M527-1 LR-M534" Components Subject to AMR Table 2.3.4-3 lists the component types that require AMR and their intended functions.

Table 3.4.2-3, Aging Management Review Results - Condensate (Nuclear) System, provides the results of the AMR.

The condenser tubes are not subject to AMR because they do not perform a license renewal intended function of the COND System.

Scoping and Screening Results Page 2.3-169 , ....... ,20*&-

IAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 2.3.4-3 Condensate (Nuclear) System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Pressure boundary Bolting Structural integrity Heat exchanger (shell) Pressure boundary Pressure boundary Orifice Structural integrity Throttling Piping Pressure boundary Structural integrity Pump casing Structural integrity Tank (COND-TK-IA, COND-TK-1B) Pressure boundary Tubing Pressure boundary Structural integrity Valve body Pressure boundary Structural integrity

• l~nsert A from page 2.3-170a Scoping and Screening Results Page 2.3-170 JAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to Table 2.3.4-3:

Flexible connection Structural integrity 2.3-170a Page 2.3-170a Amendment 1 Scoping and Results Screening Results and Screening Page Amendment 1

Columbia Generating Station Ucehse Renewal Application Technical Information The ASME Class I portions of the RFW System are addressed with the reactor coolant pressure boundary in Section.2:3.1.3.

Components Subiect to AMR Table.2.3.4-7 lists the componenttypes that require AMR and their intended functions.

Table 3.4.2-7, Aging Management Review Results - Reactor Feedwater System, provides the results 0f the AMR.

The small-bore lines to flow transmitters RFW-FT-802A and 802B are decoupled from the piping analysis, and are therefore not in scope.

The flow meter section is in scope only for NSAS; therefore, the internals, including the flow stiaighteners and the nozzles are not in scope.

Table 2.3.4-7 Reactor 'Feedwater System Components Subject to Aging ManagementRevieew Com~ponent Type Intended Function

,(as defined In Table2.0-1)

Bolting Structural integrity Flow element Structural integrity Piping Structural integrity Valve body Structural integrity insert'pages 2.3:4 80a :and 2143-180b '

• i..,.i/ f following this page Scoping and Screening Results Page 2.3-180 jAmendment 1

Columbia Generating Station License Renewal Application Technical Information 2.3.4.8 Sealing Steam System

System Description

The Sealing Steam (SS) System consists of two 100%-capacity gland. seal steam evaporators, seal, steam pressure regulators, seal ,steam header, gland seal steam condenser, exhauster blowers, and the associated. piping, valves, and instrumentation.

Sealing steam for turbine shaft seal glands and Valve stem seal glands (stop, control, reheat stop, intercept, and bypass valves) is supplied from the seal steam header at 200 psig. The source of sealing steam. is from the gland seal steam evaporators or the auxiliary steam boiler. The sealing steam is produced in an evaporator which.is heated by extraction steam taken from the high pressure turbine. The condensate fed to the, evaporator is taken .from the suction header of-the reactor feedwater pumps in the feedwater system. During startup and. low load operations, a branch line taken off the main steam header supplies the necessary heating steam for the evaporator.

Separate seal steam regulators are provided to regulate the pressure of sealing steam for the high pressure turbine, each -low pressure turbine, each reactor feed pump turbine shaft seal, the bypass valve assembly, and the main stop and control valve assembly stems.

Since the low pressure (LP) turbine and reactor feedwater pump turbine exhaust pressures are at a vacuum, sufficient sealing steam is supplied to maintain positive pressure in the glands to prevent air inleakage along the shaft. The high pressure (HP) turbine, exhaust pressure varies with load and is approximately 177 psia at its maxi~mun!,

The system is designed to maintain the seal steam supply to the HP turbine glands. at a pressure of 16 to 20 psi above HP turbine exhaust to prevent HP turbine exhaust steam leakage through the shaft gland seal.

The outer leakoff of all glands is routed to the gland seal steam condenser which is maintained at a slight vacuum by the exhauster blower. During plant operation, the gland seal steam condenser and one motor-driven blower is in operation. The exhauster blower discharges gland air inleakage to the atmosphere via the reactor building elevated release duct. The gland seal steam condenser is cooled by the main condensate flow.

The steam evaporator is a shell-and-tube heat exchanger designed to provide- a continuous supply of clean sealing steam to the seal steam header.

Reason for Scone Determination The SS System does not perform any safety-related system intended functions that meet the scoping criteria of 10 CFR 54.4(a)(1).

Screening Results Page 2.3-180a Amendment I Scoping and Screening'Results Scop~ng and Page 2.13-180a Amendment 1

Columbia Generating Station License Renewal Application Technical Information The SS System does not contain any NSR components that perform a 10 CFR 54.4(a)(1) function. The SS System does, however, contain NSR components that are attached to or located near safety-related SSCs, whose failure creates a potential for spatial interaction that could prevent the satisfactory accomplishment of one or more of the functions identified in 10 CFR 54.4(a)(1). Therefore, the SS System meets the scoping criteria of 10 CFR 54.4(a)(2).

The SS System is not relied upon to demonstrate compliance with the 10 CFR 54.4(a)(3) scoping criteria for any regulated events.

FSAR References Section 10.4.3.2 of the FSAR describes the Sealing Steam System.

License Renewal Drawings The following license renewal drawing depicts the evaluation boundaries for the system components within the scope of license renewal:

LR-M502-3 Components Subiect to AMR Table 2.3.4-8 lists the component types that require AMR and their intended functions.

Table 3.4.2-8, Aging Management Review Results - Sealing Steam System, provides the results of the AMR.

Table 2.3.4-8 Sealing Steam System Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

Piping Structural integrity Results Page 2.3-1 BOb Amendment 1 Scoping and Screening Scoping and Screening Results Page 2.3-180b Amendment 1

ColUmbia Generating Station License.Renewal Application Technical Ihformatioih 2.4.4 Circulating Water Pump House -Seismic Category I!

Structure Description The Circulating Water Pump House (aka Circulation Water Pump, House) houses the electric and die'sel driven fire water pumps, and th'ree circulating water pumps. The Circulating Water Pump House :has a reinforced concrete floor, insulated metal wall panels, and a metal roof deck over structural steel 'framing. The Circulatihg Water Pump House and. the chlorination sections of the building :are separated by a masonry wall. The diesel fire pump fuel storage tank room ist isolated by -34W fire rated masonry walls. . .. feplace' 2; hour"t7 The portion of the structure -containing chlorination systems does not contain any equipment within the scope of license, renewal.

Remote- buildings credited in the fire protection- program (Service Water Pump House 1 and 2, Circ.ulating Water Pump House, Water Filfrati6h Building) with non-rated .barriers are sufficiently separated from each other and from the, plant that a single exposure. fire:

Would not spread to more than :one building.

The circulatirhg -water basin is addressed with Yard Structures ;(Section; 2.4.12).

Reason for Scope Determihation Theý Circulating Water Pump House is relied uppoh to demndstrate compliance with the Fire Protection (10 CFR 50.48) regulated event and meets the 10 CFR54.4(a)(3) scoping criteria. The Circulating Water Pump HOuse: provides physical support and protection to the fire water pumps, which are relied upon `to demonstrate compliance with Fire Protection regulated event.

In addition, 'the Circulating Water Pump HouSe is in the, scope of license renewal because it contains:

o Structural components that are relied on during poStulated "fire event.

FSAR References Section 10A.4.5.2 and Appendix F of the FSAR describe the Circulating Water Pump House.

Components Subiect-to. AMR.

Table 2.4-4 lists the component types that require AMR and their.intended functions, The structural commodities for the Circulating Water Pump. H.ouse are addressed in the

,bulk commoditie.s evaluation in Section 2.4.131 Scoping and Sc.reening Results Page 2,4-2.1 jAmendment 1

Columbia Generating Station License Renewal Application Technical Information

• Structural components that are safety-related and are relied upon to remain functional during and following design basis events.

• Structural components that are NSR whose failure could prevent satisfactory accomplishment of safety-related functions.

• Structural components that are relied on during postulated fires, anticipated transients without scram, and station blackout events.

FSAR References Section 3.8.4 of the FSAR describes the Diesel Generator Building.

Components Subiect to AMR Table 2.4-5 lists the component types that require AMR and their intended functions.

The structural commodities for the Diesel Generator Building are addressed in the bulk commodities evaluation in Section 2.4.13.

Table 3.5.2-5, Aging Management Review Results - Diesel Generator Building, provides the results of the AMR.

Table 2.4-5 Diesel Generator Building Components Subject to Aging Management Review Component Type 1

](as Intended Function defined in Table 2.0-1)

Battery Racks SSR Diesel Generator Exhaust Plenums EN, MB, SRE, SSR Diesel Generator Intake Plenums EN, MB, SRE, SSR Diesel Generator Pedestals EXP, EN, SSR Exterior Walls (above grade) EN, MB, SRE, SSR Foundations EN, EXP, SRE, SSR Reinforced Concrete: Walls, Floors, and Ceilings EN, FB, MB, SRE, SSR Roof EN, MB, SRE, SSR Structural Steel: Beams, Columns, Plates, and Trusses EN, SSR (includes welds and bolted connections) EN, ISR

'Add new table row from Insert A shown on page 2.4-24a I Scoping and Screening Results Page 2.4-24 1

IAmendment

Columbia Generating Station License Renewal Application Technical Information Insert A to page 2.4-24 Table 2.4-5 Diesel Generator Building Components Subject to Aging Management Review Component Type Intended Function (as defined in Table 2.0-1)

South Exterior Slab SRE Scoping and Screening Results Page 2r.4-248 Amendment 1

Columbia Generating Station License Renewal Appli6cation TeChnical Information 2.5.3 Elimination of Cqmponent Commodity Groups with no License Renewal Intended Functions No generic electrical and I&C component commodity groups were eliminated from AMR at Columbia, in accordance with the direction of 10 CFR 54.21(a)(1)(i) regarding license renewal intended functions. However, individual components within a component and commodity group may still be eliminated from AMR based on this eFitepie. Replce,:"criterion" 2.5.4 Application of Screening Criteria 10 CFR 54.21(a)(1 )(ii) to Electrical and I&C Component Commodity Groups The next step in the electrical screening process is to segregate the "long-lived" electrical components from those that are subject to replacement based on a qualified life or a specified time schedule. In general, components that are screened out of license renewal consideration based on the "long-lived" criterion are those included in the plant environmental qualification (EQ) program. Electrical components included in the Plant EQ program have qualified lives and are replaced based on their qualified life determination. Therefore, environmentally qualified components do not meet the "long-lived" -criterion of 10 CFR 54;21(a)(1)(ii) and are excluded from further evaluation.

EQ evaluations that: meet the criteria for a time-limited aging analysis. are.addressed in Section 4.4.

2.5.4.1 Electrical Portions of Electrical and I&C Penetration Assemblies The electrical penetration assembly commodity group is excluded from AMR because all of the Columbia electrical penetrations are part of the EQ program. The electrical penetration assemblies are addressed by various EQ analyses. Therefore, the electrical penetration assemblies are not subject to AMR at Columbia, because they do not meet the long,lived criterion of 10 CFR 54.21 (a)(1)(ii).

2.5.4.2 Insulated Cables and Connections in the EQ Program The insulated cables and connections that are included in the plant EQ program have qualified lives and are replaced based on their qualified life determination. Therefore, insulated cables and connections that are included in the EQ program do not meet the "long-livedn criterion of 10 CFR 54.21(a)(1)(ii) and are not subject to AMR.

2.5.5 Electrical and 1&C Component Commodity Groups Requiring an Aging Management Review The electrical and I&C component commodity groups that require AMR are listed in Table 2.5-1,:along with their intended functions. Intended functions are defined in Table 2.0-1.

Table 3.6.,2-1, Aging Management Review Results - Electrical and I&C Components, provides the results of the AMR.

Scoping and Screenihg Results Page 2.5-3 d...... 04. G Amendment 1

Columbia Generating Station LicenseRenewal Applicatioh Technical Information The function of high-voltage insulatobrs is to insulate and .support an electrical Conductor.

High voltage insulators are passive,, long-lived components. Therefore, high' voltage insulators meet the criteria of 10 CFR 54..21(a)(1),and are:subjectto an AMR.

2.5.6 Evaluation Boundaries 2..5.61 System Evaluation Boundaries The evaluation boundaries: forthe electrical and I&C systems within the scope of license renewal include the entire, ;system. Electrical and I&C component types within the, boundaries of in-scope mechanicalsystems are also."included within the: electrical and l&C .evaluation boundaries.

2.5.6.2 Station Blackout Evaluation Boundaries The License Renewal Rule, 10. CFR 54.4(a)(3), requires that plant SSCs relied on "for.

compliance with the NRC regulation on station blackout (SBO), 10 CFR 505631. be included in 'the scope of license renewal., In, April 2002, the NRC- issued additional.

guidance on the (license reneWal), scoping of equipment relied, on to Meet the requirements of 10.CFR:50.63 in the form of an Interim'Staff Guidance document (ISG-02). Subse-uently, thisguidance was incorporated into NUREG-1801, Revision 1.

I nsert;: ",which is now anb historical reference" Using the requirements of the License, Renewal Rule,, the guidance provided, in NUREG-1800, the insights of ISG-02, and the current licensing basis documentation, the SBO license renewal scoping boundary Was established and the in-scope SSCS for-SBQ were identified. The following paragraphs describe the SBO license. renewal off-site power recovery paths forColumbia.

Two independent offsite power sources are supplied to Columbia via start-up transformer E-TR-S and back-uP transformer E-TR-B.

The -230*kV grid -is connected to the, onsite power system by breaker. E-CB-TRS (also known as A809) at the' Ashe substation then via overhead line to transformer E-TR-S located in the Columbia transformer yard. The distribution from the start-up transformer (E-TR-S) to the Class 1 E buses is through the hnon-segregated bus to switchgear SM-i and SM,3. Each of these NSR Switchgear feed to the Class 1 E switchgear for Division 1 and Division 2 (SM-7 and SM-8, respectively).

The 115-kV grid is. connected to the onsite power source by oil circuit breaker E-CB-TRB located in the Columbia transformer yard. The output of, breaker E-CB-TRB is directly tied by switchyard bus to- back-up transformer E-TR-B, which is then directly connected by cable (routed underground and then in tray) to the Class 1 E switchgear

.for Division 1 and Division 2 (SM-7 and SM-8 respectively).

Scoping and Screering Results Page'2.5-*8-jAmendment 1

3.3 Aging Management of Auxiliary Systems Columbia Generating Station License Renewal Application Technical Information

• Fire Protection System (Section 2.3.3.22)

• Floor Drain System (Section 2.3.3.23)

• Floor Drain Radioactive System (Section 2.3.3.24)

• Fuel Pool Cooling System (Section 2.3.3.25)

• Miscellaneous Waste Radioactive System (Section 2.3.3.27)

• Plant Sanitary Drains System (Section 2.3.3.28)

• Plant Service Water System (Section 2.3.3.29)

• Potable Cold Water System (Section 2.3.3.30)

• Potable Hot Water System (Section 2.3.3.31)

• Primary Containment System (Section 2.3.3.32)

• Process Sampling System (Section 2.3.3.33)

• Process Sampling Radioactive System (Section 2.3.3.34)

• Pump House HVAC Systems (Section 2.3.3.35)

• Radwaste Building Chilled Water System (Section 2.3.3.36)

• Radwaste Building HVAC Systems (Section 2.3.3.37)

• Reactor Building HVAC Systems (Section 2.3.3.38)

• Reactor Closed Cooling Water System (Section 2.3.3.39)

• Reactor Water Cleanup System (Section 2.3.3.41)

• Service Air System (Section 2.3.3.42)

• Standby Liquid Control System (Section 2.3.3.43)

• Standby Service Water System (Section 2.3.3.44)

IAdd Insert A from

• Tower Makeup Water System (Section 2.3.3.46) page 3.3-2a 2.3.3.47) 3

• Traversing Incore Probe System (Section Table 3.3.1, Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801, provides the summary of the programs evaluated in NUREG-1801 that are applicable to component and commodity groups in this section.

Text addressing summary items requiring further evaluation is provided in Section 3.3.2.2.

Aging Management Review Results Page 3.3-2 j.Au.. 2*190 Amendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.3.1

• Heating Steam System (Section 2.3.3.48)

" Heating Steam Condensate System (Section 2.3.3.49)

" Heating Steam Vent System (Section 2.3.3.50)

Results Page 3.3-2a Amendment 1 Management Review Aging Management Aging Review Results Page 3.3-2a Amendment 1

Columbia Generating Station 3.3.2 Results License Renewal Application Technical Information Table 3.3.2-39 Aging Management Review Results - Reactor Water Cleanup System Table 3.3.2-40 Aging Management Review Results - Service Air System Table 3.3.2-41 Aging Management Review Results - Standby Liquid Control System Table 3.3.2-42 Aging Management Review Results - Standby Service Water System Table 3.3.2-43 Aging Management Review Results - Tower Makeup Water System Table 3.3.2-44 Aging Management Review Results - Traversing Incore Probe System

< IAdd Insert A from page _3.3-ý5a 3.3.2.1 Materials, Environments, Aging Effects Requiring Management, and Aging Management Programs The materials from which specific components and commodities are fabricated, the environments to which they are exposed, the aging effects requiring management, and the aging management programs used to manage these aging effects are provided for each of the above systems in the following sections.

3.3.2.1.1 Circulating Water System Materials The materials of construction for subject mechanical components of the Circulating Water System are:

• Concrete

• Gray cast iron

• Stainless steel

• Steel Environments Subject mechanical components of the Circulating Water System are exposed to the following normal operating environments:

• Air-outdoor

• Raw water

• Soil Aging Management Review Results Page 3.3-5 Jdi iuiy 2010

[Amendment1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.3.2 Table 3.3.2-45 Aging Management Review Results - Heating Steam System Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate System Table 3.3.2-47 Aging Management Review Results - Heating Steam Vent System Page 3.3-5a Amendment 1 Aging Review Results Management Review Aging Management Results Page 3.3-5a Amendment 1

Columbia Generating Station 3.3.2.1.1 Circulating Water System License Renewal Application Technical Information Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Circulating Water System:

" Loss of material *'.Add: "Cracking"

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Circulating Water System:

" Bolting Integrity Program

• Buried Piping and Tanks Inspection Program

" External Surfaces Monitoring Program

" Open-Cycle Cooling Water Program

• Selective Leaching Inspection 3.3.2.1.2 Condensate Processing Radioactive (Demineralizer) System Materials The material of construction for subject mechanical components of the Condensate Processing Radioactive (Demineralizer) System is:

• Steel Environments Subject mechanical components of the Condensate Processing Radioactive (Demineralizer) System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

" Treated water Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Condensate Processing Radioactive (Demineralizer) System:

• Loss of material

• Loss of pre-load Jama~ 2010 Aging Management Review Results Management Review Results Page 3.3-6 Page 3.3-6 jam tary-26+0-JAmendment

Columbia Generating Station License Renewal Application Technical Information

" Loss of pre-load

• Reduction of heat transfer Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Diesel Lubricating Oil System:

• Bolting Integrity Program

• Chemistry Program Effectiveness Inspection

• Closed Cooling Water Chemistry Program

• External Surfaces Monitoring Program

• Heat Exchangers Inspection

• Lubricating Oil Analysis Program

• Lubricating Oil Inspection 3.3.2.1.21 Equipment Drains Radioactive System Materials The materials of construction for subject mechanical components of the Equipment Drains Radioactive System are:

" Glass

• Stainless steel

" Steel Environments Subject mechanical components of the Equipment Drains Radioactive System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

• Closed cycle cooling water

" Concrete Add "Moist Air" as a new bullet in the

• Raw water list of environment

• Treated water Aging Management Review Results Page 3.3-25 JaRi4a.y 210--

Amendment 1_

Columbia Generating Station License Renewal Application Technical Information 3.3.2.1.24 Floor Drain Radioactive System Materials The materials of construction for subject mechanical components of the Floor Drain Radioactive System are:

• Stainless steel

• Steel Environments Subject mechanical components of the Floor Drain Radioactive System are exposed to the following normal operating environments:

• Air-indoor uncontrolled Add "Moist air" as

• Concrete 4--1*new bullet in the

• Raw water list of environments

• Treated water Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Floor Drain Radioactive System:

• Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Floor Drain Radioactive System:

• Bolting Integrity Program

• BWR Water Chemistry Program

• Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program

• Monitoring and Collection Systems Inspection

• Supplemental Piping/Tank Inspection JAmendment 1 Aging Management Review Results Page 3.3-29 A jai miemiy 2616

Columbia Generating Station License Renewal Application Technical Information Environments Subject mechanical components of the Potable Cold Water System are exposed to the following normal operating environments:

• Condensation

• Raw water Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Potable Cold Water System:

• Cracking

• Loss of material Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Potable Cold Water System:

• External Surfaces Monitoring Program

• Potable Water Monitoring Program

• Selective Leaching Inspection 3.3.2.1.30 Potable Hot Water System Materials The materials of construction for subject mechanical components of the Potable Hot Water System are:

• Copper alloy

• Copper alloy > 15% Zn Environments Subject mechanical components of the Potable Hot Water System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

• Raw water Aging Management Review Results Page 3.3-34

]Amendment 1

Columbia Generating Station License Renewal Application Technical Information 3.3.2.1.32 Process Sampling System Materials The materials of construction for subject mechanical components of the Process Sampling System are:

• Copper alloy

• Copper alloy > 15% Zn

• Polymer

• Stainless steel

• Steel Environments Subject mechanical components of the Process Sampling System are exposed to the following normal operating environments:

• Condensation

• Raw water Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Process Sampling System:

• Cracking

• Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Process Sampling System:

• Bolting Integrity Program

• External Surfaces Monitoring Program Add:

• Open-Cycle Cooling Water Program "Monitoring and Collection Systems

• Selective Leaching Inspection Inspection" Aging Management Review Results Page 3.3-36 January 2U1U JAmendment 1

Columbia Generating Station 3.3.2 Results License Renewal Application Technical Information E n u sg,,Add new sections 3.3.2.1.45 through 47 External Surfaces Monitoring Progra las shown on pages 3.3-50a through d 3.3.2.2 Further Evaluation of Aging Management as Recommended by NUREG-1801 For the Auxiliary Systems, those items requiring further evaluation are addressed in the following sections.

3.3.2.2.1 Cumulative Fatigue Damage Fatigue is a time-limited aging analysis, as defined in 10 CFR 54.3. Time-limited aging analyses are required to be evaluated in accordance with 10 CFR 54.21(c). Time-limited aging analyses identified for fatigue in the Auxiliary Systems are evaluated in Section 4.3.4.

3.3.2.2,2 Reduction of Heat Transfer due to Fouling As described in Table 3.3.1, the Fuel Pool Cooling System has stainless steel heat exchanger tubes in treated water which are evaluated under item number 3.3.1-03.

Fouling of stainless steel heat exchanger tubes in treated water is managed by the BWR Water Chemistry Program, in conjunction with the Heat Exchangers Inspection.

3.3.2.2,3 Cracking due to Stress Corrosion Cracking (SCC) 3.3.2.2,3.1 BWR Standby Liquid Control System The treated water environment for the Standby Liquid Control System uses an aqueous solution of sodium pentaborate decahydrate. The system is normally in standby with the fluid temperature maintained above the 601F saturation temperature in an area where the ambient temperature is less than 1001F during normal plant operation. Since the temperature is below 1401F during normal plant operation, cracking due to SCC is not an aging effect requiring management for the stainless steel components of the Standby Liquid Control System.

3.3.2.2,3.2 Heat Exchanger Components As described in Table 3.3.1, there are no components compared to item number 3.3.1-

05. The Reactor Water Cleanup regenerative and non-regenerative heat exchangers at Columbia have no stainless steel components subject to AMR. Therefore, cracking of these components due to stress corrosion cracking is not an aging effect requiring management. Refer to item 3.3.1-48 (no further evaluation required) for the aging effects that do require management for these components.

3.3.2.2.3.3 Diesel Engine Exhaust Piping, Piping Components, and Piping Elements During normal plant operations, diesel exhaust piping, piping components, and piping elements are exposed to diesel exhaust infrequently and for short durations. For the remaining time, these components are exposed internally to outdoor air. As such, temperatures above 140OF occur only infrequently and for short durations. Therefore, cracking due to SCC is not identified as an aging effect requiring management for Aging Management Review Results Page 3.3-50 Jan-ua, 2010 JAmendment 1

Columbia Generating Station License Renewal Application Technical Information 3.3.2.1.45 Heating Steam System Materials The materials of construction for subject mechanical components of the Heating Steam System are:

• Copper alloy

• Gray cast iron

• Stainless steel

• Steel Environments Subject mechanical components of the Heating Steam System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

" Steam Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Heating Steam System:

• Cracking

• Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Heating Steam System:

• Bolting Integrity Program

• BWR Water Chemistry Program

• Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program Aging Management Review Results Page 3.3-50a Amendment 1

Columbia Generating Station License Renewal Application Technical Information

• Flow-Accelerated Corrosion (FAC) Program

• Selective Leaching Inspection 3.3.2.1.46 Heating Steam Condensate System Materials The materials of construction for subject mechanical components of the Heating Steam Condensate System are:

• Copper alloy

• Gray cast iron

• Steel Environments Subject mechanical components of the Heating Steam Condensate System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

• Moist Air

• Steam

• Treated water > 60 'C (140 'F)

Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Heating Steam Condensate System:

• Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Heating Steam Condensate System:

• Bolting Integrity Program Aging Management Review Results Page 3.3-50b Amendment 1

Columbia Generating Station License Renewal Application Technical Information

• BWR Water Chemistry Program

• Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program

• Flow-Accelerated Corrosion (FAC) Program

• Selective Leaching Inspection

• Supplemental Piping/Tanks Inspection 3.3.2.1.47 Heating Steam Vent System Materials The materials of construction for subject mechanical components of the Heating Steam Vent System are:

0 Steel Environments Subject mechanical components of the Heating Steam Vent System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

• Steam Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Heating Steam Vent System:

• Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Heating Steam Vent System:

• Bolting Integrity Program

• BWR Water Chemistry Program Aging Management Review Results Page 3.3-50c Amendment 1

Columbia Generating Station License Renewal Application Technical Information Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program

• Flow-Accelerated Corrosion (FAC) Program Page 3.3-50d Amendment 1 Aging Review Results Management Review Aging Management Results Page 3.3-50d Amendment 1

Columbia Generating Station License Renewal Application Technical Information an aggressive environment. Therefore, loss of material due to pitting and crevice corrosion is not an aging effect requiring management for these components.

3.3.2.2.10.7 Stainless Steel Piping, Piping Components, and Piping Elements - Soil As described in Table 3.3.1, there are no cornponents comparer3d to item number 3. 1-2-. The-re is no sta-inless; steel piping subject to ANR for Columbia that is exposed to soi in..theAuxiliar. systems. epace with Insert A on page 3.3-55a 3.3.2.2.10.8 BWR Standby Liquid Control System Loss of material due to pitting and crevice corrosion for stainless steel piping components and tanks exposed to sodium pentaborate solution is managed by the BWR Water Chemistry Program. The BWR Water Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Replace Program Effectiveness Inspection will provide a verification of the effectiveness of the with Insert WR Water Chemistry Program to manage loss of material due to pitting and crevice B from corrosion through examination of stainless steel piping components and tanks exposed page to sodium pentaborate solution.

3.3-55a

.3.2.2.11 Loss of Material due to Pitting, Crevice, and Galvanic Corrosion

.As cdescrribed in Table 3.3.1, there were no cto'mponents cernmpared to iterm numb-r 2.13-t- There are no copper alloy piping piinomponents, or piping elements in the Auxiliary systems that are exposed to treated wter.

3.3.2.2.12 Loss of Material due to Pitting, Crevice, and Microbiologically Influenced Corrosion 3.3.2.2.12.1 Piping, Piping Components, and Piping Elements- Fuel Oil There are no aluminum piping components exposed to fuel oil that are subject to AMR.

Loss of material due to pitting and crevice corrosion and MIC for stainless steel and copper alloy piping components exposed to fuel oil is managed by the Fuel Oil Chemistry Program. The Fuel Oil Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Program Effectiveness Inspection will provide a verification of the effectiveness of the Fuel Oil Chemistry Program to manage loss of material through examination of piping and components exposed to fuel oil.

3.3.2.2.12.2 Piping, Piping Components, and Piping Elements - Lubricating Oil Loss of material due to pitting and crevice corrosion and MIC for stainless steel piping components and heat exchanger components exposed to lubricating oil is managed by the Lubricating Oil Analysis Program. The Lubricating Oil Analysis Program manages aging effects through periodic monitoring and control of contaminants, including water.

The Lubricating Oil Inspection will provide a verification of the effectiveness of the Aging Management Review Results Page 3.3-55 januar.-y-n 2

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.3.2.2.10.7 The Buried Piping Thanks Inspection Program, with enhancement, manages loss of material due to pitting and crevice corrosion and microbiologically influenced corrosion (MIC) for stainless steel piping and piping components buried in soil.

Insert B to LRA Section 3.3.2.2.11 Loss of material due to pitting, crevice, and galvanic corrosion for copper alloy piping, piping components, or piping elements exposed to treated water is managed by the BWR Water Chemistry Program. The BWR Water Chemistry Program manages aging effects through periodic monitoring and control of contaminants. The Chemistry Program Effectiveness Inspection will provide a verification of the effectiveness of the BWR Water Chemistry Program to manage loss of material due to pitting, crevice, and galvanic corrosion through examination of copper alloy piping and piping components exposed to treated water.

Aging Management Review Results Page 3.3-55a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801 Further Discussion Item Aging Aging Management Evaluation Number Component/Commodity Effect/Mechanism Programs Recommended 3.3.1-28 Copper alloy fire protection Loss of material A plant-specific aging Yes, plant Not applicable.

piping, piping components, and due to pitting and management program specific piping elements exposed to crevice corrosion is to be evaluated. There are no copper alloy fire condensation (internal) protection piping, piping components, or piping elements in the auxiliary systems that are exposed to condensation (internal).

Refer to Section 3.3.2.2.10.6 for further information.

3.3.1-29 Stainless steel piping, piping Loss of material A plant-specific aging Yes, plant Nut app'tcabte components, and piping due to pitting and management program specific elements exposed to soil crevice corrosion is to be evaluated. Thei a, e no stailes steel piping., piping eempenent&,-er piping elefmcnts in the auxiliar sstetms that arc expesed t 31 Refer to Section 3.3.2.2.10.7 for further information.

FReplace with Insert A on page 3.3-75a Aging Management Review Results Page 3.3-75 Jdanuary 20-0 jAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Table 3.3.1 Item 3.3.1-29 The Buried Piping and Tanks Inspection Program, with enhancement, is credited to manage loss of material for stainless steel piping, piping components and piping elements (with or without coating or wrapping) in the auxiliary systems that are exposed to soil.

Aging Management Review Results 3.3-75a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801 Further Aging Aging Management Evaluation Discussion Item Number Component/Commodity Effect/Mechanism Programs Recommended 3.3.1-31 Copper alloy piping, piping Loss of material Water Chemistry and Yes, detection of N-applcabe.

components, and piping due to pitting, One-Time Inspection aging effects is elements exposed to treated crevice, and to be evaluated -here aieu nupper aiioy piping, water galvanic corrosion *pn...p'ipg c.mponont.., or piping I le11o11nts in the auxLl;im systesinltS Replace discussion ...mt...e......d to treated with Insert A from water-page 3.3-77a Refer t8Seetien 3.3.2.2.11 f8r further infeorrnaticn.

3.3.1-32 Stainless steel, aluminum and Loss of material Fuel Oil Chemistry and Yes, detection of Consistent with NUREG-1801, copper alloy piping, piping due to pitting, One-Time Inspection aging effects is with exceptions.

components, and piping crevice, and to be evaluated elements exposed to fuel oil microbiologically The Fuel Oil Chemistry Program, influenced in conjunction with the Chemistry corrosion Program Effectiveness Inspection, is credited to manage loss of material for stainless steel and copper alloy piping and piping components in the auxiliary systems that are exposed to fuel oil. There are no aluminum piping, piping components, or piping elements in the auxiliary systems that are exposed to fuel oil.

Refer to Section 3.3.2.2.12.1 for further information.

Aging Management Review Results Page 3.3-77 Janmen 201

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Table 3.3.1 Item 3.3.1-31 Consistent with NUREG-1801.

The BWR Water Chemistry Program, in conjunction with the Chemistry Program Effectiveness Inspection, is credited to manage loss of material for copper alloy piping and piping components in the auxiliary systems that are exposed to treated water.

Refer to Section 3.3.2.2.11 for further information.

Amendment 1 Aging Management Review Aging Management Results Review Results Page 3.3-77a Page 3.3-77a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Summary of Aging Management Programs for Auxiliary Systems Ie Table 3.3.1 Evaluated in Chapter VII of NUREG-1 801 Agn urther Item Aging Aging Management Evaluation Discussion Number Component/Commodity Effect/Mechanism Programs EuRecommended 3.3.1-71 Steel piping, piping Loss of material Inspection of Internal No The following programs are components, and piping due to general, Surfaces in credited to manage loss of elements exposed to moist air pitting, and crevice Miscellaneous Piping material for steel piping, piping or condensation (Internal) corrosion and Ducting components, and tanks in the Components auxiliary systems that are exposed to moist air or condensation (internal):

" Cooling Units Inspection for drain piping in HVAC systems exposed to condensation (internal)

• Monitoring and Collection Systems Inspection for air-water interfaces in Plant Sanitary Drain System piping evaluated as exposed to moist air (internal)

Replace deleted

• stipplermental Ripingi48on lnspcctkcn f-r a; -Výdte, text with Insert A intlzrftcc in piping and tmnik from page 33-101a evaltiatpr! as expad to~ makt IA Note E is applied in each case.

Aging Management Review Results Page 3.3-101

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Table 3.3.1 Item 3.3.1-71

• Supplemental Piping/Tank Inspection for air-water interfaces in piping, piping components, and tanks evaluated as exposed to moist air (internal)

Amendment 1 Aging Management Aging Review Results Management Review Results Page 3.3-lOla Page 3.3-101 a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801 Aging Aging Management EaFurther Item E Component/Commodity Effect/Mechanism Programs Recommended Number Recmmede 3.3.1-76 Steel piping, piping Loss of material Open-Cycle Cooling No Consistent with NUREG-1801, components, and piping due to general, Water System with exceptions.

elements (without lining/coating pitting, crevice, and or with degraded lining/coating) microbiologically Except as noted below, the exposed to raw water influenced Open-Cycle Cooling Water corrosion, fouling, Program is credited to manage and lining/coating loss of material for steel piping, degradation piping components, and piping elements that are exposed to raw water.

For steel piping and piping components in the other auxiliary systems that are exposed to raw water, the following programs are credited to manage loss of material:

" Diesel Starting Air Inspection for drain piping in Diesel Starting Air System

" Diesel Systems Inspection for drain piping in the Diesel (Engine) Exhaust System

" Monitoring and Collection Systems Inspection for dwi9-pi*i* in Equipment Drains Replace deleted Radioactive, Floor Drain, and text with: "drain Floor Drain Radioactive piping and tanks" systems

_______ .1____________________________ .1. _________________ .1.

Aging Management Review Results Page 3.3-104 j ~end ZInt

Columbia Generating Station License Renewal Application Technical Information Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801 T I Aging Management Further EuatoD s Item Aging Effect/Mechanism Programs Evaluation Discussion Number Component/Commodity Recommended 3.3.1-85 Gray cast iron piping, piping Loss of material Selective Leaching of No Consistent with NUREG-1801.

components, and piping due to selective Materials elements exposed to soil, raw leaching The Selective Leaching water, treated water or closed- Inspection is credited to detect cycle cooling water and characterize loss of material due to selective leachingfor gray cast iron piping, piping components, and piping elements in the auxiliary systems exposed to soil, raw water, d closed-cycle cooling water. Insert:

"treated This item is also applied to gray water" cast iron heat exchanger components that are exposed to raw water and closed cycle cooling water, and to gray cast iron tank components exposed to raw water. A Note C is applied.

3.3.1-86 Structural steel (new fuel Loss of material Structures Monitoring No Not applicable.

storage rack assembly) due to general, Program exposed to air - indoor pitting, and crevice There is no structural steel (new uncontrolled (external) corrosion fuel storage rack assembly) exposed to air-indoor uncontrolled (external).

3.3.1-87 PWR Only 3.3.1-88 PWR Only 3.3.1-89 PWR Only Aging Management Review Results Page 3.3-113 Aameldmy 261 j~ende ___1y I

Columbia Generating Station License Renewal Application Technical Information Table 3.3.1 Summary of Aging Management Programs for Auxiliary Systems Evaluated in Chapter VII of NUREG-1801 I I Aging Management Further Evaluation Discussion Item Aging Number Component/Commodity Effect/Mechanism Programs Recommended 3.3.1-94 Stainless steel and nickel alloy None None NA - No AEM or Consistent with NUREG-1 801.

piping, piping components, and AMP piping elements exposed to No aging effects requiring air - indoor uncontrolled management are identified for (external) stainless steel piping, piping Insert: components, and piping elements in the auxiliary systems "heat that are exposed to air-indoor exchanger uncontrolled (external).

components," This item is also applied to stainless steel accumulators, bolting, drain pans, duct,

screens, and tanks that are exposed to air-indoor uncontrolled (external). A Note C is applied.

3.3.1-95 Steel and aluminum piping, None None NA - No AEM or Not applicable.

piping components, and piping AMP elements exposed to air - There are no steel or aluminum indoor controlled (external) piping, piping components, or piping elements in the auxiliary systems that are exposed to air-indoor controlled (external). All air-indoor environments were conservatively evaluated as uncontrolled environments.

Aging Management Review Results Page 3.3-115

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-1 Aging Management Review Results - Circulating Water System Aging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801 Table I Notes No. Type Function(s) Management Program Volume Item 2 Item Pressure Steel-(Eteornl 1 Bolting Pressure Steel Air-otdornl Loss of material Bolting Integrity VII.I-1 3.3.1-43 B 1 Bligboundary (xenl 2 Bolting2 Pressure boundary Steel Air-outdoor Loss of Bolting Integrity N/A N/A H (External) pre-load Pressure Raw water 3 Piping boundary Concrete (Internal) None None N/A N/A G 4 Piping Pressure Concrete Soiltnal) None None I1.B1.2-1 3.5.1-2 0301 5 Piping boesundre (ExlRawternl boPressure S Raw water Loss of material Open-Cycle Cooling VII.C1-19 3.3.1-76 B Pipngboundary tei(Internal) Water Pressure Air-outdoor . External Surfaces 6 Piping boure Steel (Exter Loss of material Externg VII.I-9 3.3.1-58 A boundary (External) Monitoring 7 Pipin Pressure Steel Soil Loss of material Buried Piping and VII.Ce-18 3.3.1-19 A P boundary (External) Tanks Inspection F Pressure Stainless Raw water L I Ogen-Cycle Coolingq e .

8 ,uptur D boundary Steel (Internal) Water 91 R'-ture Dic, Pressure Stainle. . Loss of material Open-Cycle Cooling I VII CI-15 3.3-79 I

bounaary Wtee, kt-xternai) vvater a-7 - -.------.--- , - ______________________________

- _____________________________ ______________________________________________

___________________________________ ______________________

______________________

9 Delete rows 8 and Aging Management Review Results Page 3.3-118 January 2u01 IAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-1 Aging Management Review Results - Circulating Water System 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 10 Valve Bd Pressure Gray Cast Raw water Loss of material Open-Cycle Cooling VII.C1-19 3.3.1-76 B 1Y boundary Iron (Internal) Water 11 Valve Body Pressure Gray Cast Raw water Loss of material Selective Leaching VII.C1-11 3.3.1-85 A boundary Iron (Internal) Inspection 12 Valve Body Pressure Gray Cast Air-outdoor Loss of material External Surfaces VII.I-9 3.3.1-58 A boundary Iron (External) Monitoring 13 Valve Body Pressure Steel Raw water Loss of material Open-Cycle Cooling VII.C1-19 3.3.1-76 B boundary (Internal) Water 14 Valve Body Pressure Steel Air-outdoor Loss of material External Surfaces VII.l-9 3.3.1-58 A boundary (External) Monitoring Insert new rows 15 through 21 for Table 3.3.2-1 as shown on page 3.3-119a Aging Management Review Results Page 3.3-119 Aai uary 20i0 IAmendment 1 _J_,,-

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-1 Aging Management Review Results - Circulating Water System Row Co nt Intended Aging Effect Aging NUREG-Row Componen Intende Material Environment Requiring Management 1801 Table Notes NS. Management Program 2 Item Pressure Soil Buried Piping 15 Bolting boundary Steel (External) Cracking and Tanks N/A N/A G Inspection Pressure Soil Buried Piping 16 Bolting boundary Steel (External) Loss of material and Tanks N/A N/A G Inspection 17 Bolting Steel eSoil Loss ofundary of pre- Buried Piping and Tanks N/A N/A G 17 Boltingboundary (ExeInspection Pressure Stainless Soil Buried Piping 18 Bolting boundary Steel (External) Cracking and Tanks N/A N/A F Inspection Pressure Stainless Soil Buried Piping 19 Bolting boundary Steel (External) Loss of material and Tanks N/A N/A F Inspection '

Buried Piping F Pressure Stainless Soil Loss of pre- and Tanks N/A N/A 20 Bolting boundary Steel (External) load Inspection Inspection Pressure Soil Buried Piping VI1.C1-18 3.3.1- A 21 Valve body boundary Steel (External) Loss of material and Tanks Inspection 19 3.3-119a Amendment 1 Aging Management Aging Results Review Results Management Review 3.3-119a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-14 Aging Management Review Results - Diesel Building HVAC Systems TAging Effect Aging NUREG-Row Component Intended Material Environment Requiring Management 1801 Table 1 Notes No. Type Function(s) Malagenent Manam Volume Item Management Program 2 Item Fan Housing Air-indoor External (DEA-FN-1 1, Pressure Steel uncontrolled Loss of Surfaces VII.l-8 3.3.1-58 C 18 12, 21, 22, 31, boundary (Internal) material Monitoring0302 32 & 52) Monitoring Fan Housing Air-indoor External 19 (DEA-FN-11, Pressure Steel uncontrolled Loss of Surfaces VII.I-8 3.3.1-58 A 12, 32 &21,52)22, 31, boundary (External) materialMonitoring Flexible Pressure Air-indoor Hardening and External boundary Elastomer uncontrolled loss of Surfaces VII.4-6 3.3.1-11 E Connection (Internal) strength Monitoring Flexible Pressure Air-indoor Hardening and External 21 Connection boundary Elastomer uncontrolled loss of Surfaces VII.F4-6 3.3.1-11 E (External) strength Monitoring Heat Exchanger Pressure Steel Raw water Loss of Open-Cycle VII.C1-5 3.3.1-77 B CC-11, 12, 21, boundary (Internal) material Cooling Water 22, 31 & 32)

Heat Exchanger Pressure Condensation Loss of External 23 (header) (DMA- Steel Surfaces VII.I-11 3.3.1-58 A CC-1boundary (External) material Monitoring 22, 31 & 32)

Heat Exchanger Al -

Condensation OQn 2 (tins) (DMA- Heat transter Auminu (External) racking N/A H CC-11, 12, 21, 22, 31 & 32) 1 1 1 1 1 1 1 Delete row 24 Aging Management Review Results Page 3.3-180 enmuany 2010 jAmendment 1 -

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-14 Aging Management Review Results- Diesel Building HVAC Systems TAging Effect Aging NUREG-Row Component Intended Material Environment i agn 1801 Table I Notes No. Type Function(s) Requiring Management Volume 2 Item Item Management Program Heat Add:

Exchanger Condensation Loss of Open-Cycle VIIF2-25 (fins) (DMA- Heat transfer Aluminum (External) material Cooling Water 12 3.3.1-27 E 0325 CC-11, 12, 21, 22, 31 & 32)

Heat Exchanger Condensation Reduction in Open-Cycle 26 (fins) (DMA- Heat transfer Aluminum (External) heat transfer Cooling Water N/A N/A H CC-11, 12, 21, 22, 31 & 32)

Heat Exchanger Rawwater Reduction in Open-Cycle VI1.C1-6 3.3.1-83 27 (tubes) (DMA- Heat transfer Copper Alloy (Internal) heat transfer Cooling Water CC-11, 12, 21, (

22, 31 & 32)

Heat Exchanger C 28 (tubes) (DMA- Heat transfer Copper Alloy Condensation Reduction in Open-Cycle N/A N/A H CC-11, 12, 21, (External) heat transfer Cooling Water 22, 31 & 32)

Heat Exchanger Pressure Raw water Loss of Open-Cycle VII.C1-3 3.3.1-82 29 (tubes) (DMA- boury Copper Alloy (Internal) material Cooling Water CC-11, 12, 21, boundary 22, 31 & 32)

Heat Exchanger Pressure Condensation Loss of Open-Cycle VII.F2-30 (tubes) (DMA- Copper Alloy (External) material Cooling Water 14 3.3.1-25 E CC-11, 12, 21, boundary 22, 31 & 32) 1 1 1 1 1 1 1 Aging Management Review Results Page 3.3-181 January 2010 jAmendment 1

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

73 Component Ro opoet Tbn Type Intended Inedd Function(s)

Material Environment Aging Effect Reurn equiring Management Aging Mage Managemen Program nt NUREG-1801 Volume 2 Item Table 1 Item I Notes Pressure Stainless Fuel oil Loss of Fuel Oil VII.H1-6 3.3.1- B ITuing boundary Steel (Internal) material Chemistry 32 74 Tubing Pressure Stainless Air-indoor3.3.1-uncontrolled None None VII.J-15 3. A gboundary Steel (External)

Chemistry 75 Valve dy Pressure Steel Fuel oil Loss of Program VII.H1- 3.3.1- A lveBoy boundary (Internal) material Effectiveness 10 20 Inspection 76 Valve Body Pressure Steel Fuel oil Loss of Fuel Oil VII.H1- 3.3.1- B boundary (Internal) material Chemistry 10 20 Pressure Air-indoor Loss of External 3.3.1-77 Valve Body boundary Steel uncontrolled Surfaces VII.1-8 A (External) material Monitoring 58 Chemistry 78 7Valve VavBoyBody integrity Structural Steel (internal)

Fuel oil material Loss of Effectiveness Program 10 VII.H1- 20 3.3.1- A Inspection 79 Valve Body S S Fuel oil Loss of Fuel Oil VII.H1- 3.3.1- B integrity (Internal) material Chemistry 10 20 Structural Air-outdoor Loss of External 3.3.1-80 Valve Body integrity Steel (External) material Surfaces VII19 58A Insert new rows 81 through 86 for Table 3.3.2-18 as shown on page 3.3-215a Aging Management Review Results Page 3.3-215 January*201.,

IAmendment 1 h'

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-18 Aging Management Review Results - Diesel Fuel Oil System I T INUREG- Notesl Row Com ponent MaterialeEA ging Effect Aging Row Typoen Intended Material Environment Requiring Management 1801 No. Type Function(s) Management Program Volume 1Table Item Notes 2 Item Pressure Soil Buried Piping 81 Bolting boundary Steel (External) Cracking and Tanks N/A N/A G Inspection Pressure Soil Buried Piping 82 Bolting boundary Steel (External) Loss of material and Tanks N/A N/A G Inspection Pressure Soil Loss of pre- Buried Piping boundary (External) load and Tanks N/A N/A G Inspection Structural Soil Buried Piping 84 Bolting integrity Steel (External) Cracking and Tanks N/A N/A G Inspection Structural Soil Buried Piping 85 Bolting integrity Steel (External) Loss of material and Tanks N/A N/A G Inspection Buried and Piping Tank Structural Soil Loss of pre-86 Bolting integrity Steel (External) load and Tanks N/A N/A G Inspection 3.3-215a Amendment 1 Aging Review Results Management Review Aging Management Results 3.3-215a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-21 Aging Management Review Results - Equipment Drains Radioactive System TAging Effect Aging NUREG-Row Component Intended iEing Magint 1801 Table No. Type Function(s) Material nvironment Requiring Management Volume 2 1 Item Notes SManagement Program Item Treated Monitoring and 52 Valve Body Sur Steel water Loss of Collection VII.E3- 3.3.1- E integrity(Internal) material Systems 18 17 Inspection Structural Air-indoor Loss of External3.3.1-53 Valve Body integrity Steel uncontrolled material Surfaces VII.1-8 58 A (External) material _Monitoring Page 3.3-232 Jan~ar~ 2010 Aging Management Aging Results Review Results Management Review Page 3.3-232 january 28 jAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-21 Aging Management Review Results - Equipment Drains Radioactive System Row Component T ]

Aging Effect Aging NUREG- Table Intended Material Environment Requiring Management 1801 1 Notes No. Type Function(s) i Management Program Volume 2 Item M mrItem Pump Casing Structural Stainless Air-indoor 3.3.1- A 54 (EDR-P14A, integrity Steel uncontrolled None None VII.J-15 94 0306 14B, 15) (Internal) 94_0306 Monitoring and Pump Casing Structural Stainless Raw water Loss of Collection VII.C1- 3.3.1-55 (EDR-P14A, integrity Steel (Internal) material Systems 15 79 E 14B, 15) Inspection Pump Casing Structural Stainless Air-indoor 3.3.1-56 (EDR-P14A, uncontrolled None None VII.J-15 A 14B, 15) integrity Steel (External) 94 Air-indoor Loss of SuracesVI.f-8 External 3.3.1-57 Tank (EDR- Structural Steel uncontrolled materialSurfacesMonitoring VII.-8 58 0302 TK-4A, 4B, 5) integrity (Internal)

Tank (EDR- Structural Moist air Loss of Supplemental VII.H2- 3.3.1- E 58 TK-4A, 4B, 5) integrity (Internal) material Piping/Tank 21 71 0303 TK-4, 4B 5) ntegityInspection Monitoring and 59 Tank (EDR- Structural Steel Raw water Loss of Collection VII.C1- 3.3.1- E TK-4A, 4B, 5) integrity (Internal) material Systems 19 76 Inspection Tank (EDR- Structural Air-indoor Loss of External 3.3.1 60 TK-4A, 48, 5) integrity Steel uncontrolled material Surfaces VII.I-8 58 A (External) Monitoring Amendment 1 Aging Management Review Results Review Results Page 3.3-232a Page 3.3-232a Amendment 1

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 Aging Effect 1801 Table No. Type Function(s) Material Environment Requiring Management Management Program Volume 2 Item 1 Item Notes Air-indoor Loss of External 113 Pump Casing Pressure Gray Cast uncontrolled material Surfaces VII.1-8 3.3.1- A (Lube Oil) boundary Iron (External) Monitoring 58 Pressure Air-indoor3.3.1- A 114 Sight Glass boundary Glass uncontrolled None None VII.J-8 33.1-0A (Internal) 93 0306 115 SightGlass Pressure Glass Raw water None 3.3.1- A boundary (Internal) None VII.J-11 Pressure Air-indoor 116 Sight Glass boundary Glass uncontrolled None None VII.J-8 3 A (External) 93 Air-indoor Etra Pressure Loss of External3.3.1- C 117 Sight Glass boundary Steel uncontrolled Surfaces VII.1-8 3.3.102 (Internal) material Monitoring 58 0302 118 Sight Glass Pressure Steel Raw water Loss of Fire Water VII.G-24 3.3.1- A boundary (Internal) material 68 Air-indoor Loss of External SurfaceseVII.s1-8 3.3.1-119 Sight Glass boundary Steel uncontrolled materialSurfaces VI-8 A (External) Monitoring Pressure Copper Alloy Air-indoor 120 Spray Nozzle boundary > 15% Zn uncontrolled None +4efe-- N/A N/A G b (Internal) I I1

[Insert: "Fire Water" F-sert- "03'27" 1 Aging Management Review Results Page 3.3-248 jA m e n d m e n t 1 - ,; . .... .. 2 0

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-22 Aging Management Review Results -Fire Protection System Row Component Intended TAging Aging Effect Aging Managmnt NUREG-1801 Table No. Type Function(s) Material nvironment Requiring Management Volume I Item Notes Management Program 2 Item Pressure Copper Alloy Raw water H 121 Spray Nozzle boundary > 15% Zn (Internal) Cracking N/A 0318 122 Spray Nozzle Pressure Copper Alloy Raw water Loss of Fire Water VII 012 3.3.1- A boundary > 15% Zn (Internal) material - 70 0317 nsert:

Pressure Copper Alloy Air-indoor '0327" 123 Spray Nozzle >15% Zn uncontrolled None Note N/A N/A G lboundary (External)

Air-indoor 124 Spray Nozzle Spray > 15% Alloy Copper uncontrolled (Internal) None > Non N/A N/A G Copper Alloy Raw water H 125 Spray Nozzle Spray > 15% Zn (Internal) Cracking Fire Water N/A N/A 0318 126 Spray Nozzle Spray Copper Alloy Raw water Loss of VII 012 3.3.1- A

> 15% Zn (Internal) material Fire Water - 70 0317 127 Spray Nozzle Spray >Copper Alloy 15% Zn Air-indoor (xenl Co27 Spray uncontrolled None -Nene N/A N/A G (External)

Pressure Air-indoor 128 Strainer (body) boundary Copper Alloy uncontrolled None None N/A N/A G (Internal) lInsert: "Fire Water" Aging Management Review Results Page 3.3-249 IAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-22 Aging Management Review Results -Fire Protection System Row Component Intended Aging Effect Aging NUREG-Row Cmpnen Fnctiondd Material Environment Requiring Management 1801 Table Notes No. Type Function(s) Maaeet{rga Volume 1 Item SManagement Program 2 Item 177 Valve Body Pressure Steel Raw water Loss of Fire Water VIIG-24 3.3.1- A boundary (Internal) material 68 Pressure Air-indoor Loss of External 3.3.1-178 Valve Body boundary Steel uncontrolled material Surfaces VII.1-8 58 A (External) Monitoring 17 Pressure Vle od telSurfaces Air-outdoor Loss of External3.3.1- VII.I-9 3..18 179 Valve Body boundary Steel (External) material Monitoring 58 Pressure Soil Loss of Buried Piping 3.3.1-180 Valve Body boundary Steel (External) material and Tanks VI.G-25 19 A bounday (Extrnal)Inspection 1 Insert new rows 181 through 183 for Table 3.3.2-22 as shown on page 3.3-256a Aging Management Review Results Page 3.3-256 ddiudiy 20 1fr j~mendment

Columbia Generating Station License Renewal Application Technical Information 3.3-256a Amendment 1 Aging Management Review Results Review Results 3.3-256a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-24 Aging Management Review Results - Floor Drain Radioactive 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 Monitoring and 37 Valve Body Structural Stainless Raw water Loss of Collection VII.C1- 3.3.1- E integrity Steel (Internal) material Systems 15 79 Inspection Structural Stainless Air-indoor3.3.1-38 Valve Body integrity Steel uncontrolled None None VII.J-15 3. A 38 VlBd itr(External)

Air-indoor External Structural Ai-nor Loss of Exenl3.3.1- C 39 Valve Body integrity Steel uncontrolled LossroflSurfaces VII.1-8 58 0302 (Internal) material Monitoring Monitoring and 40 Valve Body S S Raw water Loss of Collection VII.C1- 3.3.1- E integrity (Internal) material Systems 19 76 Inspection Structural Air-indoor Loss of External3.3.1-41 Valve Body integrity Steel uncontrolled material Surfaces VII1.-8 58 A (External) Monitoring Insert new rows 42 through 47 for Table 3.3.2-24 after this page Aging Management Review Results Page 3.3-263 manenamey 201 jAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-24 Aging Management Review Results - Floor Drain Radioactive System Row Component Intended Maeil Eniomnt Aging Rqiing Effect Mfet Aging angemnt 1NUREG-1801 Table Noe No. Type Function(s) Material Environment Requiring Management Volume 2 1 Item Notes Management Program Item Monitoring and 42 Pump Casing Structural Stainless Raw water Loss of Collection VII.C1- 3.3.1- E (FDR-P-21) integrity Steel (Internal) material Systems 15 79 Inspection Pump Casing Structural Stainless Air-indoor 3.3.1-43 (FRP2)

(FD R-P-21 ) itgiy integrity Seluncontrolled (External)

Steel None None VII. -15 94 94_____ A (Extr-nal) xera Tank (FDR- Structural Air-indoor Loss of External 3.3.1- C 44 T-)itgiy Steel uncontrolled maeilSurfaces VII -8 58 02 TK-9) integrity (Internal) material Monitoring 58 0302 Tank (FOR- Structural Moist air Loss of Supplemental VIIH2- 3.3.1- E 45 nTK-9) integrity Steel (Internal) material Piping/Tank 21 71 0303 Inspection Monitoring and 46 Tank (FDR- Structural Steel Raw water Loss of Collection VIIC1- 3.3.1- E TK-9) integrity (Internal) material Systems 19 76 Inspection Tank (FOR- Structural Air-indoor Loss of External 3.3.1 47 Tak. interity Steel uncontrolled material Surfaces VII,1-8 58 A TK-9) integrity (External) material _Monitoring 58 Page 3.3-263a Amendment 1 Review Results Management Review Aging Management Results Page 3.3-263a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-29 Aging Management Review Results- Potable Cold Water System Agihg:Effectý: Aging NUEG 110 1 NUREO- al Row, Component Intended Environment Requiring Management, 1801 Voume ITable item Notes TypeMaterial Management Program 2 Item Pump Casing Structural Copper Alloy Condensation. Loss of Lective 1,0 (PWC-P-A/B) integrity >15% Zn (External) material inspection N/AN/__

Shock Structural Copper Alloy Raw water Loss of Potable Water 3 3.1- E suppressor integrity (Internal) material Monitoring VIIC 81E Shock, Structural Condensation Loss of er1 3'n.

Z Supprssor integrity Copper Alloy , nenatn Loss Surfaces VIeF1n6 E Suprssr integy (External) material Monitoring.25

13. Strainer body Structural Copper Alloy Raw water Loss of Potable-Water I3.33.1- E integrity > 15%,Zh (Internal) material Monitoring - 81 I Copper. Alloy. Condensation Loss. of External 3 3.1- E Structural 14 Strainer (body) integrity > 15% Zn (External)i material MSurfaces.

onitoring ViI:F7,16 25 E

... .. .. .. .M Structural Copper Alloy Condensation. Loss-of Selective 'G 15 -Strainer (body).itgiy >1%Z (Eera) raeil Leaching N/A N/A. G I integrity >.15% Zn (External) material Inspection trih r( d .'Leaching. .... .. ,AlC - *3 Structural CopperAlloy Raw water Loss:of SelectieV 3.3.1-

.6. Staine (bo integrity > 15% Zn (Internal) material Lechin 10 84 A

- ~~Inspection____

17 Tank (shell and Structural Aluminum Raw water Loss-of Potable Water I3.31- E 18 end cap)

Tank (shell and end cap) integrity Structural integrity Aluminum (Internal)

Condensation (External) material Loss of material Monitoring Surfaces, External MSouaen I.itoring V1l.171'14-62 27 331E E:.l LI 0.nse14 O32 I

Aging Management Review Results Page 3.3-287 #Ia!uCi y 201' FAmendment 1 I

iDelete row S191 Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-29 Aging Management Review Results - Potable Cold Water System Row Component Intended Aging Effect Aging 1 NUREG-Row Cmpoent FInteond Material Environment Requiring Management 1801 Table Notes Type Function(s) Management Program 2 Item No. 2Vol meItem t Tank (shell and Structural Condensation External Amufn nur. . I I ____ -! 1 INfA

• f4 end cap) integrity (External) Monitoring 20 Tank (bushing) Structural Gray'Cast Rawwater Loss of Potable Water VII.G-24 3.3.1- E integrity Iron (Internal) material Monitoring 68 Selective:

21 Tank (bushing) Structural Gray integrity Iron Cast Raw water (Internal) Loss of material Leaching Inspection VII.C1-11 3.3.1-85 22 Structural Tnk.bushng)Surfaces Gray Cast Condensation Loss of External VI1.I-1i 3.1 3.3.1-. A 22 Tank (bushing) integrity Iron (External) material Monitoring 58 Structural Gray Cast Condensation Loss of Selective integrity Iron (External) material Leaching N/A N/A G Inspection 24 Tubing Structural Coe All Raw Water Loss of "Potable Water . C1-9 3.3.1- E integrity (Internal) material Monitoring VII81 25 TubingStructural CoppCondensation Loss of urna331- E 25 Tubing integrity Copper Alloy (External) material Monitoring 25 26 Tb Structural CopperAlloy Raw water Loss of Potable Water 3.3.1-integrity > 15% Zn (Internal) material Monitoring 81 27 Tubing Structural Copper Alloy Raw water Loss of Selective, VII.CI- 3.3.1-integrity > 15%Zn (Internal) material Leaching 110 84

_____ ________ _______ ______ _I_____ Inspection108A Page 3.3-288 ~u~r2O~a-Aging Review Results Management Review Aging Management Results Page,3.3-2,88 january2010 Am end me

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-30 Aging Management Review Results - Potable Hot Water System Row Component Intended Agn fet Aging Effect Aging Aig1801 NUREG- Table No. Type Function(s) Material Environment Requiring Management Voum TaIte Notes Management Program Volume 1 Item 2 Item Structural Copper Alloy Air-indoor 3.4.1-10 Valve Body integrity >15% Zn uncontrolled None None VIII.1-2 41 A 10_ _ Valve__Body_ integrity _ >_15%_n (External) 41 Insert new table rows 11 through 13 for Table 3.3.2-30, as show on page 3.3-291 a Aging Management Review Results Page 3.3-291 F Ja-uacrl 2010 Amendment 1 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-30 Aging Management Review Results - Potable Hot Water System Row Component Intended Maeil Eniomnt Aging RqiingEffect] Aging Mfet angemnt NUREG-1801 Table Noe No. Type Function(s) Material Environment Requiring Management Volume 2 1 Item Notes Management Program Item Tubing Structural Copper Alloy Raw water Loss of Potable Water VII.C1-9 3.3.1- E 11 integrity > 15% Zn (Internal) material Monitoring 81 Tubing Structural Copper Alloy Raw water Loss of Selective VII.C1- 3.3.1- A 12 integrity > 15% Zn (Internal) material Leaching 10 84 Inspection Tubing Structural Copper Alloy Air-indoor None None VIII.I-2 3.4.1- A 13 integrity > 15% Zn uncontrolled 41 (External)

Amendment 1 Review Results Aging Management Review Results Page 3.3-291a Page 3.3-291 a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-32 Aging Management Review Results - Process Sampling System Row Component Intended Aging Effect Aging Effet T Aging Aint NUREG-1801 Table No. Type Function(s) Material Environment Requiring Management Volume I Item Notes SManagement Program 2 Item 10 Strainer (body) Structural Steel Raw water Loss of Open-Cycle VII.C1-19 3.3.1- B integrity (Internal) material Cooling Water 76 11 Strainer (body) Structural integrity Steel Condensation (External) Loss of material External Surfaces Monitoring VII.I-11 3.3.1- A 58 12 Tubing Structural Copper Alloy Raw water Loss of Open-Cycle VII.C1-9 3.3.1- B integrity (Internal) material Cooling Water 81 13 Tubing Structural integrity Copper Alloy Condensation Loss of External3.3.1-(External) material Surfaces VII.F1-16 25 E Monitoring 14 Tubing Structural Stainless Raw water Loss of Open-Cycle VII.C1-15 3.3.1- B integrity Steel (Internal) material Cooling Water 79 Structural Stainless Condensation Loss of External 3.3.1-15 Tubing integrity Steel (External) material Surfaces VIIFl-i 27 E /Ionitoring Monitoring a nd Structural Copper Alloy Raw water -&epenGye <_ Collection 16 Valve Body Cracking N/A N/A H integrity > 15% Zn (Internal) Gee' +@-Wa4&_ S*ystems i + +i + 1I1n~rk:

I *, ,V T31-Un zv 17 Structural Copper Alloy Raw water Loss of Open-Cycle 3.3.1-Valve Body VII.C1-9 B integrity > 15% Zn (Internal) material Cooling Water 81 18 Valve Body

_ _

Structural integrity itegrity_

_ _ _

Copper

> 15% Zn

_

Alloy

_

Raw

_

water (Internal)

_ _ 1 Loss

_

of material

_ _ IInspection Selective Leaching Vll.C1_1I 3.3.1-

_j 84

_ __

A Aging Management Review Results Page 3.3-294 January 2010 IAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-34 Aging Management Review Results - Pump House HVAC Systems Aging Effect Aging NUREG-Row Component Intended Aging Manae ment 1801 Table No. Type Function(s) Material Environment Requiring Management Volume 1 Item Notes Management Program 2 Item Heat Exchanger Pressure Raw water Open-Cycle VIC- 3.3.1-34 (header) (PRA- boundary Steel (Internal) Loss of material Cooling Water 77 CC-lA/B, 91 A/B)

Delete Heat ExchngerExternal (Exchanger Pressure Condensation L oteriac (header) (PRA- boundary Steel (External) Loss of material Surfacesing 3.3.1-V1.1-11 58 A 36 CC-lA/B, Mntrn 91 A/B)

Heat Exchanger ExcanerCondensationLAuiiiri1iA Open-C yrle. 1

-3V (ill,15) (PFAb- Heat Idanslfr Aluminum (External) Cracking Cooling Water NIA WA CC-1A/B, 91 A/B)

Heat Add:

Exchanger Condensation Open-Cycle E 0325 37 (fins) (PRA-(finsA(PB, Heat transfer Aluminum (External) of material C ycle Cooling Water VII52-12 VII.FLoss 3.3.1-27 E CC-lA/B, 91 A/B)

Heat Exchanger Condensation Reduction in Open-Cycle 38 (fins) (PRA- Heat transfer Aluminum (External) heat transfer Cooling Water N/A N/A H CC-1A/B, 91 A/B)

Heat Exchanger Raw water Reduction in Open-Cycle VII.C1-6 3.3.1-39 (tubes) (PRA- Heat transfer Copper Alloy (Internal) heat transfer Cooling Water 83 CC-1A/B, 91 A/B) I I I I I I Aging Management Review Results Page 3.3-307 Jornuafy 2010 j~mendmen 1-

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-34 Aging Management Review Results - Pump House HVAC Systems Intended IAging Aging Effect Aging Mangint NUREG-1801 Table Row Component No. Type Function(s) Material Environment Requiring Management Management Program Volume 2 Item 1 Item Notes Heat Exchanger Condensation Reduction in Open-Cycle 40 (tubes) (PRA- Heat transfer Copper Alloy (Etenal) heat transfer Cooling Water N/A N/A H CC-1A/B, (External) 91A/B)

Heat Exchanger Pressure Raw water Loss of material Open-Cycle 3.3.1- B 41 (tubes) (PRA- boundary Copper Alloy (Internal) Cooling Water VI.C1-3 CC-1A/B, 91 A/B)

Heat Exchanger Pressure Condensation Open-Cycle 3.3.1- E 42 (tubes) (PRA- boundary Copper Alloy (External) Loss of material Cooling Water V1152-14 25 CC-lA/B, 91A/B)

Heat Exchanger Pressure Raw water Open-Cycle 3.3.1- B 43 (header) r Steel (Internal) Loss of material oinyWater 3 -77 (PMA-CC- boundary Steel 81 A/B)

Heat Exchanger Pressure Condensation External 3.3.1-44 (header) Steel (External) Loss of material Surfaces VI1.1-1 1 58 A (PMA-CC- Monitoring 81A/B)

Heat 45 Exchanger Alu..i.u.n Heat t.Enaf"r,, Condensation .... Open-Cycle WA..

(fins) (PMA- (External) Cooling Water CC-81A/B)

IDelete Row 45 ]

Aging Management Review Results Page 3.3-308 jAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-34 Aging Management Review Results - Pump House HVAC Systems TAging Effect Aging NUREG-Row Component Intended Aging Managemnt 1801 Table Notes No. Type Function(s) Material Environment RequiringMaagmet Management rgrm Volume olm2 Item Item Add:e Heat Exchangeranagmentnrogrmation 3.3.1- 0325 Add 46 Exchanger Heat transfer Aluminum Condensation Loss of material Open-Cycle V1112-12 331 (fins) (PMA- (External) Cooling Water 27 CC-81A/B)

Heat 47 Exchanger Heat transfer Aluminum Condensation Reduction in Open-Cycle N/A N/A H (fins) (PMA- (External) heat transfer Cooling Water CC-81 A/B)

Heat Exchanger Raw water Reduction in Open-Cycle VII.C1-6 3.3.1- B 48 (tubes) (PMA- Heat transfer Copper Alloy (Internal) heat transfer Cooling Water 83 CC-81 A/B)

Heat 49 Exchanger Heat transfer Copper Alloy Condensation Reduction in Open-Cycle N/A N/A H (tubes) (PMA- (External) heat transfer Cooling Water CC-81A/B)

Heat 50 Exchanger Pressure Copper Alloy Raw water Loss of material Open-Cycle VII.C1-3 3.3.1- B (tubes) (PMA- boundary (Internal) Cooling Water 82 CC-81A/B)

Heat Exchanger PressureCondensation 331 51 (tubes)xch(PMA- boundarye Copper Alloy Condenal) Loss of material Open-Cycle VII.F2-14 253.1- E CC-81 A/B) (tbs PA onay(External) Cooling Water 2 Mechanical Pressure Air-indoor Hardening and External 3.3.1-52 Sealants boundary Elastomer uncontrolled loss of strength Surfaces VII.F1-7 1 E (Internal) Monitoring 11 53 Mechanical Pressure EasAir-indoor Har External 3.3.1- E 53 Sealants boury Elastomer uncontrolled Hardening and Surfaces VII.F1-7 11 Sealants_____boundary____ (External) loss of strength Monitoring 11 Aging Management Review Results Page 3.3-309 Janumry 2010 Amndent 1J

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-36 Aging Management Review Results - Radwaste Building HVAC Systems Aging Effect Aging NUREG-Row Component Intended Material Environment Requiting Management 1801 Table I Notes No. Type Function(s) Volume Management Program " '2 - 2 Item Item Item Air-Handling Unit Housing Air-indoor Loss of External 3.3.1- C 1 (WMA-AH- Pressure Steel uncontrolled L Surfaces VII.L-8 64AI*-,52A/B, boundary (Internal) material Monitoring 58 0302 Air-Handling Unit Housing Pressure Air-indoor Loss of External 3.3.1-1 2(WMA-AH- Steel uncontrolled Surfaces Vil.l-8 58 A W 52NB, (External) Monitoring oaterial 3 Bolting Pressure Stainless Air-indoor uncor Loss of bonay Seluncontrolled pr-odBolting Integrity N/A N/AF boundary Steel (External) pre-load 4boundary Pressure Air-indoor Lossof 3.3.1-Steel uncontrolled mtrl Bolting Integrity VII.I-4 B (External) maeral4 Pressure Air-indoor Loss of 331-5 Blnbury Steel uncontrolled preloadBolting Integrity VII.-5 5_ Botingboundary (External) _________ 45 6 Bolting Pressure Condensation Cracking Bolting Integrity N/A N/A H boundary Steel (External)

Pressure Condensation Loss of 3.3.1-7 Bolting boundary Steel (External) material Bolting Integrity VIID-1 44 B 8 Bolting Pressure Steel Condensation Loss of Bolting Integrity N/A N/A H boundary S(External) pre-load Aging Management Rey.iew Results Page 1.3-315 -jaiipary 20 1u dment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-36 Aging Management Review Results - Radwaste Building HVAC Systems Row Row Component Coponen Intended Fntiendd Material Environment IAging Agn Effect fet Requiring Aig10 Aging Management NUREG- al 1801 Table I Notes No. Type Function(s) Maaeet Programn volume Item Management Pro2 Item Heat Exchanger External 37 (header) Pressure Steel Condensation Loss of Surfaces VI.1-11 3.3.1- A (WMA-CC- boundary (External) material Monitoring 58 51A2, 51B2, 52A2 & 52832)

Heat Exchanger 38 (fins) (WMA- Heat transfer Aluminum Condensation Cooling Units N/A N/A H CC-51 A2, (External) Cracking Inspection 51B2, 52A2 &

52B2)

Heat Exchanger 39 (fins) (WMA- Heat transfer Aluminum Condensation Loss of Cooling Units V15F2-12 3.3.1- E CC-51A2, (External) material Inspection 27 51B2, 52A2 &

52B2)

Heat Exchanger 40 (fins) (WMA- Heat transfer Aluminum Condensation Reduction in Cooling Units N/A N/A H CC-51A2, (External) heat transfer Inspection 51B2, 52A2 &

52B2)

Heat Exchanger Ccncn.... -Q,,R,,,.-

41 (fins) (WMA- Heat transfer Aluminum (External) Cracking Cooling Water N/A CC-53A2 &

Det 53Rw2)

IDelete Row 41 1 Aging Management Review Results Page 3.3-320 AAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-36 Aging Management Review Results - Radwaste Building HVAC Systems Row Component Intended TAging Aging Effect Aging Manae Ajnt NUREG-1801 Table 1N No. Type Function(s) Material Environment Requiring Management Volume Item Notes Management Program 2 Item Heat Exchanger Condensation Loss of Open-Cycle 3.3.1- Add: j V1152-12 27 E 03~25J 42 (fins) (WMA- Heat transfer Aluminum (External) material Cooling Water CC-53A2 &

53B2)

Heat Exchanger Condensation Reduction in Open-Cycle 43 (fins) (WMA- Heat transfer Aluminum (External) heat transfer Cooling Water N/A H CC-53A2 &

53B2)

Heat Exchanger (tubes) (WMA-CC-51Al, H t Condensation Reduction in Open-Cycle N/A N/A H 51B1, 52A1, Heat transfer CopprAly (External) heat transfer Cooling Water 52B1, 53A1, 53A2, 53B1 &

53B2 Heat Exchanger (tubes) (WMA-CC-51A1, Heat t Raw water Reduction in Open-Cycle VII.C1-6 3.3.1- B 51B1, 52A1, HeatLtransfer Copper Ally (Internal) heat transfer Cooling Water 83 52B1, 53A1, 53A2, 53B1 &

53B2)

JdIIudIy 2010 Management Review Aging Management Results Review Results Page 3.3-321 Page 3.3-321 dai iudi y 20 10

Columbia Generating: Station LicenseiRenewal.Application Technical Information Table-3.1.2-36 Aging. Management Review Results - Radwaste Building HVAC 'Systems Aging,Effect Aging NURG Row Component Intended Material Environment: Reqfiring Managementble"! Notes

,No., 'Type Function(s) - Management Maaemn Program Prga 2VIteme Vollume tm Item ....

.... . " 2:Item . .

Delete r 66 65 Pipin pg Structural SteeAir-indoor . External 3.31-integrity Steel uncontrolled LossZof Surfaces VII.48 intgrL*0_- (External) material Monitoring 58 A

_......Struruthiral Staninla-,* Qnndpnsatinn External integrity Steel ineriyMonitoring (External), rac~ing *urraces N7I/ N7P -

Structural Stainless Condensation Lossof External integrity Steel (External) material Monitorng 277 SoundoudPressure Air-indoor Loss of" External- 31i3:1 - C 68 Absorber Steel uncontrolled LSurfaces VII.k-8 38 0302 Casing boundary (Entemal) materal Monitoring- 5 Sou n'd ,P es r A ir-ind oor - Loss-of- Ek&a[33.1 -

69 Ab*sorber i rsue Steel uncontrolled- :,mtra Surface's VILI_-8 A Casing, bonay(External) . Monitoring 5 70 Strainer (body) Structural SteelRaw water Lossf OpenycleB integrity (Internal) material Co0ling Water 76 Lossof E31 EtrctlCondensationVII -11 A 71 Strainer (body) integrity, Steul Steel (External) material _Surfaces 58.

IMonitoing Pressure Air-indoor 72 Tubing, boundary Copper-Alloy uncontrolled None None, N/A N/A G

________ (Internal) .. .... .

Pressure Air-indoor 73 Tubing Copper Alloy uncontrolled None None N/A N/A G boundary (External)

Aging, Management Review Results Page 3.3-325 A e > -danur2ele-I~mendmnt 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-36 Aging Management Review Results - Radwaste Building HVAC Systems Component Intended Aging Effect Aging NUREG-Row No. Type Function(s) Material Environment Requiring Management 1801 Table 1 Notes Management Program Volume Item 2 Item 92 Valve Body Structural integrity Steel Air-indoor uncontrolled Loss of material External3.3.1 Surfaces VII1.-8 .1 A I (External) material Monitoring 58 Structural Condensation Loss of External 3.3.1-93 Valve Body integrity Steel (External) material Surfaces Monitoring VI1.I-1 1 58 A Insert new rows 94 through 99 for Table 3.3.2-36 as shown on page 3.3-328a Aging Management Review Results >

Page 3.3-328 Fm-endment 1 T jaRwary 201-9

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-36 Aging Management Review Results - Radwaste Building HVAC Systems Intended Aging Effect Aging NUREG-Row Component Row Typo Funtended Material Environment Requiring Management 1801 Table 1 Notes No. Type Function(s) Management Program Volume Item 1 1 Air-indoor 122Item External Air-Handling Loss of 331 00 Unit Housing Pressure Steel uncontrolled Surfaces VII.I-8 3.3.1- C0302 (WMA-AH- boundary (Internal) material Monitoring 58 51A/B)

Air-Handling 95 Unit Housing Pressure Steel Condensation Loss of Cooling Units VIIG-23 3.3.1- E0326 (WMA-AH- boundary (Internal) material Inspection 71 51 A/B)

Air-Handling Air-indoor External 96 Unit Housing Pressure Steel uncontrolled Loss of Surfaces VII.M-8 3.3.1- A (WMA-AH- boundary (External) material Monitoring 58 51 A/B)

Soil Buried Piping Pressure G 97 Bolting boundary Steel (External) Cracking and Tanks N/A N/A Inspection Soil Loss of Buried Piping Pressure G 98 Bolting Steel Soil Lossrofland Tanks N/A N/A gboundary (External) material Inspection Pressure Soil Loss of Buried Piping 99 Bolting boundary Steel External) preload and Tanks N/A N/A G I I Inspection Page 3.3-328a Amendment 1 Aging Management Results Review Results Management Review Page 3.3-328a Amendmeni i

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-37 Aging Management Review Results - Reactor Building HVAC Systems SAging Effect Aging NUREG-Row Component Intended Aring Magint 1801 Table 1 No. Type Function(s) Material Environment Requiring Management Volume Item Notes SManagement Program 2 Item Heat Exchanger Structural Air-indoor Loss of External 3.3.1-33 (housing) Steel uncontrolled Surfaces VII.I-8 58 A (ROA-HC-1 & integrity (External) material Monitoring 2)

Heat Exchanger (header) 34 (RRA-CC-1, 2, Pressure Steel Raw water Loss of Open-Cycle VII.C1-5 3.3.1- B 3, 4, 5, 6, 10, boundary (Internal) material Cooling Water 77 11, 12,13, 14, 15, 17,19 &

20)

Heat Exchanger (header) External 35 (RRA-CC-1, 2, Pressure Steel Condensation Loss of Surfaces Vl1.1-11 3.3.1- A 3, 4, 5, 6,10, boundary (External) material Monitoring 58 11, 12, 13, 14, 15, 17, 19 &

20)

Heat Exchanger (fins) (RRA- Condensation Open-Cvcle 36 CC 1,2,3,4, Ieattral AL1 liiiUiii (External) Cooling Water 5,6,10,11, 12, 13, 14, 15,

____ 17, 19 & 20)

IDelete Row 36 Aging Management Review Results Page 3.3-333 january 2010 jAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-37 Aging Management Review Results - Reactor Building HVAC Systems Aging NUREG-Row No. Component Type Intended Function(s) Aging Effect Aging Efet.gn 1801 Table I Material Environment Requiring Management Voum Te Notes Management Program Volume Item 2 Item Heat Exchanger ColubiaGeneatig Sttio Add:

(fins) (RRA- Condensation Loss of Open-Cycle 0325 37 CC-1, 2, 3, 4, Heat transfer Aluminum (Extenal) oftOpen-Coole VII.F2-12 3.3.1- E 5,6, 10, 11, (External) material Cooling Water 27 12, 13, 14,15, 4 Heat Exchanger (fins) (RRA-38 CC-i, 2, 3, 4, Heat transfer Aluminum Condensation Reduction in Open-Cycle H 5, 6,10, 11, (External) heat transfer Cooling Water N/A N/A 12, 1,,,14, !a, Heat Exchanger Structural Steam Loss of BWR Water 39 (header) i Steel N/A N/A G (ROA-HC-1 & integrity (Internal) material Chemistry 2

Heat Chemistry Exchanger Structural Steam Loss of Program 40 (header) intStam LosAofNrogra (ROA-HC-1 & integrity (Internal) material Effectiveness 2& Inspection Heat Flow-Exchanger Structural Steam Loss of Accelerated 41 (header) Strutu Steel (Internal) material CorrosionG (ROA-HC-1 & integrityC

2) (FAC)

Jw~1 ua~ 2013 Aging Management Review Aging Management Results Review Results Page 3.3-334 Page 3.3-334 ja mHary 2810

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-37 Aging Management Review Results - Reactor Building HVAC Systems Aging Effect Aging TaNUREG-RNo. Type Function(s) Material Environment Requiring Management Volume Item Notes Management Program 2 Item Structural Raw water Loss of Potable Water 3.3.1-80 Valve Body integrity (Internal) material Monitoring1-19 76 E 81 81Vlve ody Valve Body integrity Structural Sel(internal) Steam material Loss of Chemistry BWR Water N/NAG N/A N/A G Chemistry 82 Valve Body Structural Steam Loss of Program G integrity (Internal) material Effectiveness Inspection Flow-83 Valve Body Structural Steel Steam Loss of Accelerated N/A N/A G integrity (Internal) material Corrosion (FAC) 84 Valve Body Structural integrity Steel Air-indoor uncontrolled Loss of material External3.3.1-Surfaces VII 1.-8 383A (External) Monitoring 58 External 85 Valve Body Structural integrity Steel Condensation (External) Loss of trnal 3.3.1-material Monitoring V-Insert new rows 86 and 87 from Page 3.3-340a Aging Management Review Results Page 3.3-340 JenuaFy"20,-

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-37 Aging Management Review Results - Reactor Building HVAC Systems Aging Effect Aging NUREG-RNo. Type Function(s) Material Environment Requiring Management Voum Te Notes Management Program volume Item 2 Item Heat Exchanger (fins) (RRA- Condensation Loss of Open-Cycle VII.F2-14 3.3.1-86 CC-12, 13, 14, Heat transfer Copper Alloy (External) material Cooling Water 25 15, 17, 19, &

20)

Heat Exchanger 87 (fins) (RRA- Heat transfer Copper Alloy Condensation Reduction in Open-Cycle N/A N/A H CC-1 2, 13, 14, (External) heat transfer Cooling Water 15, 17, 19, &

20) 3.3-340a Amendment 1 Aging Management Aging Results Review Results Management Review 3.3-340a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-42 Aging Management Review Results - Standby Service Water System I Aging Effect Aging NUREG-Row Component Intended Material Environment Requiring Management 1801 Table 1 Notes No. Type Function(s) Management Program Volume Item Structural Stainless Air-indoor2tmA Ai-nor3.3.1- A 105 Valve Body inteructu Stale uncontrolled None None VII.J-15 94 0306 yntegrity Steel (Internal) 106 Valve Body Structural Stainless Raw water Loss of Open-Cycle VII.C1-15 3.3.1- B integrity Steel (Internal) material Cooling Water 79 107 Valve Body Structural integrity Stainless Steel Air-indoor3.3.1-uncontrolled None None VII.J-15 3. A (External) 108 Valve Body Sttu integrity Steel Air-indoor Loss of External uncontrolled Surfaces VII.1-8 58 0302 (Internal) material Monitoring 109 Valve Body Structural Raw water Loss of Open-Cycle VII.C1-19 3.3.1- B integrity Steel (Internal) material Cooling Water 76 Structural Air-indoor Loss of External 110 Valve Body integrity Steel uncontrolled material Surfaces VII.1-8 3. A (External) Monitoring 58 Add new rows 111 through 116 shown onpage 3.3-390a Aging Management Review Results Page 3.3-390 january 20 10 j~mendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-42 Aging Management Review Results - Standby Service Water System Row Component Intended Maeil Eniomnt Aging Effect Rqiing MfetAging angemnt NUREG-1801 Table Noe No. Type Function(s) Material Environment Requiring Management Volume 1 Item Notes Management Program 2 Item Pressure Soil Buried Piping ill Bolting boundary Steel (External) Cracking and Tanks N/A N/A G Inspection Pressure Soil Buried Piping 112 Bolting boundary Steel (External) Loss of material and Tanks N/A N/A G Inspection eSoil Loss of pre- Buried Piping 113 Bolting Pressure Steel Soil loss and Tanks N/A N/A G boundary (External) load Inspection 114 Orifice Pressure Stainless Soil Loss of material Buried and Piping Tanks VI1.C1-16 331-

• • E boundary Steel (External) Inspection 29 Pressure Stainless Soil Buried Piping 3.3.1-115 Piping boundary Steel (External) Loss of material and Tanks VII.C1-16 29 E Inspection Pressure Stainless Soil Buried Piping 3.3.1-116 Valve body boundary Steel (External) Loss of material and Tanks VII.C1-16 29 E bua Steel (External) Inspection 29 3.3-390a Amendment 1 Aging Review Results Management Review Aging Management Results 3.3-390a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-43 Aging Management Review Results - Tower Makeup Water System Aging Effect Aging NUREG-RowMaterial Environment Requiring Management 1801 Table 1 Notes No. Type Function(s) Management Program Volume Item 2 Item Pressure Steel Raw water Loss of Open-Cycle VII.C119 331 B boundary (Internal) material Cooling Water 76 38 Valve Body boundary Pressure Pressury Steel (External)

Air-indoor uncontrolled Loss of matriaMoitoin material External Surfaces VII.I-8 3.3.1-58 A (Externl)Montorinal Pressure Air-outdoor Loss of External3.3.1-39 Valve Body boundary Steel (External) material Surfaces VII.1-9 3. A Monitoring 58 Pressure Condensation Loss of External3.3.1-40 Valve Body boundary Steel (External) material Surfaces VII.I-1 1 58 A (External)I Monitoring Insert new rows 41 through 44 for Table 3.3.2-43 as shown on page 3.3-395a Aging Management Review Results Page 3.3-395 jai iuaiy 20 10 j~edmn

Columbia Generating Station License Renewal Application Technical Information 3.3-395a Amendment 1 Aging Management Review Results Review Results 3.3-395a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-44 Aging Management Review Results - Traversing Incore Probe System Aging Effect Aging NUREG-Row Component Intended Aging Manae ment 1801 Table No. Type Function(s) Material Environment Requiring Management Volume 1 Item Notes Management Program 2 Item Structural Stainless Air-indoor3.3.1- A 10 Piping uncontrolled None None VII.J-15 3.3.1-6 10 Piping integrity Steel (Internal) 94 0306 11 Piping Structural Stainless Gas None None VIIJ-19 3.3.1- A integrity Steel (Internal) 97 Structural Stainless Air-indoor3.3.1-12 Piping ntegrutua Suncontrolled None None VII.J-15 3. A gintegrity Steel (External)

Pressure Stainless Air-indoor3.3.1- A 13 Valve Body uncontrolled None None VII.J-15 3.3.1-6 13 ValveBy boundary Steel (Internal) 94 0306 Pressure Stainless Gas 3.3.1-14 Valve Body boundary Steel (Internal) None None VII.J-19 7A Pressure Stainless Air-indoor3.3.1-15 Valve Body uncontrolled None None VII.J-15 3. A boundary y Steel (External)

Structural Stainless Air-indoor3.3.1- A 16 Valve Body i S uncontrolled None None VII.J-15 3.3.1-6 16 VaveBoy integrity Steel (Internal) 94 0306 17 Valve Body Structural Stainless Gas None VIIJ-19 3.3.1- A integrity Steel (Internal) None 97 Structural Stainless Air-indoor3.3.1-18 Valve Body integrity Steel uncontrolled None None VII.J-15 3. A 18_ValveBody integrity _ Steel(External) 4 I Insert new LRA Tables 3.3.2-45, 3.3.2-46, and 3.3.2-47 after this page Aging Management Review Results Page 3.3-397 jAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-45 Aging Management Review Results - Heating Steam System Aging Effect NUREG-Row Component Intended Material Environment RequiringManagement 1801 Table No. Type Function(s) Management Program Volume 1 Item 2 Item Air-indoor 1 Bolting Structural integrity Steel Air-indo Loss of 3.3.1-uncontrolled Bolting Integrity VII.B-4 B (External) material 4 Structural Loss of 3.3.1-2 Bolting integrity Steel uncontrolled pre-load Bolting Integrity VII.-5 B (External) 45 Heat 3 Exchanger Structural Steel Steam Loss of BWR Water N/A N/A G (header) integrity (Internal) material Chemistry (WOA-HC-1)

Heat Eh Stt l Steam Loss of Chemistry Program xcanger rucura Steel Effectiveness N/A N/A G (header) integrity (Internal) material (WOA-HC-1) Inspection Heat 5 Exchanger Structural Steel Steam Loss of Flow-Accelerated N/A N/A G (header) integrity (Internal) material Corrosion (FAC)

(WOA-HC-1)

Heat Exchanger Structural Steel uncontrolled Loss of External Surfaces VII.1-8 3.3.1- A (header) integrity unotroll material Monitoring 58 (WOA-HC-1) (External)

Heat Exchanger Structural Steam Loss of BWR Water 7 (header)SteN/ NA G (WRASUH-4, integrity (Internal) material Chemistry 5, 6)

Heat Exchanger Structural Steam Loss of Chemistry Program 8 (header) integrity Steel Effectiveness N/A N/A G (WRA-SUH-4, (Internal) material Inspection 5, 6)

Aging Management Review Results Page 3.3-397a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-45 Aging Management Review Results - Heating Steam System Aging Effect Aging Management Requiring Program Management Flow-Accelerated Corrosion (FAC)

External Surfaces BWR Water None BWR Water Results Review Results Page 3.3-397b Amendment 1 Aging Management Aging Management Review Page 3.3-397b Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-45 Aging Management Review Results - Heating Steam 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 Heat Exchanger Structural Stainless Steam Loss of BWR Water 16 (tubes) integrity Steel (internal) material ChemistryG (WRA-SUH-1, 3,4,5)

Heat Exchanger Structural Stainless Steam Loss of Chemistry Program 17 (tubes) i S ( Effectiveness N/A N/A G (WRA-SUH-1, integrity Steel (Internal) material Inspection 3,4,5)

Heat Exchanger Structural Stainless Air-indoor 3.3.1-18 (tubes) uncontrolled None None VII.J-15 31 C (WRA-SUH-1, integrity Steel (External) 94 3,4,5)

Humidifier 19 (WMA-HU-6, Structural Gray Cast Steam Loss of BWR Water N/A N/A G WOA-HU-4, integrity Iron (Internal) material Chemistry 5,9)

Humidifier 20 (WMA-HU-6, Structural Gray Cast Steam Loss of Chemistry Program N/A N/A G WOA-HU-4, integrity Iron (Internal) material Effectiveness 5, 9)

Humidifier 21 (WMA-HU-6, Structural Gray Cast Steam Loss of Flow-Accelerated N/A N/A G WOA-HU-4, integrity Iron (Internal) material Corrosion (FAC) 5,9 )

Humidifier 22 (WMA-HU-6, Structural Gray Cast Steam Loss of Selective Leaching N/A N/A G WOA-HU-4, integrity Iron (Internal) material Inspection 5, 9)

Aging Management Review Results Page 3.3-397c Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-45 Aging Management Review Results - Heating Steam 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 Humidifier Air-indoor 23 (WMA-HU-6, Structural Gray Cast uncontrolled Loss of External Surfaces VII.l-8 3.3.1- A WOA-HU-4, integrity Iron (External) material Monitoring 58 5, 9) 24 P.. Structural Steel Steam Loss of BWR Water N/A N/A G iping integrity (Internal) material Chemistry 25 Structural Piin trctra tel Steam temLos Loss off Chemistry Program Effectiveness N/A N/A G 25 Piping integrity Steel (Internal) material Inspection 26 Structural Steel Steam Loss of Flow-Accelerated N/A N/A G Piping integrity (Internal) material Corrosion (FAC)

Structural Air-indoor Loss of External Surfaces 3.3.1-27 Piping integrity Steel uncontrolled material Monitoring 58 (External) materialMnitoring _5 28 Strainer Structural Steam Loss of BWR Water N/A N/A G (body) integrity Copper Alloy (Internal) material Chemistry Strainer Structural Steam Loss of Chemistry Program 29 (body) integrity Copper Alloy (Internal) material Effectiveness N/A N/A G Inspection Structural Air-indoor Strainer 30 (body) integrity Copper Alloy uncontrolled None None N/A N/A G (External) 31 Trap Body Structural Gray Cast Steam Loss of BWR Water N/A N/A G integrity Iron (Internal) material Chemistry Page 3.3-397d Amendment 1 Aging Management Aging Review Results Management Review Results Page 3.3-397d Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-45 Aging Management Review Results - Heating Steam 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 Structural Gray Cast Steam Loss of Chemistry Program 32 Trap Body integrity Iron (Internal) material Effectiveness N/A N/A G Inspection 33 Trap Body Structural Gray Cast Steam Loss of Flow-Accelerated integrity Iron (Internal) material Corrosion (FAC) N/A N/A G 34 Trap Body Structural Gray Cast Steam Loss of Selective Leaching N/A N/A G integrity Iron (Internal) material Inspection Structural Gray Cast Air-indoor Loss of External Surfaces 3.3.1-3 Body integrity Iron uncontrolled material Monitoring 58

________(External) 36 Tubing Structural Stainless Steam BWR Water N/A N/A G integrity Steel (Internal) Cracking Chemistry Structural Stainless Steam Chemistry Program 37 Tubing integrity Steel (Internal) Cracking Effectiveness N/A N/A G Inspection 38 Tubing Structural Stainless Steam Loss of BWR Water N/A N/A G integrity Steel (Internal) material Chemistry Structural Stainless Steam Loss of Chemistry Program 39 Tubing integrity Steel (Internal) material Inspection Structural Stainless Air-indoor 3.3.1-40 Tubing integrity Steel uncontrolled None None VII.J-15 A 40 __Tubing __ integrity__ Steel(External) 94 Amendment 1 Aging Management Review Results Management Review Results Page 3.3-397e Page 3.3-397e Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-45 Aging Management Review Results - Heating Steam 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 BWR Water A N/Am Structural Steam Loss of 41 Valve Body integrity Copper Alloy (Internal) material Chemistry N/A N/A G Structural Steam Loss of Chemistry Program 42 Valve Body integrity Copper Alloy (internal) material Effectiveness N/A N/A G Inspection-Structural Air-indoor 43 Valve Body integrity Copper Alloy uncontrolled None None N/A N/A G (External) 44 Structural Gray Cast Steam Loss of BWR Water N/A N/A G Valve Body integrity Iron (Internal) material Chemistry Structural Gray Cast Steam Loss of Chemistry Program 45 Valve Body integrity Iron (Internal) material Effectiveness N/A N/A G interityInspection 46 Valve Body Structural Gray Cast Steam Loss of Flow-Accelerated N/A N/A G integrity Iron (Internal) material Corrosion (FAC) 47 Structural Gray Cast Steam Loss of Selective Leaching N/A N/A G Valve Body integrity Iron (Internal) material Inspection Structural Gray Cast Air-indoor Loss of External Surfaces 3.3.1-48 Valve Body integrity Iron uncontrolled material Monitoring 58 (External) 49 Valve Body Structural Steel Steam Loss of BWR Water N/A N/A G integrity (Internal) material Chemistry Page 3.3-397f Amendment I Aging Management Management Review Results Review Results Page 3.3-397f Amendment I

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-45 Aging Management Review Results - Heating Steam 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 Structural Steam Loss of Chemistry Program 50 Valve Body integrity Steel (internal) material Effectiveness N/A N/A G Inspection 51 Valve Body Structural Steel Steam Loss of Flow-Accelerated N/A N/A G integrity (Internal) material Corrosion (FAC)

Structural Air-indoor Loss of External Surfaces 3.3.1-52 Valve Body integrity Steel uncontrolled material Monitoring 58 (External) materialMonitoring_58 Page 3.3-397g Amendment 1 Aging Management Aging Results Review Results Management Review Page 3.3-397g Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate 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 Air-indoor Structural Stelincor Loss of 3.3.1-Bolting integrity Steel uncontrolled (External) material maeil4 Bolting Integrity VII.I-4 B Structural Air-indoor Loss of 3.3.1-2 Bolting integrity Steel uncontrolled pre-load Bolting Integrity VII.l-5 3. B (External) pre-load_45 3 Structural Steel Steam Loss of BWR Water N/A N/A G 3ipingI integrity (Internal) material Chemistry Structural Steam Loss of Chemistry Program 4 Piping Steel Effectiveness N/A N/A G integrity S(Internal) material Inspection P.. Structural Steel Steam Loss of Flow-Accelerated N/A N/A G iping integrity (Internal) material Corrosion (FAC) 6 Piping Structural integrity Steel Treated water

> 60(Internal)

°C (140 Loss of material BWR Water Chemistry VII.E3- 3.3.1- A PF)

Structural Treated water Loss of Chemistry Program VII.E3- 3.3.1- A 7 Piping integrity Steel > 60 °C (140 Effectiveness 18 17 0305 iF) (Internal) material Inspection Structural Air-indoor Loss of External Surfaces 3.3.1-8 Piping integrity Steel uncontrolled material Monitoring 58 (External)

Pump Casing Air-indoor Loss of External Surfaces 3.3.1- C 9 (WHCO-P-1A, Structural Gray Cast uncontrolled material Monitoring VII.I-8 1B) integrity Iron (Internal) 58 0302 Aging Management Review Results Page 3.3-397h Amendment 1

Columbia Generating Station License Renewal Application Technical Information T

Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate System eAging Effect NUREG-Row Component AgnIfec Management gn Prgrm 0olm TaItem Nte Intended Material Environment Requiring AgingProgram Management 1801 No. Type Function(s) Management Volume 1Table Item Notes 2 Item Pump Casing Structural Gray Cast Moist air Loss of Supplemental VII.H2- 3.3.1- E 10 (WHCO-P-1A, Strutu Gray CIsteair Lossrofl Piping/Tank 21 71 0303 1B) integrity Iron (Internal) material Inspection Pump Casing Structural Gray Cast Treated water Loss of BWR Water VII.E3- 3.3.1- A 1B) integrity Iron 0

' F) (Internal) material Chemistry 18 17 0305 12 (HOP-A Pump Casing tucua G ray Cs Cast >60°(10 Treated water Lsof Loss of Effectiveness Chemistry Program VIE-VII.E3- 331 3.3.1- A SB) integrity Iron F 0 C (140 material Inspection 18 17 0305 12 B)COPA inerty IoOF) (Internal) Inspection _____

PumpCasing Structural Gray Cast > water Loss of Selective Leaching VII.E3- 3.3.1- A 13 integrity Iron >F) (140 material Inspection 12 85 0305 1B) OF) (Internal) ___

Pump Casing Structural Gray Cast Air-indoor Loss of External Surfaces 3.3.1-S(WHCO-P-1A, integrity Iron uncontrolled material Monitoring 58 141B) inert rn(External)____

15 Strainer Structural Gray Cast Steam Loss of BWR Water N/A N/A G (body) integrity Iron (Internal) material Chemistry Strainer Structural Gray Cast Steam Loss of Chemistry Program (body) 16Effectiveness integrity Iron (Internal) material Insection N/A N/A_ N/A N/A_ G Inspection 17 Strainer Structural Gray Cast Steam Loss of Flow-Accelerated N/A N/A G (body) integrity Iron (Internal) material Corrosion (FAC) 18 Strainer Structural Gray Cast Steam Loss of Selective Leaching N/A N/A G (body) integrity Iron (Internal) material Inspection Page 3.3-397i Amendment 1 Aging Management Aging Results Review Results Management Review Page 3.3-397i Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate 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 19 Strainer Structural Gray Cast Air-indoor Loss of External Surfaces V.-8 3.3.1- A (body) integrity Iron (External) material Monitoring 58 Air-indoorVIl-20 Tank (WHCO- Structural Steel uncontrolled Loss of External Surfaces 3.3.1- C CU-1) integrity (Internal) material Monitoring 58 0302 Tank (WHCO- Structural Moist air Loss of Supplemental 21 71 0 21 CU-1) integrity Steel (Internal) material Inspection 21 71 0303 22 Tank (WHCO-C-)itgiy Structural Sel> 60 0C (140 Treated water Loss of BWR Water VII.E3- 3.3.1- C CU-)

2 integrity F)0 (Internal) material Chemistry 18 17 0305 Treated water Loss of Chemistry Program VIIE3- 3.3.1- C 23 CU-1) integrity Steel > 60 OC (140 material Effectiveness CF) (Internal) Inspection 18 17 0305 24 Tank (WHCO- Structural Steel Steam Loss of BWR Water N/A N/A G CU-1) integrity (Internal) material Chemistry Tank (WHCO- Structural Steam Loss of Chemistry Program 25 CU-1) integrity Steel (Internal) material Effectiveness N/A N/A G Inspection 26 Tank (WHCO- Structural Steel Steam Loss of Flow-Accelerated N/A N/A G CU-1) integrity (Internal) material Corrosion (FAC) 27 Tank (WHCO- Structural Steel Air-indoor Loss of External Surfaces V.I-8 3.3.1- A CU-1) integrity uncontrolled material Monitoring 58

_____

_____ _ ___

__ _ _____ ___ _ _____ ____ (External) _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ __ _ _ _

Page 3.3-397j Amendment 1 Review Results Management Review Aging Management Results Page 3.3-397j Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate 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 28 Trap Body Structural Gray Cast Steam Loss of BWR Water N/A N/A G integrity Iron (Internal) material Chemistry 29 Structural Ta oyEffectiveness Gray Cast Steam Loss of Chemistry Program N/A N/A G 29 Trap Body integrity Iron (Internal) material Inspection 30 Trap Body Structural Gray Cast Steam Loss of Flow-Accelerated N/A N/A G integrity Iron (Internal) material Corrosion (FAC) 31 Trap Body Structural Gray Cast Steam Loss of Selective Leaching N/A N/A G integrity Iron (Internal) material Inspection Air-indoor Structural Gray Cast uncontrolled Loss of External Surfaces V.I-8 3.3.1- A 32 Trap Body integrity Iron (External) material Monitoring 58 33 Structural Steam Loss of BWR Water N/A N/A G Tubing 33 integrity Copper Alloy (Internal) material Chemistry Structural Steam Loss of Chemistry Program 34 Tubing integrity Copper Alloy (Internal) material Effectiveness N/A N/A G Inspection StructuralStructural ~~Treated water TetdwerLoss Ls off BRWtr331 BWR Water 3.3.1- A 35 Tubing integrity Copper Alloy > 60 IC (140 material Chemistry VII.E3-9 31 0305 OF) (Internal)

Structural Treated water Loss of Chemistry Program 331- A 36 Tubing iCopper Copper Alloy A > 60 C (140 F) (Internal) material Effectiveness Inspection VII.E3-9 31 0305 Page 3.3-397k Amendment 1 Aging Management Results Review Results Management Review Page 3.3-397k Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate 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 Structural Air-indoor 37 Tubing integrity Copper Alloy uncontrolled None None N/A N/A G (External) 38 Valve Body Structural Steam Loss of BWR Water N/A N/A G integrity Copper Alloy (Internal) material Chemistry Structural Steam Loss of Chemistry Program 39 Valve Body integrity Copper Alloy (Internal) material Effectiveness N/A N/A G Inspection Structural Loss of BWR Water 3.3.1- A 40 Valve Body integrity Copper Alloy > 60 °C (140 material ChemistryVIE3-9 iF) (Internal) 31 0305 Structural Treated water Loss of Chemistry Program 3.3.1- A 41 Valve Body integrity Copper Alloy > 60 °C (140 Effectiveness VII.E3-9 31 0305 iF) (Internal) material Inspection Structural Air-indoor 42 Valve Body integrity Copper Alloy uncontrolled None None N/A N/A G (External) 43 Valve Body Structural Steam Loss of BWR Water N/A N/A G Sintegrity Steel (Internal) material Chemistry Structural Steam Loss of Chemistry Program 44 Valve Body integrity Steel (Internal) material Effectiveness N/A N/A G Inspection 45 Valve Body Structural Steel Steam Loss of Flow-Accelerated N/A N/A G integrity (Internal) material Corrosion (FAC)

Results Page 3.3-3971 Amendment 1 Management Review Aging Management Review Results Page 3.3-3971 Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-46 Aging Management Review Results - Heating Steam Condensate System Aging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801 Table No. Type Function(s) Management Program Volume I Item 2 Item 46 Valve Body Structural integrity Steel Treated 0C water

>4F)60(Internal)

(140 Loss of material BWR Water Chemistry VII.E3-18 3.3.1-17 A 0305 Structural Treated water Loss of Chemistry Program VII.E3- 3.3.1- A 47 Valve Body integrity Steel > 60 0C (140 Effectiveness 18 17 0305 OF) (Internal) material Inspection Structural Air-indoor Loss of External Surfaces 3.3.1-48 Valve Body integrity Steel uncontrolled material Monitoring 58 (External) matrilontoin_5 Amendment 1 Results Review Results Aging Management Review Page 3.3-397m Page 3.3-397m Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.3.2-47 Aging Management Review Results - Heating Steam Vent System Aging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801 Table No. Type Function(s) Management Program Volume I Item 2 Item Air-indoor Structural Stelinc or Loss of 3.3.1-Bolting integrity Steel uncontrolled (External) material maeil4 Bolting Integrity VII.- 43 SrcuaAi-nor Air-indoor Loss of pre- 3.3.1-2 Bolting Structural Steel uncontrolled loss Bolting Integrity VII.I-5 3. B oing integrity (External) load 3 Piping Structural Steel Steam Loss of BWR Water N/A N/A G integrity (Internal) material Chemistry Structural Steam Loss of Chemistry Program 4 Piping Sntegructu Steel Sinternam) LosEffectiveness N/A N/A G integrity S(Internal) material Inspection 5 Structural Steel Steam Loss of Flow-Accelerated N/A N/A G Piping integrity (Internal) material Corrosion (FAC)

Structural Air-indoor Loss of External Surfaces 3.3.1-6 Piping integrity Steel uncontrolled material Monitoring 58 (External) materialMonitoring_58 Page 3.3-397n Amendment 1 Aging Management Review Results Management Review Results Page 3.3-397n Amendment 1

Columbia Generating Station Generic Notes Table 3.3.2-xx 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 on page 3.3-400a Aging Management Review Results Page 3.3-400 Amendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Page 3.3-400 0325 The material is not aluminum alloy > 12% Zinc or 6% Magnesium, which is required for the mechanism of cracking due to stress corrosion cracking to be applicable.

0326 Based on a review of recent operating experience, the bottom portion of the air-handling unit housings for WMA-AH-51A/B are evaluated as exposed to an internal environment of condensation.

0327 No aging effects requiring management have been identified. However, for all brass (copper alloy > 15% Zn) spray nozzles that are in the scope of license renewal, the Fire Water Program is credited to provide confirmation of the absence of significant aging effects during the period of extended operation.

Aging Management Review Results Page 3.3-400a Amendment' i

Columibia Generating Station License Renewal Ap-plication Technical Information 3.4 AGING MANAGEMENT OFSTEAM AND POWER CONVERSION SYSTEMS 3.4.1 Introduction Section 3.4 provides the results of the aging management reviews (AMRs) for, those components identified in Section 2.3.4, Steam and Power Conversion Systems, as subject to AMR. The systems or portions of systems are described in the indicated sections of the Application.

• Auxiliary Steam System (Section 2.3.4.1)

• Condensate (Auxiliary) System (Section 2,3.4.2) o Condensate (Nuclear) System (Section 2.3.4.3)

• Main Steam System (Section 2.3.4.4)

• MainSteam Leakage Control System (Section 2.3.4.5)

• Miscellaneous Drain System (Section 2.3,4.6)

• Reactor Feedwater System (Section 2 .3 .4 .71) lnse-tA fro 'pagei34-a Table 3.4.1, Summary of Aging Management Programs for -Steam and, Power Conversion Systems Evaluated in Chapter VIII of NUREG-1801,. provides the summary of the programs evaluated in NUREG-1801 that are applicable to component and commodity groups in this section, Text addressing summary items requiring further evaluation, is. provided in Section 3.4.2.2.

3.4.2 Results The following tables summarize the results of the AMR for the Steam and Power Conversion Systems.

Table 3.4.2-1 Aging Management Review Results.- Auxiliary Steam System Table 3.4.2-2 Aging Management Review Results - Condensate (Auxiliary) System Table 3.4.2-3 Aging Management Review Results - Condensate (Nuclear) System Table 3.4.2-4 Aging Management Review Results - Main Steam System Table 3.4.2-5 Aging Management Review Results- Main Steam Leakage Control System Table 3.4.2-6 Aging Management Review Results - Miscellaneous Drain System Table 3.4.2-7 Aging Management Review Results - Reactor Feedwater System n<sert B frotm page" 3.4-1 a I Aging Management Review Results Page 3.4-1 -ja*emf "G"4G-

[Amendment 1 _

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section 3.4.1

• Sealing Steam System (Section 2.3.4.8)

Insert B to LRA Section 3.4.2 Table 3.4.2-8 Aging Management Review Results - Sealing Steam System Review Results Page 3.4-la Amendment 1 Aging Management Aging Management Review Results Page 3.4-1 a Amendment 1

Columbia Generating Station License Renewal Application Technical Information

• Chemistry Program Effectiveness Inspection External Surfaces Monitoring Program E

• Flow-Accelerated Corrosion (FAC) Program

• Selective Leaching Inspection 3.4.2.1.2 Condensate (Auxiliary) System Materials The materials of construction for subject mechanical components of the Condensate (Auxiliary) System are:

• Gray cast iron

• Steel Environments Subject mechanical components of the Condensate (Auxiliary) System are exposed to the following normal operating environments:

• Air-indoor uncontrolled

• Air-outdoor

• Treated water > 60 °C (140 oF)

Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Condensate (Auxiliary) System:

• Loss of material

• Loss of pre-load Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Condensate (Auxiliary) System:

• Bolting Integrity Program

• BWR Water Chemistry Program

• Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program ,,--Add: "Supplemental Piping/Tank Inspection" Aging Management Review Results Page 3.4-3 [_2 Amendment 1

eColurnbiaGeneratinrg-Station 3.4.2.1.7 Reactor Feedwater System Licenriw , enewal Application fqTehqhn icallqn6,fomation Aging, Management Programs The following aging management programs manage the aging effects for .the subject mechanicalcomlorponents of the Reactor Feedwater System:

o Bolting Integrity Program BWRWater Chemistry Program' o Chemistry Program Effectiveness. Inspecti*n

. "Inset If ro :page.

new. Sectin4-a" 3.424.i8

.. External Surfaces Mo itoring Prog Iram

• Flow-Accelerated Corrosion (FAC) Program 3.4.2.2 Further Evaluation of Aging Managementas. Recommended by NUREG-1 801 For the-Steam .and Power Coonversion systems, those.items requiring further evaluation a're addressed in the follo~wing sectibns,.

3.4.2.2.1 Cumulative Fatigue Damage Fatigue is a time-limited aging analysis, as defined in 101CFR 5,4.3. Time-limited aging

.analyes are required, to be evaluated in accordance with 1,0 CFR 544.21:(c), Time-limited aging analyses identified for fatigue !in. the Steam and Power Conversion systems areevaluated in Section 4;3.4.

3-.4.22.2 Loss of Material dueAto General, Pitting, and Crevice Corrosion 314,*22.2.1 Pipjng, Piping Components, Piping Elements, Tanks, and Heat Exchangers Lossý of material due to general, pitting, and crevice, corrosion for steel pi0ping components and tanks exposed to treated water (including steam) in the Steam and Power Conversion systems is managed by the BWR Water Chemistry Program. The BWR Water Chemistry Program managesagingeffects through' perdic monitoring, and control of contaminants. The Chemistry Program Effectiveness Inspection will provide, a verification of the effectiveness of the BWR Water Chemistry Program to manage loss of material due to general, pitting, and crevice corrosion through examination of steel piping components and tanks exposed to treated water.

3.,42.2.21'2 Piping, Piping Components, and Piping Elements -Lubricating, Oil As described in Table 3.4.1, there ar no components compared to item number3.4,1-

07. There. are no steel components exposed, to, a lubricating oil environment that- are subject.to AMR for th eiSteam and Power Conversion, systems.

Aging Management RevieW Results Page 3.4-9 -,i.fy.OAWO-jAmendment 1

Columbia Generating Station License Renewal Application Technical Information 3.4.2.1.8 Sealing Steam System Materials The materials of construction for subject mechanical components of the Sealing Steam System are:

• Steel Environments Subject mechanical components of the Sealing Steam System are exposed to the following normal operating environments:

" Air-indoor uncontrolled

• Steam Aging Effects Requiring Management The following aging effects require management for the subject mechanical components of the Sealing Steam System:

• Loss of material Aging Management Programs The following aging management programs manage the aging effects for subject mechanical components of the Sealing Steam System:

• BWR Water Chemistry Program

" Chemistry Program Effectiveness Inspection

• External Surfaces Monitoring Program

" Flow-Accelerated Corrosion (FAC) Program Results Page 3.4-9a Amendment 1 Aging Management Aging Review Results Management Review Page 3.4-9a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.4.1 Summary of Aging Management Programs for Steam and Power Conversion Systems Evaluated in Chapter Vi11 of NUREG-1801 Item IFurther Aging Management Evaluation Discussion Item Aging Effect/

Component/Commodity Mechanism Programs EuRecommended Number 3.4.1-04 Steel piping, piping components, Loss of material due Water Chemistry and Yes, detection of Consistent with NUREG-1 801.

and piping elements exposed to to general, pitting One-Time Inspection aging effects is treated water and crevice to be evaluated The B..R waterel henist.y corrosion Plouylm, in cunjurntian with the Chemistry Programff

,ffotvenessInspeion, i crodited to manmage lass of

.,aterial f. . steel piping, III eampeinents, and piping-elements fing the steamn and power convryeFien systems oexposed to treated w~ater, ineludimg treated water->60-&

Refer to Section 3.4.2.2.2.1 for 7 further information.

Insert A from page 3.4-14a Aging Management Review Results Page 3.4-14 FIAmendmen Am I

>endment

Columbia Generating Station License Renewal Application Technical Information Insert A to Page 3.4.-14 The BWR Water Chemistry Program, in conjunction with the Chemistry Program Effectiveness Inspection, is credited to manage loss of material for steel piping, piping components, piping elements and tanks in the steam and power conversion systems exposed to treated water, including treated water >60 °C (140 OF).

Amendment 1 Management Review Aging Management Results Review Results Page 3.4-14a Page 3.4-14a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.4.2-2 Aging Management Review Results - Condensate (Auxiliary) System Row Component Intended Material Environment 1AgiRequiring ng Effect Aging Management NUREG-1801 Table Notes No. Type Function(s) Management Program Volume 1 Item 2 Item Structural Air-indoor3.4.1-18 Valve Body integrity Steel uncontrolled None None VIII.H-7 3.4.1-28 0406 (External)

Structural Loss of External Surfaces 3.4.1- C 19 Valve Body integrity Steel uncontrolled material MonitoringVIII.H-7 (Internal)

Structural Air-indoor Loss of External Surfaces 3.4.1-20 Valve Body integrity Steel uncontrolled material Monitoring 28 (External)

Add new rows 21 through 25 to Table 3.4.2-2 as shown on pages 3.4-43a Aging Management Review Results Page 3.4-43 r> - jai uary 20 10 iAmendment 1 i

Columbia Generating Station License Renewal Application Technical Information Results 3.4-43a Page 3.4-43a Amendment 1 Aging Review Results Management Review Aging Management Page Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table 3.4.2-3 Aging Management Review Results - Condensate (Nuclear) System Row Component Intended Material Environment TAging Effect Requiring1801 NUREG-Table No. Type Function(s) Management Program Volume I Item 2 Item Structural Stainless Air-indoor 3.4.1-78 Valve Body uncontrolled None None VIII.I-310 41 A 78 V y integrity Steel (External) 41 79 Structural Stainless Condensation Loss of External Surfaces N/A N/A G Valve Body integrity Steel (External) material Monitoring 80 Valve Body Structural Steel Treated water Loss of BWR Water VIII.E-33 3.4.1- A integrity (Internal) material Chemistry 04 Structural Treated water Loss of Chemistry Program 3.4.1- A trt(Internal) material Effectiveness VIII.E-33 04 81 Valve Body integrity (Inspection Structural Air-indoor Loss of External Surfaces 3.4.1-82 Valve Body integrity uncontrolled material Monitoring 28 (External) 83 Valve Body Structural Steel Condensation Loss of External Surfaces VIII.H-10 3.4.1- A integrity (External) material Monitoring 28 Insert new rows 84 through 87 to Table 3.4.2-3 as shown on page 3.4-53a Aging Management Review Results Page 3.4-53 17-7ý0, Jalludly 20 0l j~enment 1 1

Columbia Generating Station License Renewal Application Technical Information Table 3.4.2-3 Aging Management Review Results - Condensate (Nuclear) System Aging Effect Aging NUREG- Table Row Component Intended Aging Magint 1801 1 Notes No. Type Function(s) Material Environment Requiring Management Volume 2 Item Management Program Item Flexible Structural Steel Treated water Loss of BWR Water VIII.E-33 3.4.1- A 84 Connection integrity (Internal) material Chemistry 04 Flexible Structural Steel Treated water Loss of Chemistry VIII.E-33 3.4.1- A 85 Connection integrity (Internal) material Program 04 Effectiveness Inspection Flexible Structural Steel Air-indoor Loss of External VIII.H-7 3.4.1- A 86 Connection integrity uncontrolled material Surfaces 28 (External) Monitoring Flexible Structural Steel Condensation Loss of External VIII.H-10 3.4.1- A 87 Connection integrity (External) material Surfaces 28 Monitoring Page 3.4-53a Amendment 1 Management Review Aging Management Results Review Results Page 3.4-53a Amendment 1

Columbia Generating Station LicenOseRenewal, Application technifcal :Inf6ormatibn Table'3.4.2-72 Aging Management Review Results-Reactor Feedwater System Ai " NUREG-Row Componerit Intendeda Aging Effect Agig Management 1801' ITable-Notes No.Material Environment Requiring Volume..

.Item

-Management Program 2i1me, Treatfed Structural water> 60Cfhemistry Program 34A1- :A 17 tValveuBody w 0Steel mo(140) oatel Effectiveness, VIII.D2-7` 04 0403 (Internal) inspection Treated 18 Valve Body Structural Sewater'> 60. C' Loss lof- Flow-Accelerated I34.1-. A integrity Steel (140,017F) material'. Corrosion (FAC)i ýViILD2; 29 0403

_______ (lritemal) _______ __ _ _ _ _ _ _ _ __ _____

Structural Air-idoor L66ssof, Extfefnal:Su-rfa'ces 3.34*1ý-

19 aveo aveBd Structural integrity Steel ,(Exemal) uncontrolled 'material "L .. e.nal u.

Monitoring VIII.H47 3.41-28 A Cnsert NeW'Table 3.-8frta ge Review Results' Page :3.4-76 Management' _ ew;Results, g_ - ----, kevi Aging -Maina-emerit" Page*3'.4,-7 6

Columbia Generating Station License Renewal Application Technical Information Table 3.4.2-8 Aging Management Review Results - Sealing Steam System Aging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801 Table otes No. Type Function(s) Management Program Volume 1 Item 2 Item 1 Piping Structural Steel Steam Loss of BWR Water VIII.C-4 3.4.1- A integrity (Internal) material Chemistry 02 2 Piping Structural Steel Steam Loss of Chemistry Program VIII.C-4 3.4.1- A integrity (Internal) material Effectiveness 02 Inspection 3 Piping Structural Steel Steam Loss of Flow-Accelerated VIII.C-5 3.4.1- A integrity (Internal) material Corrosion (FAC) 29 4 Piping Structural Steel Air-indoor Loss of External Surfaces VIII.H-7 3.4.1- A integrity uncontrolled material Monitoring 28 (External)

Page 3.4-76a Amendment 1 Aging Review Results Management Review Aging Management Results Page 3.4-76a Amendment 1

Columbia Genefating:ýStatidn Generic Notes Table 3.4.2-xx License Renewal Application Technical Informatiion Plant-Specific Notes:

0404 The'aging effect determination for the Air-indoor Uncontrolled (Internal) enVironment.is the same as-the NUREG-1801" determination for an Air-indoor uncontrolled (Extemal) environmen't because thermaterial is the:same and-the internal environment is equivalent to0the external environment evaluated in the NUREG-1 801 item Monitoring .of'the external-surface Condition Will be used to characterize the ag!ing-effects on .the,internal surfaces.

0405 Bolting -asýsociated with the quencbers is stainloess steel and located-in the suppression pool.

0406 This steel component hasan external surface:temperature.>212- 0F. Theref~re, 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 thetcarbon and low-alloy (steel) bolting at the base and foundationof the, OSTs due .to potential for pondingorrpooling of water..

0408, The:Buried Piping and Tanks-Inspection Program-will manage.loss of materialfor the carbonsteel (steel) pipihg from the CSTs that is enclosed in guard pipe and buried.

0409 The Aboveground Steel Tanks Inspection-will detect and characterize .1ss, of material at~the base of each CST ini-'coritactmwith the.tank foundation.

The aging effect determinationfor the Air-indodruncontrolled (Internal) environment is the same as the*NUREG-1 801 0 determination for an Air-indoor unc~ontrolled (Exte-nal)' environrent becausethematerial is&the same and the internal 0environmentis equivalent to the .external environment evaluated in the NUREG-1801 item There, are no aging effectS requiring management.

The aging effect.determination for:theAir-outdoor (Interna!).environment'is the same as the NUREG-1801 determination for an Air-outdoor(External) environmentý because the material is the same and the internal environment-is equivalent to the external environment evaluated in the NUREG-1 801 item. Monit.oring of the external surface condition willbsed to characterize.the aging effects-on'the i.htemal surfaces.

iAdd:

10412,-T The normal environmentofthe Sealing Steam'System is evaluated as a,;seamenvironment from when the steam evaporator relief valves-are actuated.

A ingMappgemeritReviiBw'Reisýults iPange 3-ýee78 jAmendment

Columbia Generating Station License Renewal Application Technical Information Table 3.5.2-5 Aging Management Review Results - Diesel Generator Building dAging Effect NUREG-Row Component Intended Material Environment Requiring Aging Management 1801 Table I No. Commodity Function' Management Program Volume 2 Item Notes Management__Item Structures Monitoring 10 Roof SRE, SSM Concrete Air-indoor None Program N/A N/A 0501 SRE,_SR_ 0526 Refer to Table 2.0-1 for intended function descriptions.

Add new rows 11 and 12 to Table 3.5.2-5 shown on page 3.5-98a Amendment 1 Aging Management Review Results Page 3.5-98 L

I:

Columbia Generating Station License Renewal Application Technical Information Insert A to pagie 3.5-98 Table 315.2-5 Aging Management Review Results - Diesel Generator Building Aging Effect NUREG-.

Row Component / IntendedAgnEfetNR-Now Commodity/ Function Material Environment Requiring Aging Management 1801 Table 1 Notes Management Program Volume, 2 Item TStructures Management Item _

Monitoring 'I I

11 ISouth Exterior Slab SRE Concrete Air-outdoor None Program N/A N/A 0501 12 SouthExterior Slab SRE

___ Concrete Soil None I Program Structures Monitoring N/A N/A 0501 1

I.

Page 3.5-98a Amendment 1 Aging. Review Results Management Review Aging Management Results Page 3.5-98a Amendment I

Replace this page in its entirety Columbia Generating Station with page 4.3-4a License Renewal Application Technical Information Columbia is analyzed for 120 startups and shutdowns. The 120 startups consist of 117 normal startups and 3 natural circulation startups. The 120 shutdowns consist of 111 nor al shutdowns, 8 single safety or relief valve blowdowns, and 1 rapid depressurization with delayed trip.

~Table 4.3-2 Actual Cycles and Projected Cycles Actual cycles 12/13/1984 60 year Cycles for Analyzed throughh (12/13/2044) future Conditions cycles 7/31/200Y projection(3) analyses(4)

Boltup/Unbolt 123 21 55 60 Reactor Startup (100 degF/hr) \ 120 /8 233 250 Reactor Shutdown (100 degF/hr) 111 87 230 242 Vessel Pressure Tests 130 2(1 2) 2(1) 60 Loss of Feedwater Heaters 0 0 0 80 Scram - Loss of feedwater pumps, 1 7 18 20 isolation valves closed A Scram - Single safety relief valve 8 0 0 8 blowdown Scram - TG trip, FW on, isolation 40 \\2 58 60 valves open /'

Scram -Other /140 34 90 90 LPCS operation 10 0 0 10 HPCS operation 10 4 10 104 LPCI operation - 10 0 0 10 SLC operation 10 0 10 (1) Vessel drostatic pressure tests are no longer performed. Vessel operatio I leak t ts have replaced the hydrostatic pressure tests.

(2) The'e two pressure tests were hydrostatic pressure tests.

(3) Pr jections were not changed for those events that have not occurred.

(4) e 20 Scrams with Loss of Feedwater assume 3 HPCS injections per scram.

The HPCS initiation assumes 10 additional injections without a scram. The HPCS nozzle is analyzed for 70 cycles combined from the two events.

Time-Limited Aging Analyses Page 4.3-4 "danurx"e 2A-JAmendment 1

Columbia Generating Station License Renewal Application Technical Information Columbia is analyzed for 120 startups and shutdowns. The 120 startups consist of 117 normal startups and 3 natural circulation startups. The 120 shutdowns consist of 111 normal shutdowns, 8 single safety or relief valve blowdowns, and 1 rapid depressurization with delayed trip.

Table 4.3-2 Actual Cycles and Projected Cycles Actual cycles 12/13/1984 60 year Cycles for Analyzed through (12/1312044) future Conditions cycles 2/16/2010 projection(1 ) analyses Boltup/Unbolt 123 23 54 60 Reactor Startup (100 degF/hr) 120 94 224 250 Reactor Shutdown (100 degF/hr) 111 93 221 250 Vessel Pressure Tests 130 23 54 65 Loss of Feedwater Heaters 80 0 0 80 Scram - Loss of feedwater pumps, 10 7 16 20 isolation valves closed Scram - Single safety relief valve 8 1 2 8 blowdown Scram - TG trip, FW on, isolation 40 23 54 60 valves open Scram - HPCS Injection 30 12 28 602 Scram - Other 140 39 92 90 LPCS operation 10 0 0 10 HPCS operation 10 3 7 102 LPCI operation 10 0 0 10 SLC operation 10 0 0 10 (1) Projections were not changed for those events that have not occurred.

(2) Total HPCS injection cycles from scrams (60) and non-scrams (10) should not exceed 70.

Page 4.3-4a Amendment 1 Aging Analyses Time-Limited Aging Time-Limited Analyses Page 4.3-4a Amendment I

Columbia Generating Station License Renewal Application Technical Information A.1.2.4 Bolting Integrity Program The Bolting Integrity Program is a combination of existing activities that, in conjunction with other credited programs, address the management of aging for the bolting of mechanical components and structural connections within the scope of license renewal.

The Bolting Integrity Program relies on manufacturer and vendor information and industry recommendations for the proper selection, assembly, and maintenance of bolting for pressure-retaining closures and structural connections. The Bolting Integrity Program includes, through the Inservice Inspection (ISI) Program, Inservice Inspection (ISI) Program - IWF, Structures Monitoring Program, and External Surfaces Monitoring Program, the periodic inspection of bolting for indications of degradation such as leakage, loss of material due to corrosion, loss of pre-load, and cracking due to stress corrosion cracking (SCC) and fatigue. I ,+A, AI +, v+*, ,it A.1.2.5 Buried Piping and Tanks Inspection Program P Insert A on page A-9a The Burned Piping and Tamits Inspeetion Program manages the effects of less of material due to corroSiO n the extU--1 i ia lace of pipin and tanks exposd to a buried environment. The Buried Piping and Tanks Inspection Program is a combination of a mitigation program (consisting of protective coatings) and a condition monitoring program (consisting of visual inspections).

An inspection of buried piping will be performed within the 10-year period prior to entering the period of extended operation. An additional inspection of buried piping will be performed within 10 years after entering the period of extended operation.

The Buried Piping and Tanks Inspection Program is an existing program that requires enhancement prior to the period of extended operation.

A.1.2.6 BWR Feedwater Nozzle Program The BWR Feedwater Nozzle Program is an existing program that manages cracking due to stress corrosion cracking and intergranular attack (SCC/IGA) and flaw growth of the feedwater nozzles. The BWR Feedwater Nozzle Program is in accordance with ASME Section XI and NRC augmented requirements.

The BWR Feedwater Nozzle Program consists of: (a) enhanced inservice inspection in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWB, Table IWB 2500-1 (2001 edition including the 2002 and 2003 Addenda) and the recommendations of General Electric report NE-523-A71-0594-A [Reference A.1.4-1], and (b) system modifications, as described in FSAR Section 5.3.3.1.4.5, to mitigate cracking. The program specifies periodic ultrasonic inspection of critical regions of the feedwater nozzles.

Final Safety Analysis Report Supplement Page A-9 da i mry720tf1 AendmntZ

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section A.1.2.5 The Buried Piping and Tanks Inspection Program manages the effects of loss of material due to corrosion on the external surfaces of piping, piping components and tanks exposed to a buried environment. The program also manages the effects of cracking, loss of material and loss of pre-load for bolting exposed to a buried environment.

Page A-9a Amendment 1 Final Safety Analysis Final Safety Report Supplement Analysis Report Supplement Page A-9a Amendment 1

Columbia Generating Station License Renewal Application Technical Information A.1.2.15 CRDRL Nozzle Program The CRDRL Nozzle Program is an existing mitigation and condition monitoring program that manages cracking due to flaw growth of the control rod drive return line (CRDRL) nozzle, safe end, cap, and connecting welds. The CRDRL Nozzle Program consists of a) mitigation activities, and b) inspection, flaw evaluation, and repair in accordance with the ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWB, Table IWB 2500-1 (2001 Edition through 2003 Addenda) and the recommendations of NUREG-0619. System modifications were implemented by the original equipment manufacturer prior to initial startup to mitigate cracking. The BWR Water Chemistry Program monitors and controls reactor coolant water chemistry in accordance with BWRVIP guidelines to ensure the long-term integrity and safe operation of the critical regions of the CRDRL nozzle.

The CRDRL Nozzle Program credits portions of the Inservice Inspection (ISI) Program.

A.1.2.16 Diesel Starting Air Inspection The Diesel Starting Air Inspection detects and characterizes the condition of materials for the DSA System air dryers and downstream piping and components (excluding the DSA System air receivers). The inspection provides direct evidence as to whether, and to what extent, a loss of material due to corrosion has occurred.

The Diesel Starting Air Inspection is a new one-time inspection that will be implemented prior to the period of extended operation. The inspection activities will be conducted within the 10-year period prior to the period of extended operation.

A.1.2.17 Diesel Systems Inspection The Diesel Systems Inspection detects and characterizes the condition of materials for the interior of the exhaust piping for the Division 1, 2, and 3 diesels in the Diesel Engine Exhaust System, including the loop seal drains from the exhaust piping, and the drain Pons and drain pipi I nl a Loateu WILI I U -handling units ftheDiesel DuidiII IJ II-'A systems. The inspection provides direct evidence as to whether, and to what extent, a loss of material due to corrosion has occurred.

The Diesel Systems Inspection is a new one-time inspection that will be implemented prior to the period of extended operation. The inspection activities will be conducted within the 10-year period prior to the period of extended operation.

A.1.2.18 Diesel-Driven Fire Pumps Inspection The Diesel-Driven Fire Pumps Inspection detects and characterizes the material condition of the interior of the Fire Protection System diesel engine exhaust piping, and of Fire Protection System diesel heat exchangers exposed to a raw water environment.

Final Safety Analysis Report Supplement Page A-1 3 jAmendment 1

Columbia Generating Station License Renewal Application Technical Information A.1.2.37 Lubricating Oil Inspection The Lubricating Oil Inspection detects and characterizes the condition of materials in systems and components for which the Lubricating Oil Analysis Program is credited with aging management. The inspection provides direct evidence as to whether, and to what extent, a loss of material due to corrosion or selective leaching has occurred. The inspection also determines whether a reduction in heat transfer due to fouling has occurred.

The Lubricating Oil Inspection is a new one-time inspection that will be implemented prior to the period of extended operation. The inspection activities will be conducted within the 10-year period prior to the period of extended operation.

A.1.2.38 Masonry Wall Inspection The Masonry Wall Inspection consists of inspection activities to detect cracking of masonry walls within the scope of license renewal. Masonry walls that perform a fire barrier intended function are also managed by the Fire Protection Program. The Masonry Wall Inspection is implemented as part of the Structures Monitoring Program.

The Masonry Wall Inspection performs visual inspection of external surfaces of masonry walls.

The Masonry Wall Inspection is an existing program that requires enhancement prior to the period of extended operation.

A.1.2.39 Material Handling System Inspection Program The Material Handling System Inspection Program manages loss of material for cranes (including bridge, trolley, rails, and girders), monorails, and hoists within the scope of license renewal. The Material Handling System Inspection Program is based on guidance contained in ANSI B30.2 for overhead and gantry cranes, ANSI B30.11 for monorail systems and underhung cranes, and ANSI B30.16 for overhead hoists.

ThU*,a,, id,,n Ispe.ti. Pr,,gra, is an . prgrFam that rcquircs

,xisting enhacement prior to the period of extended operation.

A.1.2.40 Metal-Enclosed Bus Program The Metal-Enclosed Bus Program is an inspection program that detects degradation of metal-enclosed bus within the scope of license renewal. The program provides for the visual inspection of interior sections of bus, and an inspection of the elastomeric seals at the joints of the duct sections. The program also makes provision for thermographic inspection of bus bolted connections.

[Amendment 1 Final Safety Analysis Report Supplement Page A-21 january 201-9

Columbia Generating Station License Renewal Application Technical Information The Metal-Enclosed Bus Program is a new aging management program that will be implemented prior to the period of extended operation. The thermography portion of the program will be performed once every 10 years, with the initial inspections to be performed prior to the period of extended operation. The visual inspection portion of the program will also be performed once every 10 years, with the first inspections to be performed prior to the period of extended operation.

A.1.2.41 Monitoring and Collection Systems Inspection The Monitoring and Collection Systems Inspection detects and characterizes the condition of materials at the internal surfaces of subject mechanical components that are exposed to equipment or area drainage water and other potential contaminants and fluids. The inspection provides direct evidence as to whether, and to what extent, a loss of material due to corrosion or erosion has occurred. The inspection also determines whether cracking due to SCC of susceptible materials has occurred.

The Monitoring and Collection Systems Inspection is a new one-time inspection that will be implemented prior to the period of extended operation. The inspection activities will be conducted within the 10-year period prior to the period of extended operation.

A.1.2.42 Open-Cycle Cooling Water Program The Open-Cycle Cooling Water Program manages .racking due to SCC Of suveptibl, mater*s's and loss of material due to corrosion and erosion for components located in the Standby Service Water and Plant Service Water systems, and for components connected to or serviced by those systems. The program manages fouling due to particulates (e.g., corrosion products) and biological material (micro- or macro-organisms) resulting in reduction in heat transfer for heat exchangers (including condensers, coolers, cooling coils, and evaporators) within the scope of the program.

The Open-Cycle Cooling Water Program also manages loss of material for components associated with the feed-and-bleed mode for emergency makeup water to the spray pond.

The Open-Cycle Cooling Water Program consists of inspections, surveillances, and Insert:

testing to detect the presence, and assess the extent of reFackkg, foWuI!g, nd loss of "fouling" material. The inspection activities are combined with chemical treatments and cleaning activities to minimize the effects of aging. The program is a combination condition monitoring and mitigation program that implements the recommendations of NRC Generic Letter 89-13 for safety-related equipment in the scope of the program. The scope of the program also includes non-safety related components containing either service water or spray pond makeup water.

The Open-Cycle Cooling Water Program is an existing program that requires enhancement prior to the period of extended operation.

Final Safety Analysis Report Supplement Page A-22 Jwnuary 2010 IAmendment 1 II

Columbia Generating Station License Renewal Application Technical Information Table A-1 Columbia License Renewal Commitments FSAR Enhancement Commitment Supplement or Item Number Location Implementation (LRA App. A) Schedule

5) Buried Piping The Buried Piping and Tanks Inspection Program is an existing A.1.2.5 Enhancement and Tanks program that will be continued for the period of extended operation, prior to the period Inspection with the following enhancements: of extended Program

• Revise the site program document to include the buried portions operation.

of the Radwaste Building Outside Air. (WOA) piping. Then ongoing.

0 Require that an inspection of a representative sample of buried I piping be performed within the 10-year period prior to entering the Add Insert A period of extended operation (i.e., between year 30 and year 40). from page

• Require an additional inspection of a representative sample of A-43a buried piping be performed within 10 years after entering the period of extended operation (i.e., between year 40 and year 50).

6) BWR The BWR Feedwater Nozzle Program is an existing program that will A.1.2.6 Ongoing Feedwater be continued for the period of extended operation.

Nozzle Program

7) BWR The BWR Penetrations Program is an existing program that will be A.1.2.7 Ongoing Penetrations continued for the period of extended operation.

Program

8) BWR Stress The BWR Stress Corrosion Cracking Program is an existing program A.1.2.8 Ongoing Corrosion that will be continued for the period of extended operation.

Cracking Program Final Safety Analysis Report Supplement Page A-43 Januar/y2010 jAmendment 1 Z"

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Table A-1 Item Number 5

" Revise the site program document to include cracking, loss of material and loss of pre-load of bolting as aging effects managed by the program.

• Revise the site program document to include loss of material of stainless steel piping and piping components as an aging effect managed by the program.

Page A-43a Amendment 1 Final Safety Report Supplement Analysis Report Safety Analysis Supplement Page A-43a Amendment 1

Columbia Generating Station License Renewal Application Technical Information Table A-1 Columbia License Renewal Commitments FSAR Enhancement Item Number Commitment Supplement or Location Implementation (LRA App. A) Schedule

16) Diesel Starting The Diesel Starting Air Inspection is a new activity. A.1.2.16 Within the 10-Air Inspection The Diesel Starting Air Inspection detects and characterizes the year period prior condition of materials for the DSA System air dryers and downstream to the period of piping and components (excluding the DSA System air receivers), extended The inspection provides direct evidence as to whether, and to what operation.

extent, the relevant effects of aging have occurred.

17) Diesel Systems The Diesel Systems Inspection is a new activity. A.1.2.17 Within the 10-Inspection The Diesel Systems Inspection detects and characterizes the year period prior condition of materials for the interior of the exhaust piping for the to the period of Division 1, 2, and 3 diesels in the Diesel Engine Exhaust System, extended including the loop seal drains from the exhaust piping,, ,a,4he 4 fa,, operation.

pans and drai. p..ipi .... oiated with air handling units of the Diesel Buildg I,'VAG systems. The inspection provides direct evidence as to whether, and to what extent, the relevant effects of aging have occurred.

18) Diesel-Driven The Diesel-Driven Fire Pumps Inspection is a new activity. A.1.2.18 Within the 10-Fire Pumps The Diesel-Driven Fire Pumps Inspection detects and characterizes year period prior Inspection the material condition of the interior of the Fire Protection System to the period of diesel engine exhaust piping, and of Fire Protection System diesel extended heat exchangers exposed to a raw water environment. The operation.

inspection provides direct evidence as to whether, and to what extent, the relevant effects of aging have-occurred.

Final Safety Analysis Report Supplement Page A-46 January 2010 jAmendment 1

Satio Gneratng Col~mia Columhbia Generating. Station License Renewal Application Technical Information Table A-I Columbia License Renewal Commitments FSAR Enhancement Item Number Commitment Supplement or Location Implementation (LRA App. A) Schedule

23) External The External Surfaces Monitoring Program is anexisting program A.1.2.23 Enhancement Surfaces that will be continued for the period of extended operation, with the prior to the period Monitoring following enhancements: of extended Program

• Add aluminum, copper alloy, copper alloy >15% Zn, gray cast operation.

iron, stainless steel (including CASS), and. elastomers to the Then ongoing.

scope of the program.

• Add cracking as an aging effect for raluminum.,-,nd c.iRness ste*l components.

a Add visual (VT-1 or equivalent) or volumetric examination techniques-to detect cracking.

a Add hardening and loss of strength as aging'effects for elastomer-based mechanical sealants and flexible connections in HVAC systems.

e Add physical examination techniques in addition to visual inspection-to detect hardening and loss of strength for elastomer-based mechanical sealants and flexible connections in HVAC systems.

24) Fatigue The Fatigue, Monitoring Program isan S existing program that will be AX1!.2.24 Enhancement Monitoring continued for the period of extended operation, with the following A.1.3.2 prior to the period Program enhancements: A..1-3.4 of extended operation.

Then ongoing.

Final Safety Analysis Report Supplement Page A-49 FAmendment 1

Columbia Generating Station License Renewal Application Technical Information Table A-1 Columbia License Renewal Commitments FSAR Enhancement Item Number Commitment Supplement or Location Implementation (LRA App. A) Schedule

38) Masonry Wall The Masonry Wall Inspection is an existing program that will be A.1.2.38 Enhancement Inspection continued for the period of extended operation, with the following prior to the period enhancements: of extended Specify that for each masonry wall, the extent of observed operation.

masonry cracking or degradation of steel edge supports and Then geifng.

bracing are evaluated to ensure that the current evaluation basis is still valid. Corrective action is required ifthe extent of masonry cracking or steel degradation is sufficient to invalidate the iongoing evaluation basis. An option is to develop a new evaluation basis that accounts for the degraded condition of the wall (i.e.,

acceptance by further evaluation).

39) Material The Material Handling System Inspection Program is an existing A.1.2.39 Enhahe eemnt 1

Handling program that will be continued for the period of extended operation- ,,uI to t,!Mpet-d System with the f,,l.w.ng enhane.. . .t. of-exte',ied-Inspection E ...s,- .... a.d ..........lly elctric t..d... operation.

Program inspocted for -orroesion. T-hen ongoing.

Amnment 1 Final Safety Analysis Report Supplement Page A-56 januaFy 2010

Columbia Generating Station License Renewal Application Technical Information Table B-2 Consistency of Columbia Aging Management Programs with NUREG-1801 (continued)

Consistent New / Plant- Enhancement Program Name Ewith NUREG- NUREG- Required Existing 1801 1801 with Specific Exceptions Inservice Inspection (ISI) Program - IWF Existing Yes Section B.2.35 Lubricating Oil Analysis Program Existing Yes Yes Section B.2.36 Lubricating Oil Inspection New Yes Section B.2.37 Masonry Wall Inspection Existing Yes Yes Section B.2.38 Material Handling System Inspection Existing Yes --Ye-Program Section B.2.39 Metal-Enclosed Bus Program New Yes Section B.2.40 Monitoring and Collection Systems New Yes Inspection Section B.2.41 Open-Cycle Cooling Water Program Existing Yes Yes Section B.2.42 Potable Water Monitoring Program Existing Yes Yes Section B.2.43 jAmendment 1 Agin Mangemet Pogras Pae B23 J~L1:1_4 Aging Management Programs Page B-23 jaRUaFy 2

B.2.3 Appendix J Program Columbia Generating Station Renewal Application LicenseTechnical Information Type B and C leakage rate test results from the 2007 Refueling Outage (R18) are summarized in the local leak rate test post outage report. The R18 local leak rate test involved ninety-one Type B and C air tests. Twenty-five Type B tests were conducted, including the personnel airlock barrel test. All Type B as found leak rates were below their administrative limits with the exception of the containment-side flange (CEP-V-2A),

which had a leak rate exceeding its administrative limit. This flange was checked using a soap solution with test pressure applied and showed no external leakage. This visual inspection confirmed that the leakage recorded was into the system rather than a breach of the containment penetration. Sixty-six Type C tests were conducted. All but eight valves had as found leak rates below their administrative limits. The valves with leak rates in excess of their administrative limit required corrective actions to reduce their leak rates. Of the eight valves with as found leak rates in excess of their administrative limits, five required disassembly and rework, and one valve was replaced. The remaining two valves were successfully flushed and as-left tested without disassembly.

The total as found leakage at the beginning of Refueling Outage 19 (R19) was 19,712 standard cubic centimeters per minute (sccm). This equates to 16.2 percent of the total allowable containment leakage (La) of 121,536 sccm. The values from previous refueling outages (R18) and (R17) were 13,683 sccm and 20,879 sccm respectively.

The total as left leakage at the end of R19 was 13,098 sccm. This equates to 10.8 percent of the total allowable containment leakage (La) of 121,536 sccm and well below the maximum allowable startup containment leakage rate of 0.6La. The values from the previous refueling outages (R18) and (R17) were 14,051 sccm and 17,423 sccm, respectively.

The results of previous Type A tests are shown below. No Type A tests have failed to meet their acceptance criteria at Columbia.

Total Leakage Acceptance Limit (percent) (percent) 02/16/1984 0.2758 0.50 06/17/1987 0.3241 0.50 06/09/1991 0.319 0.50 07/20/1994 0.330 0.50 06/14/2009 0.3418 0.50 The health of the Appendix J Program is reported periodically in terms of performance indicators. The program health reports for 2007,.Rd 2008 indicated no age-related concerns for systems and components within th ope of the Appendix J Program.

to 2009 Amendment 17 AgngMnaeen rormsPgeB35Ji~~-I4 Aging Management Programs Page B-35

Columbia Generating Station License Renewal Application Technical Information B.2.5 Buried Piping and Tanks Inspection Program Program Description The Buried Piping and ',,.,"Ta-icorns iW-g P-uysd ill

.w,,IIcdIi--,,,

manage e[

eubo ut uI

.......... d maerial corrosion on the ext l ,,-,-,.s of piping and tanks exposed to a burid Replace with Insert A on page B-39a The Buried Piping and Tanks Inspection Program is a combination of a mitigation program (consisting of protective coatings) and a condition' monitoring program (consisting of visual inspections). Integrity of coatings will be inspected when components are excavated for maintenance or other reasons. If an opportunistic inspection has not occurred between year 30 and year 38, an excavation of a section of buried piping for the purpose of inspection will be performed before year 40. An additional inspection of buried piping will be performed within 10 years after entering the period of extended operation.

The Buried Piping and Tanks Inspection Program will continue to ensure that the pressure boundary integrity of the subject components is maintained consistent with the current licensing basis during the period of extended operation.

NUREG-1801 Consistency The Buried Piping and Tanks Inspection Program is an existing Columbia program that, with enhancement, will be consistent with the 10 elements of an effective aging management program as described in NUREG-1801,Section XI.M34, "Buried Piping and Tanks Inspection."

Exceptions to NUREG-1801 None.

Required Enhancements Prior to the period of extended operation the enhancements listed below will be implemented in the identified program element:

• Scope of Program-Revise the site program document to include the buried portions of the Radwaste Building Outside Air (WOA) piping.

Add Insert B on page B-39a Aging Management Programs Page B-39 -Jef'taryy 2816

[Amendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section B.2.5, page B-39 The Buried Piping and Tanks Inspection Program will manage the effects of loss of material due to corrosion on the external surfaces of piping, piping components and tanks exposed to a buried environment. The program also manages cracking, loss of material and loss of pre-load for bolting exposed to a buried environment.

Insert B to LRA Section B.2.5, page B-39 Revise the site program document to include cracking, loss of material and loss of pre-load of bolting as aging effects managed by the program.

Revise the site program document to include loss of material of stainless steel piping and piping components as an aging effect managed by the program.

Page B-39a Amendment 1 Management Programs Aging Management Aging Programs Page B-39a Amendment 1

Columbia Generating Station B.2.5 Buried Piping and Tanks Inspection Program License Renewal Application Technical Information

• Detection of Aging Effects -

Require that an inspection of a representative sample of buried piping be performed within the 10-year period prior to entering the period of extended operation (i.e., between year 30 and year 40).

Require an additional inspection of a representative sample of buried piping be performed within 10 years after entering the period of extended operation (i.e.,

between year 40 and year 50).

Operating Experience No history of piping degradation due to external corrosion of buried piping was identified for Columbia through searches of operating experience or discussions with program owners. Columbia operating experience demonstrates that the coating of buried steel piping and tanks is effective in managing the effects of aging. Plant design considerations addressed the potential for degradation of buried piping components through the application of protective coatings.

A review was conducted of station piping failures, and it was determined that there had been no documented failures attributed to externally-initiated corrosion. Identified instances of leakage associated with buried piping have been the result of internal corrosion.

The environmental conditions at Columbia are very good based on the sandy soil and electrolyte resistivity of the soil which is considered very high. This has resulted in minimal degradation of buried piping as evidenced by excavations of certain sections of piping for examination. There have been no significant areas of degradation caused by protective coating failure. This was determined after a section of buried Standby Service Water (SW) System piping was excavated and evaluated in 2007.

Conclusion Replace with Insert A on Page B-40a The Bu r ied Piping and Tanks -ispecton-ProradiVwii miianiage loss f niIateia l due to corrnsion for susceptible piping compon.nt. a n in bu*rid Invironm..ts.

The Buried Piping and Tanks Inspection Program, with the required enhancements, provides reasonable assurance that the aging effects will be managed such that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Aging Management Programs Page B-40 -- aJefwny-2+0--

TAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A to LRA Section B.2.5, page B-40 The Buried Piping and Tanks Inspection Program will manage cracking and loss of pre-load of bolting and loss of material due to corrosion for susceptible bolting, piping, piping components and tanks in buried environments.

Amendment 1 Management Programs Aging Management Programs Page B-40a Page B-40a Amendment 1

Columbia Generating Station B.2.14 Cooling Units Inspection License Renewal Application Technical Information experience (e.g., time in-service, most susceptible locations, lowest design margins).

Inspection findings that do not meet the acceptance criteria will be evaluated using the Columbia corrective action process to determine the need for subsequent aging management activities and for monitoring and trending of the results.

Acceptance Criteria Indications or relevant conditions of degradation detected during the inspections will be compared to pre-determined acceptance criteria. If the acceptance criteria are not met, then the indications and conditions will be evaluated under the corrective action program to determine whether they could result in a loss of component intended function during the period of extended operation.

• Corrective Actions This element is common to Columbia programs and activities that are credited with aging management during the period of extended operation and is discussed in Section B.1.3.

• Confirmation Process This element is common to Columbia programs and activities that are credited with aging management during the period of extended operation and is discussed in Section B.1.3.

• Administrative Controls This element is common to Columbia programs and activities that are credited with aging management during the period of extended operation and is discussed in Section B.1.3.

Operating Experience The Cooling Units Inspection is a new one-time inspection activity for which plant operating experience has not shown the occurrence of the aforementioned aging effects. The inspection provides for confirmation of material conditions near the period of extended operation. The elements comprising the inspection activity are to be consistent with industry practice.

NUREG-1801 is based on industry operating experience through January 2005.

Recent industry operating experience has been reviewed for applicability; none was identified. Future operating experience is captured through the normal operating experience review process, which will continue through the period of extended operation.

A review of Columbia operating experience, documented in recent work orders, revealed that cooling unit coils have been found clean and no leakage was observed. *"*-Add!nsetA r~mPage B-68ai Aging Mahagement Programs Page B-68 jai lucy2i j~mentmell1 P

License Renewal Application Technical Information Insert A to LRA Section B.2.14, page B-68 In addition, water was found to be dripping from duct downstream of Control Room Division 1 air handling unit WMA-AH-51A in. June, of 2009. This was determined to be from condensation that collected in a depression in the bottom of the air handling unit housing. Water was removed from the bottom of the housing and similar air handling units were inspected and confirmed to be self-draining properly. No corrosion of the air unit housing was identified during the removal and inspection.

Amendment 1 Management Programs Aging Management Programs Page B-68a Page B-68a Amendment 1

Columbia Generating Station License Renewal Application Technical Information B.2.17 Diesel Systems Inspection Program Description The Diesel Systems Inspection is a new one-time inspection that will detect and characterize the material condition of the interior of the exhaust piping for the Division 1, 2, and 3 diesels in the Diesel Engine Exhaust System, including the loop seal drains from the exhaust piping, and the drain pans and drain p.ping a..i. ated with air hndling un.its of the ,Die-el Building H.. A^ system . The inspection provides direct evidence as to whether, and to what extent, a loss of material due to corrosion has occurred or is likely to occur.

Implementation of the Diesel Systems Inspection will provide confirmation that the integrity of the subject components will be maintained consistent with the current licensing basis during the period of extended operation.

NUREG-1801 Consistency The Diesel Systems Inspection is a new one-time inspection for Columbia that will be consistent with the 10 elements of an effective aging management program as described in NUREG-1801,Section XI.M32, "One-Time Inspection."

Exceptions to NUREG-1801 None.

Aging Management Program Elements The results of an evaluation of each program element are provided below.

Scope of Program The scope of the Diesel Systems Inspection includes the steel exhaust piping exposed to an air-outdoor environment, and the loop seal drains from the exhaust piping that are exposed to a raw water environment, for the following diesel engines:

• DG-ENG-1A1/1A2

• DG-ENG-1B1/1B2

• DG-ENG-1C

• DSA-ENG-C/2C

,AdditiGnally the stainless steel drain pans and steel dramin piping exposed to a raw water environment and essociated with ,p_ the *,.

follo...,e ent are i pe-e the Diesel Systems Inspection:;

Aging Management Programs Page B-77 January-*20108

[Amendment

Columbia Generating Station License Renewal Application Technical Information IlDMA AH 11, 12, 21, 22, 31, 32, and 51 (air handling unit hIusings)

" Preventive Actions No actions are taken as part of the Diesel Systems Inspection to prevent aging effects or to mitigate aging degradation.

• Parameters Monitored or Inspected The parameters to be inspected by the Diesel Systems Inspection include wall thickness or visual evidence of internal surface degradation,_ of the diesel exhaust piping and the drain pan. and drainl pipiRg as measures of loss of material.

Inspections will be performed by qualified personnel using established NDE techniques (i.e., ultrasonic examination). Visual inspection of the internals for evidence of corrosion and corrosion products may be performed as opportunities for access arise.

" Detection of Aging Effects The Diesel Systems Inspection will use a combination of established volumetric and visual examination techniques (such as equivalent to VT-1 or VT-3) performed by qualified personnel on a representative sample of the subject components to identify evidence of loss of material.

The sample population will be determined by engineering evaluation based on sound statistical sampling methodology, and, where practical, will be focused on the components most susceptible to aging, such as due to their time in service, the severity of conditions during normal plant operations, and design margins.

The Diesel Systems Inspection will be conducted after the issuance of the renewed license and prior to the end of the current operating license, with sufficient time to implement programmatic oversight for the period of extended operation. The activities will be conducted no earlier than 10 years prior to the end of the current operating license, so that conditions are more representative of the conditions expected during the period of extended operation.

" Monitoring and Trending This one-time inspection activity is used to characterize conditions and to determine if, and to what extent, further actions may be required. The activity includes provisions for increasing the inspection sample size and locations if degradation is detected.

The sample size will be determined by engineering evaluation of the materials of construction, the environment (i.e., service conditions), aging effects, and operating experience (e.g., time in-service, susceptible locations, lowest design margins).

Inspection findings that do not meet the acceptance criteria will be evaluated using Aging Management Programs Page B-78 J..u..y 2010 JAmendment 1

Columbia Generating Station License Renewal Application Technical Information B.2.23 External Surfaces Monitoring Program Program Description The External Surfaces Monitoring Program will manage the following aging effects for the external surfaces, and in some cases the internal surfaces, of mechanical components within the scope of license renewal:

Loss of material for metals (aluminum, copper alloy, copper alloy > 15% Zh, gray cast iron, -stainless steel (including CASS), and steel) that are exposed to condensation, air-indoor uncontrolled, and air-outdoor environments

, Cracking of aluminum and tn .s.eexposed to condensation environments

• Hardening and loss of strength for elastomer-based mechanical sealants and flexible connections in HVAC systems The External Surfaces Monitoring Program is a condition monitoring program that consists of visual inspections and surveillance activities of accessible external surfaces on a frequency 'that generally exceeds once per fuel cycle. Surfaces that are inaccessible during normal plant operation are inspected during refueling outages.

Surfaces that are inaccessible or not readily visible during both plant operations and refueling outages, such as surfaces that are insulated, are inspected opportunistically, for example during maintenance activities during which insulation is removed.

The External Surfaces Monitoring Program is supplemented by the Aboveground Steel Tanks Inspection to manage loss of material for the inaccessible external surfaces of the carbon steel condensate storage tanks (i.e., the tank bottom).

NUREG-1801 Consistency The External Surfaces Monitoring Program is an existing Columbia program that, with enhancement, will be consistent with the 10 elements of an effective aging management program as described in NUREG-1801,Section XI.M36, "External Surfaces Monitoring."

Exceptions to NUREG-1801 None.

Required Enhancements Prior to the period of extended operation the enhancements listed below will be implemented in the identified program element:

Aging Management Programs Page B-101 Ja,.uary 2610 jAmendment 1

Columbia Generating Station License Renewal Application Technical Information

• Scope of Program -

" Add aluminum, copper alloy, copper alloy >15% Zn, gray cast iron, stainless steel (including CASS), and elastomers to the scope of the program.

• Add cracking as an aging effect for aluminum

. .and .+ileSC, -- c, components.

• Add hardening and loss of strength as aging effects for elastomer-based mechanical sealants and flexible connections in HVAC systems.

e Monitoring and Trending -

• Add physical examination techniques in addition to visual inspection to detect hardening and loss of strength for elastomer-based mechanical sealants and flexible connections in HVAC systems.

• Add visual (VT-1 or equivalent) or volumetric examination techniques to detect cracking.

Operating Experience The elements that comprise the External Surfaces Monitoring Program are consistent with industry practice and have proven effective in maintaining the material condition of Columbia plant systems and components.

A review of the most recent plant-specific operating experience, through a search of condition reports, revealed that minor component leakage (typically at bolted joints and closures), damage (event-driven, not age-related), and degradation are routinely identified by the External Surfaces Monitoring Program, with subsequent corrective actions taken in a timely manner; and that no loss of pressure boundary integrity has occurred that was, or could have been, attributed to the aging effects that are in the scope of the program.

Operating experience associated with the External Surfaces Monitoring Program is routinely documented and communicated to site personnel in System Health Reports.

System Health Reports are updated after significant changes, or at least quarterly.

Aging Management Programs Page B-102', .......--040-JAmendment 1

Columbia Generating Station License Renewal Application Technical Information Conclusion The External Surfaces Monitoring Program will detect and manage loss of material for aluminum, copper alloy, copper alloy >15% Zn, gray cast iron, stainless steel (including CASS), and steel components. The continued implementation of the External Surfaces Monitoring Program, with the required enhancements, provides reasonable assurance that the effects of aging, including cracking for aluminum aid staiMes- .tc--

components and hardening and loss of' strength for elastomer-based mechanical sealants and flexible connections in HVAC systems, will be managed such that components subject to aging management will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Aging Management Programs Page B-I 03 -jae~ey 294G-

[Amendment 1

B.2.28 Flow-Accelerated Corrosion (FAC) Program Columbia Generating Station License Renewal Application Technical Information periodically reported, including material conditions. Industry operating experience has been, and continues to be, evaluated for impact to Columbia and for possible program enhancement. For example, based on review of INPO operating experience 14865, the program was enhanced to require evaluation of replacements for future inspection.

Periodic self assessments are also conducted. Gaps identified during the most recent self assessment have all been closed; and the FAC program plan was Fecently updated, with the ebrent revision addressing all issues identified by the self assessment. In the last benchmark assessment, performed in March 2007, no issues or weaknesses were identified.

As a result, Columbia has programs and procedures in place, with operating experience demonstrating that the FAC Program is capable of detecting and managing loss of material due to FAC for susceptible components, and will continue to be an effective aging management program for the period of extended operation.

A review of program health reports, recent self-assessment reports, and related condition reports, demonstrates that the FAC Program is effective in detecting loss of material due to FAC for susceptible components, and defining the corrective actions (e.g., repair or replacement) necessary to assure their continued operation in accordance with design requirements.

Conclusion The FAC Program will detect and manage loss of material due to FAC for susceptible components. The FAC Program, with the required enhancements, provides reasonable assurance that the aging effects will be managed such that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Aging Management Programs Page B-120 -- a y 2_010

]Amendment 1 I"

B.2.29 Fuel Oil Chemistry Program Columbia Generating Station License Renewal Application Technical Information contain fuel oil. Quarterly sampling of the fuel oil tanks for the diesel-driven fire pumps has been effective at identifying unacceptable levels of water and sediment prior to a loss of function. Higher than expected amounts of water or sediment during periodic sampling has resulted in cleaning of the tanks and filtering of the fuel to restore acceptable conditions. The periodic cleaning and filtering has included the addition of a biocide due to evidence of biofouling.

To meet new Environmental Protection Agency requirements, Columbia will be transitioning to Ultra-Low-Sulfur Diesel (ULSD) fuel prior to the period of extended operation. ULSD fuel and its possible adverse impacts on diesel performance are addressed in NRC Information Notice 2006-022. The impact of using ULSD fuel on the Columbia design and licensing basis has been evaluated, including the consideration of related operating experience from the industry, and corrective actions assigned to account for the future transition. Columbia will p..Vidc notification of any chang.s to the F uel till nernistry as a reSult of te transition t^ UGH Tuol.

^^Fograr Conclusion The Fuel Oil Chemistry Program will manage loss of material and cracking for susceptible components through monitoring and control of contaminants in the fuel oil.

The Fuel Oil Chemistry Program provides reasonable assurance that the aging effects will be managed such that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Insert A:

Energy Northwest determined that there are no compatibility issues and that no corrective actions or modifications are necessary as a result of the transition to ULSD fuel.

Aging Management Programs Page B-123 jaRwaFy 29 lAmendment 1

Columbia Generating Station License Renewal Application Technical Information B.2.39 Material Handling System Inspection Program Program Description The Material Handling System Inspection Program is credited with managing loss of material for cranes (including bridge, trolley, rails, and girders), monorails, and hoists within the scope of license renewal. The Material Handling System Inspection Program is based on guidance contained in ANSI B30.2 for overhead and gantry cranes, ANSI B30.11 for monorail systems and underhung cranes, and ANSI B30.16 for overhead hoists. The inspections monitor structural members for signs of corrosion and wear.

The inspections are performed periodically for installed cranes and hoists (e.g., annually for the reactor building crane, other NUREG-0612 heavy load handling systems and the refueling platform).

The Material Handling System Inspection Program provides reasonable assurance that the effects of aging are adequately managed for Columbia cranes (including bridge, trolley, rails, and girders), monorails, and hoists and that their intended function will continue to be performed consistent with the current licensing basis for the period of extended operation.

Replace stricken NUREG-1801 Consistency text with "is" The Material Handling Syster lnspection Program is an existing Columbia program that, with cnhanccmcnt, 'i!l be consistent with the 10 elements of an effective aging management program as described in NUREG-1801,Section XI.M23, "Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems."

Exceptions to NUREG-1801 None.

RReplace stricken Required Enhancements

• Jtext with "None."

Prior to the period of extended upe-ration he enhancement listed below will be implemAnt8d i the- 4entif.ied program efement-nete~to Fn.*ire jih rranes and e*letrically operated- hois-ts--are visually in.pected for.

Operating Experience A review of crane and hoist inspections previously conducted at Columbia and of industry operating experience confirms the acceptability of the inspections and their jAmendment 1 Aging Management Programs Page B-153

Columbia Generating Station B.2.39 Material Handling System Inspection Program License Renewal Application Technical Information frequency in that degradation of cranes (including bridge, trolley, rails, and girders),

monorails, and hoists was detected prior to loss of function. Related crane and hoist inspections have found no age-related degradation problems.

The health of the Material Handling System Inspection Program is reported periodically in terms of performance indicators. The program health reports for 2007 -ea6*2eS-noted no age-related improvements for the program.

The Material Handling System Inspection Program has been effective in managing the identified aging effects. The site corrective action program and ongoing review of industry operating experience will be used to ensure that the program continues to be effective in managing the identified aging effects. replace with Conclusion "to 2009" The Material Handling System Inspection Program will be capable of detecting and managing loss of material for cranes (including bridge, trolley, rails, and girders),

monorails, and hoists within the scope of license renewal. The continued implementation of the Material Handling System Inspection Program, with thc rcgquired enhancement, provides reasonable assurance that the aging effects will be managed such that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Amendmet1 rogams Maagemnt Agin ageB-15 ~yaOI Aging Management Programs Page B-1 54 L__ý 404:MaPP24ý9

B.2.40 Metal-Enclosed Bus Program Columbia Generating Station License Renewal Application Technical Information

• Confirmation Process This element is common to Columbia programs and activities that are credited with aging management during the, period of extended operation and is discussed in Section. B.1.3.

Aorministrative Controls This element is common to Columbia programs and activities that are credited with aging management during the period of extended' operation and is discussed in Section B.1.3.

Operating Experience The Metal-Enclosed Bus Program is a new program for which there is no direct site-specific operating experience. Based on review of plant-specific and industry operating experience, the identified aging effects require management for the period of extended operation.

Plant operating experience has shown that the. corrective action program has addressed, issues related to bus and bus enclosure degradation in recent years. For example, corrosion was identified on insulators used to support bus associated with the unit normal auxiliary transformer (which is not in scope for license renewal). In addition, the corrective action program noted that the use of thermography would provide an improvement to the bus preventive maintenance program. Industry operating experience will be included in the developmentof this program.

Required Enhancements Add Insert A shown Ibelow here program.

Not applicable, this is a new Conclusion The Metal-Enclosed Bus Program will manage aging degradation for metal-enclosed bus. The Metal-Enclosed Bus Program will provide reasonable assurance that the aging effects will be managed such that metal-enclosed bus subject to aging management review will continue to perform its intended functions consistent with the current licensing basis for the period of extended operation.

Insert A:

Also, in August 2009, there was a failure of a 6.9 kV non-segregated metal-enclosed bus (this bus not in the license renewal scope). The corrective action program is addressing the cause and actions needed to prevent reoccurrence on plant metal-enclosed busses.

Aging Management Programs Page 8-158.

JAmendment 1

Columbia Generating Station B.2.41 Monitoring and Collection Systems Inspection License Renewal Application Technical Information

" Floor Drains Radioactive (FDR) System

• Fuel Pool Cooling (FPC) System

" Miscellaneous Waste Radioactive (MWR) System Add:

• Plant Sanitary Drains (PSD) System Process Sampling

• Process Sampling Radioactive (PSR) System (PS) System 0 Reactor Closed Cooling (RCC) Water System A representative sample of components in these systems, to be defined in the implementing documents, and to include containment isolation piping and valve bodies, will be examined for evidence of a loss of material (due to crevice, galvanic, general, or pitting corrosion, erosion, or MIC), or to confirm a lack thereof, and the results applied to all of the systems and components within the scope of the inspection, based on engineering evaluation. In addition, the p.s..*ntativc

... ,,.m,,c

.... ....... tailess steel components exposed to temperatures

.... ... ta. 14 , F Mat v,, be examined for evidence of c g due to ,C. Replace with Insert A Preventive Actions on page B-160a No actions are taken as part of the Monitoring and Collection Systems Inspection to prevent aging effects or to mitigate aging degradation.

Parameters Monitored or Inspected The parameters to be inspected by the Monitoring and Collection Systems Inspection include wall thickness or visual evidence of internal surface degradation, as measures of a loss of material or cracking in susceptible materials. Inspections will be performed by qualified personnel using established NDE techniques.

Detection of Aging Effects The Monitoring and Collection Systems Inspection will use a combination of established volumetric and visual examination techniques (such as equivalent to VT-1 or VT-3) performed by qualified personnel on a sample population of subject components to identify evidence of loss of material or cracking in susceptible materials or to confirm a lack thereof on the susceptible internal surfaces of the components.

The sample population will be determined by engineering evaluation based on sound statistical sampling methodology, and, where practical, will be focused on the components most susceptible to aging, such as due to their time in service, the severity of conditions during normal plant operations, and the lowest design margins.

The sample population will include at least one location for containment isolation components.

Aging Management Programs Page B-160 JaErn atFY20108 1 J~m ndmnt1 _

Columbia Generating Station License Renewal Application Technical Information Insert A to Page B-160 In addition, the representative sample will include stainless steel components exposed to temperatures greater than 140 OF and copper alloy> 15% Zn components exposed to raw water that will be examined for evidence of cracking due to SCC.

Page B-160a Amendment 1 Programs Aging Management Programs Page B-160a Amendment 1

Columbia Generating Station License Renewal Application Technical Information B.2.42 Open-Cycle Cooling Water Program Program Description The Open-Cycle Cooling Water Program manages loss of material due to crevice, galvanic, general, pitting, and MIC, and erosion for components located in the Standby Service Water and Plant Service Water systems, and components connected to or serviced by those systems, and in the Tower Makeup Water and Circulating Water systems. The program also manages fouling due to particulates (e.g., corrosion products) and biological material (micro- and macro-organisms) resulting in reduction in heat transfer for heat exchangers within the scope of the program. hI addtiuui, [the program manages cracking for coppor alloy >,15% *omPZn the Procc..

on.....

in SamplinRg System and for a1Hfluminu compcnents in the HYAC systemgs that are subject to condcnsation. Replace:

"fouling The Open-Cycle Cooling Water Program consists of inspections, surveillances, and and testing to detect the presence, and assess the extent, of fouling, less of material,

-loss GaGki.,, combined with chemical treatments and cleaning activities to minimize fouling, of loss of material,,,d ,,-eaek"i. The existing program is a combination condition material" monitoring and mitigation program that implements the recommendations of NRC GL 89-13, "Service Water System Problems Affecting Safety-Related Equipment."

NUREG-1801 Consistency The Open-Cycle Cooling Water Program is an existing Columbia program that, with enhancement, will be consistent with the 10 elements of an effective aging management program as described in NUREG-1801 Section XI.M20, "Open-Cycle Cooling Water System," with exceptions.

Exceptions to NUREG-1801 Pro-gram Elements Affected:

• Preventive Actions -

NUREG-1801 states that system components are lined or coated to protect underlying metal surfaces from being exposed to aggressive cooling water environments. Protective coatings on the inner walls are not used in the service water systems that are within the scope of license renewal at Columbia.

• Monitoring and Trending -

NUREG-1801 states that testing and inspections are performed annually and during refueling outages. Inspection frequencies for the Open-Cycle Cooling Water Program are based on operating conditions and past history; flow rates, water quality, lay-up, and heat exchanger design.

Aging Management Programs Page B-163 -4anury-2Oýt Amendment 1 PJ_

Columbia Generating Station B.2.43 Potable Water Monitoring Program License Renewal Application Technical Information

" Parameters Monitored or Inspected The Potable Water Monitoring Program monitors the water treatment plant performance and the overall status of the potable water system, including water quality.

" Detection of Aging Effects The Potable Water Monitoring Program will be enhanced to use a combination of established volumetric and visual examination techniques performed by qualified personnel on locations within the PWC, PWH, and ROA systems, as determined by engineering evaluation, to identify evidence of a loss of material, or to confirm a lack thereof. At least one inspection will be conducted within the 10-year period prior to the period of extended operation.

Based on operating experience, it is necessary that inspections be conducted at least once every five years, and include components of the PWC and PWH systems that are located in the Reactor Building and components associated with the ROA air washer (ROA-AW-1), including the a 'washer housing.

• Monitoring and Trending I r Radwaste Building (including corridors)"I The Potable Water Monitoring Program monitors the water treatment plant performance and the overall status of the potable water system, including water quality, and the results are recorded and trended.

• Acceptance Criteria The acceptance criteria for potable water system inspections are: indications or relevant conditions of degradation detected during the inspection will be compared to pre-determined acceptance criteria. If the acceptance criteria are not met, then the indications and conditions will be evaluated under the corrective action program to determine whether they could result in a loss of component intended function during the period of extended operation.

Acceptance criteria have been established for potable water quality, which minimizes the presence of impurities that could cause degradation.

" Corrective Actions This element is common to Columbia programs and activities that are credited with aging management during the period of extended operation and is discussed in Section B.1.3.

• Confirmation Process This element is common to Columbia programs and activities that are credited with aging management during the period of extended operation and is discussed in Section B.1.3.

Aging Management Programs Page B-167 .. .>

iAmendment 1

B.2.47 Selective Leaching Inspection Columbia Generating Station LicenseTechnical Renewal Application Information inspection includes a visual examination and hardness measurement, or NRC approved alternative, of a sample set of components to determine whether selective leaching is occurring or is likely to occur in the period of extended operation.

The aging management activity is credited for the following systems:

• Auxiliary Steam (AS) System

• Circulating Water (CW) System

• Containment Nitrogen (CN) System

• Control Rod Drive (CRD) System

• Diesel Building HVAC Systems (DMA) Insert:

• Diesel Fuel Oil (DO) System "Heating Steam (HS) System

• Fire Protection (FP) System Heating Steam Condensate (HCO) System"

• High Pressure Core Spray (HPCS) System

• Low Pressure Core Spray (LPCS) System

• Main Steam (MS) System

• Plant Service Water (TSW) System

• Potable Cold Water (PWC) System

• Potable Hot Water (PWH) System

• Process Sampling (PS) System

• Radwaste Building Chilled Water (WCH) System

• Radwaste Building HVAC Systems (WEA, WMA, WOA, WRA)

• Reactor Building HVAC Systems (REA, ROA, RRA)

• Residual Heat Removal (RHR) System

• Standby Service Water (SW) System

• Tower Makeup Water (TMU) System

• Preventive Actions No actions are taken as part of the Selective Leaching Inspection to prevent aging effects or to mitigate aging degradation. Although the control of water chemistry may reduce selective leaching in treated water environments, no specific credit is taken for water chemistry control as part of this program.

Aging Management Programs Page B-179 -January-204,9 jAmendment 1

B.2.50 Structures Monitoring Program Columbia Generating Station License Renewal Application Technical Information of whether failures were maintenance preventable. A review of the Maintenance Rule program periodic assessments did not identify any age-related functional failures related to structures. Two non-age related functional failures identified were that the Reactor Building crane was parked without the tornado latches installed and a 10 CFR 21 notice from Whiting Crane Corporation regarding a weld defect on the Reactor Building crane main trolley. Replace with "documented" A -eeRe condition report d.eE....-s a surface flaw noted in the concrete of the west exterior wall of the Reactor Building. The surface flaw appears to have existed for a significant period of time with no apparent adverse effects on secondary containment or the Reactor Building structure. - ApageaB-196a NRC Unresolved Item (URI)05000397/2007005-02 was issued in February of 2008.

This URI identified that Columbia had not performed nor scheduled condition monitoring, inspection, or preventative maintenance (since receiving an operating license in 1983) of the submerged portion of the suppression chamber, the standby service water spray ponds, or the condensate storage tanks. The URI stated that although the licensee performed some monitoring of these structures, failure to perform monitoring of the submerged portion of these structures could result in undetected cracks or leakage that could prevent them from meeting their design basis functions.

This URI was documented in a condition report i .... b..... resolved under the corrective action process with closure information .. . . . ..F., . t ..

........... *Replace with "and

'--IReplace with "reviewed and accepted by the NRC" has been" The Structures Monitoring Program provides reasonable assurance that aging ettects are being managed. This has been demonstrated through inspection reports, program health reports, periodic assessments, and the corrective action program.

The site corrective action program and ongoing review of industry operating experience will be used to ensure that the program continues to be effective in managing the identified aging effects.

Conclusion The Structures Monitoring Program, with enhancements, will be capable of detecting and managing aging effects for structures within the scope of license renewal. The continued implementation of the Structures Monitoring Program, with the required enhancements, provides reasonable assurance that the effects of aging will be managed so that components subject to aging management review will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.

Aging Management Programs Page B-196 Ja7jap,94-9 JAmendment 1

Columbia Generating Station License Renewal Application Technical Information Insert A for LRA Section B.2.50, Paqe B-1 96 Investigation concluded that the crack has existed since construction and was repaired by grout material. A visual inspection of the cracked area determined additional sealing was required in order to prevent potential corrosion of reinforcing steel. The surface flaw crack has been partially sealed at the north end to close up the wider portion of the gap. The location of the surface flaw has been noted for re-inspection and future trending by the Structural Monitoring Program.

Page B-i 96a Amendment 1 Management Programs Aging Management Programs Page B-1 96a Amendment 1

Columbia Generating Station License Renewal Application Technical Information B.2.51 Supplemental Piping/Tank Inspection Program Description The Supplemental Piping/Tank Inspection is a new one-time inspection that will detect and characterize the material condition of steel, gray cast iron, and stainless steel components that are exposed to moist air environments, particularly the aggressive alternate wet and dry environment that exists at air-water interfaces or air spaces of susceptible piping and tanks. The inspection provides direct evidence as to whether, and to what extent, loss of material due to crevice, galvanic, general, and pitting corrosion, or MIC has occurred or is likely to occur that could result in a loss of intended function of the subject components.

Implementation of the Supplemental Piping/Tank Inspection will ensure that the pressure boundary integrity of susceptible safety-related components is maintained consistent with the current licensing bases during the period of extended operation.

Implementation of the inspection will also ensure that the structural integrity of susceptible NSR components will be maintained such that spatial interactions (e.g.,

leakage) will not result in the loss of any safety-related component intended functions during the period of extended operation.

NUREG-1801 Consistency The Supplemental Piping/Tank Inspection is a new one-time inspection for Columbia that will be consistent with the 10 elements of an effective aging management program as described in NUREG-1801,Section XI.M32, "One-Time Inspection."

Exceptions to NUREG-1801 None.

Aging Management Program Elements The results of an evaluation of each program element are provided below.

Scope of Program The scope of the Supplemental Piping/Tank Inspection includes the internal and external surfaces of steel, gray cast iron, and stainless steel components at air-water interfaces and other susceptible locations in the following systems:

" Condensate (Nuclear) (COND) Syste Add: "Condensate (Auxiliary) (CO)

• Containment Vacuum Breakers (CVB) System"

• Diesel Cooling Water (DCW) System

" Equipment Drains Radioactive (EDR) System Aging Management Programs Page B-197 -Jafualy2010 IAmendmentL1ZI7

Columbia'GeneratihngStation se Reneal AW plicationi B.2.51 Supplemental Piping/Tank Inspection L:Liceh Technical Information o Fire Protection .(FP) System

" Floor Drain (FD) System Floor Drain Radioactive.(FDR)ý System

" Fuel Pool!Cooling (FPC) System Add:

Heating Steam CondensateI

• AHgh Pnressure Core ,Spray (HPCS)NSytem HCO)Sstem

• Low Pressure-Core Spray (LPCS) System

. Main Steam (rMS)System

• Miscellaneous Drain (MD) System

• Process Sampling Radioactive (PSR) System o ReattorBuilding Outside Air (ROA) System

• ReactorClosed Cooling. Water (RCC) System

• ReactorCore !solation Cooling :(RCIC),,System

• Residual Heat Removal (RHR),System standby Liquid Control (SLC) System S

• Standby Services Water`(SV) System

• Tower Makeup Water (TMU) System A representative sample of components at susceptible locations Wil -be examined for evidence of loss of material (due to crevice, galvanic,, general, or pitting corrosion, or MIC),, orto confirm a lack thereof.

The Supplemental Piping/Tank Inspection focuses on a limited but representative sample population of subject components at susceptible locations to be defined in the implementing documents, to include external piping surfaces, and internal tank and piping surfaces at air-water interfaces. The inspections provide symptomatic evidence of loss of material at the other susceptible, but possibly inaccessible, locations (such as internal surfaces of piping) due to the similarities in materials and environmental conditions.

• Preventive Actions No actions are taken as part, of the Supplemental Piping/Tank Inspection to prevent aging effects-or to mitigate agingdegraýdation.

• Parameters'Monitored or Inspected The parameters tobe inspetted by the Supplemental Pipifgfank I.nspection include wall -thickness or visual evidence of internal and external surface degradation, as measures of, loss of material. Inspections will be performted by qualified personnel Aging'Management Programs Page B-1984.

jAmendment 1 r

Columbia Generating Station B.2.53 Water Control Structures Inspection License Renewal Application Technical Information Operating Experience The Water Control Structures Inspection has been effective in managing the identified aging effects. Visual inspections conducted by the Water Control Structures Inspection, implemented as part of the Structures Monitoring Program, have found no age-related problems.

The general structural condition of Standby Service Water Pump Houses "A" and "B" and their associated spray ponds is good. No adverse conditions or deficiencies (cracking, spalling, or honeycombs) were noted during the inspection of concrete structural elements (walls, slabs, beams, etc.) that would affect the structural integrity of either pump house or spray pond. Equipment anchorages were secured. No degraded conditions (bent or twisted members, cracked welds, loose or missing fasteners, etc) were identified for steel members. The "saddle" supports for the ring header were noted to have the coating delaminating in places. However, there were only minor amounts of corrosion products at those locations (i.e., not a structural concern). Pipe supports on spray pond walls were in good shape with all fasteners installed and tight. Doors and frames did not show any evidence of a degraded condition. There were no signs of moisture intrusion from the roof above and no signs of gross deficiencies (spalling, cracking, honeycombs) found from below. There were no obvious deficiencies identified with the crane structural frames. The rails appeared in good physical condition with no obvious signs of degradation such as bent or deformed rails. The Standby Service Water Pump Houses and the Spray Ponds are capable of performing their intended design function as the ultimate heat sink in response to accident conditions. Replace with "and has been" NRC Unresolved Item (URI)05000397/2007005-0 was issued in February of 2008.

This URI identified that Columbia had not p rformed nor scheduled condition monitoring, inspection, or preventative mainten nce (since receiving an operating license in 1983) of the submerged portion of th suppression chamber, the standby service water spray ponds, or the condensate orage tanks. The URI stated that although the licensee performed some monitoring of these structures, failure to perform monitoring of the submerged portion of these tructures could result in undetected cracks or leakage that could prevent them fro meeting their design basis functions.

This URI was documented in a condition report hat GsF.,.,,y .,,"- resolved under the corrective action process with closure information cxpected near the time Of the I=RA

' --

-FFta. Replace with "reviewed and accepted by the NRC" The general conditions noted for the Circulating Water Pump House (including circulating water basin) and the cooling tower basins, including the structural components within the structures, was acceptable. Minor leaching was observed in the Circulating Water Pump House on a concrete pad near the interface with the siding, in addition to cracks in the wall along joints due to stresses caused by a hanger attached to the wall above the door, corrosion on the lower section of various door frames, and Aging Management Programs Page B-207 [Amendment 1 II-'...."..cw 2... -

The 37 Drawings specifically referenced in Enclosure 2 have been processed into ADAMS.

These drawings can be accessed by NRC Staff members within the ADAMS package or by performing a search on the Document/Report Number.

D-01 TO D-37X

LICENSE RENEWAL APPLICATION FIRST ANNUAL UPDATE Page 1 of 1 For information only -3 copies Revised Boundary Drawinas Drawing number Reason LR-216-01,3682 Added Rev 0 indication on drawing.

LR-225-02,21 Added Rev 0 indication on drawing:

LR-225-02,22 Added Rev 0 indication on drawing.

LR-M502-1 , Revised LR-M508 Revised LR-M-513 Revised f LR-M515-4. Revised LR-M515-5 Revised LR-M517 Revised LR-M525-2 Revised LR-M526-1 Revised LR-M526-2 Revised LR-M527-1 Revised LR-M537 Revised LR-M539 Revised LR-M604 Revised LR-M788-1 Revised LR-M852 Revised LR-P541 -1 Revised LR-P542 Revised LR-M502-3 New drawing LR-M508-2 New drawing LR-M514-1 New drawing LR-M519 New drawing LR-M521-2 New drawing LR-M527-1 New drawing LR-M527-2 New drawing LR-M531 New drawing LR-M532 New drawing LR-M533-1 New drawing L-LR-M533-2 New drawing [

LR-M534 New drawing LR-M536 New drawing LR-M537 New drawing LR-M543-2 New drawing LR-M545-2 New drawing LR-M545-3 New drawing