ML11139A346

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Summary of Telephone Conference Call Held on May 10, 2011, Between the NRC and Nuclear, LLC, Concerning a Draft Response to a Draft RAI Pertaining to the Salem Nuclear Generating Station, Units 1 and 2, (Salem) License Renewal Application
ML11139A346
Person / Time
Site: Salem  PSEG icon.png
Issue date: 05/26/2011
From: Cuadradodejesus S
License Renewal Projects Branch 1
To:
Public Service Enterprise Group
CuadradoDeJesus S
References
Download: ML11139A346 (47)
v • d • e


Text

v\.~P.R RfGlJz., UNITED STATES

~" }<o fJ~. "P,I. NUCLEAR REGULATORY COMMISSION

!t g WASHINGTON, D.C. 20555-0001

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"'+') ~o~ May 26, 2011

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LICENSEE: PSEG Nuclear, LLC FACILITY: Salem Nuclear Generating Station, Units 1 and 2

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MAY 10, 2011, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PSEG NUCLEAR, LLC, CONCERNING A DRAFT RESPONSE TO A DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2, (SALEM) LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PSEG Nuclear, LLC (the applicant), and Exelon held a telephone conference call on May 10, 2011, to discuss the applicant's draft response to the staff's request for additional information (D-RAI) 3.2.1.48. The telephone conference call was useful in clarifying the intent of the applicant's D-RAI response.

Enclosure 1 provides a listing of the participants. Enclosure 2 contains a brief summary of the discussion and status of the items. Enclosure 3 includes the applicant's response to the D-RAI.

The applicant had an opportunity to comment on this summary.

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adrado de Jesus, Project Manager Projects ranch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311

Enclosures:

As stated cc w/encls: Listserv

TELEPHONE CONFERENCE CALL SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS May 10, 2011 PARTICIPANTS AFFILIATIONS Samuel Cuadrado de Jesus U.S. Nuclear Regulatory Commission (NRC)

Bennett Brady NRC John Wise NRC William Holston NRC Phillip O'Donnell Exelon Albert Piha Exelon Kevin Muggleston PSEG Nuclear (Contractor)

ENCLOSURE 1

SUMMARY

OF MEETING ON A DRAFT RAI RESPONSE FOR SALEM NUCLEAR GENERATING STATION. UNITS 1 AND 2. LICENSE RENEWAL APPLICATION MAY 10, 2011 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PSEG Nuclear, LLC (the applicant) held a telephone conference call on May 10, 2011, to discuss the applicant's draft response to the staffs draft request for additional information (O-RAI) 3.2.1.48 regarding the aging management of stainless steel components and steel components with stainless steel cladding exposed to treated borated water with high oxygen content.

Discussion The staff stated that after reviewing the applicant's response to O-RAI 3.2.1.48 clarification was needed regarding one line item on Table 3.2.2-3 of the LRA. Specifically the staff found that the applicant chose not to add a one-time inspection for the restricting orifices (class-one) component for which loss of material in treated borated water is managed by the Water Chemistry Program (referring to Table 1 item 3.2.1-49). The staff stated that looking at the plant drawings, it is not clear whether this orifice is normally exposed to an oxygen-scavenged reactor coolant environment, or whether it may actually be isolated between valves in an air-saturated reactor coolant environment. The staff further stated that if the orifice is exposed to high-oxygen water an additional program, like the one-time inspection, should be added for verification. The staff asked the applicant to explain why they didn't add the one-time inspection program to the restricting orifices (class-one) components.

The applicant stated that those components were isolated and that their assumption was that over time oxygen will deplete. The staff stated that it was not clear whether this assumption was valid and, even under this scenario, the mechanism of oxygen depletion may be corrosion.

Thus, the staff recommended that a verification program be added to these components. The applicant agreed to add the one-time inspection to these components and will update their O-RAI response to reflect that in their final LRA supplement letter.

ENCLOSURE 2

10 CFR 50 10 CFR 51 10 CFR 54 LR-N11-0148 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Salem Nuclear Generating Station, Unit No.1 and.Unit No.2 Facility Operating License Nos. DPR-70 and DPR;~75" NRC Docket Nos. 50-272 and 50-311

Subject:

Supplement to the Salem Nuclear Generating Station, Unit No.1 and Unit No.2 License Renewal Application to address Treated Borated Water Environments

Reference:

NRC Draft RAI 3.2.1.48 and associated May 5, 2011 Teleconference between NRC Staff and PSEG Nuclear LLC related to, Salem Nuclear Generating Station, Unit No.1 and Unit No. 2'Ucense Renewal" The NRC Staff contacted PSEG Nuclearc,.c,.C (PS~~).related fo.adetermination made by Staff that the guidance in the Standard Review Plan for Rev'jew of License Renewal Applications for Nuclear Power Plants (SRP-LR) and Generic Aging Lessons Learned (GALL) Report does not adequately address aging management in treated borated water environments that contain dissolved oxygen above a 100 ppb threshold. Based on this determination, the Staff made three specific requests otPSEG to ensure that the Salem LRA adequately addresses this issue.

Enclosure A provides the NRC requests and the associated PSEG responses. Enclosure B contains updateq sections of the Salem LRA.

A minor revision to License Renewal commitment #20 is made to reflect this change, as shown on page 30 of Enclosure B. There are no other new or revised regulatory commitments contained in this letter.

If you have any questions, please contact Mr. Ali Fakhar, PSEG Manager - License Renewal, at 856-339-1646.

ENCLOSURE 3

-2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on Sincerely, Paul J. Davison Vice President, Operations Support PSEG Nuclear LLC

Enclosures:

A. Response to draft RAI associated with Salem Nuclear Generating Station, Unit No. 1 and Unit No. 2 License RenewalApplication B. Changes to Salem Nuclear GeneratiQg Station, Unit No.1 and Unit No.2 License Renewal Application cc: William M. Dean, Regional Admin.istrator - USNRC Region I Bennett Brady, Senior Project Man!E!ger, LiceQs~.13enewar;;.;.. VSNRC Samuel CuadradoDeJesus, Project Manager,. Licehse Renewal - USNRC R. Ennis, Project Manager - USNRC NRC Senior Resi9~htlnspec:tor - Salem P. Mulligan, Manager IV, NJBINE L. Marabella'.:!'C()rporate Co~mitment Tracking Coordinator H. Berrick, Salem Commitment Tracking Coordinator

Enclosure A LR-N11-0148 Page 1 of 2 Draft RAI 3.2.1.48

Background

The staff has determined that existing guidance in the Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) and Generic Aging Lessons Learned (GALL) Report does not adequately address aging management in treated borated water environments that contain dissolved oxygen above a 100 ppb threshold. Specifically, for pressurized water reactors (PWRs), the guidance recommends using the Water Chemistry Program only for aging management of loss of material due to pitting Jand crevice corrosion and cracking due to stress corrosion cracking in stainless steel components exposed to treated borated water, whereas the combination of the Water Chemi~try Program and One-Time Inspection Program is used for boiling water reactor (BWR) treated water environments.

In its development of the GALL Report, the staff originally attributed the lesser corrosiveness of PWR primary water (treated borated) relative to that::pf BWR primary water (treated) to the presence of boron. However, the low corrosiveness of PWR primary water is not due to the presence of boron, but rather very low dissolved oxygen levels and other chemistry controls.

The boron compounds in treated borated water are not actively managed to ensure that they are in a form or of an appropriate concentration to inhibit corrosion. Thus, SSCs exposed to an environment of treated borated water with elevated oxygen should be age managed by a combination of the Water Chemistry ProQ,.am~.nct9ne-Time Inspection Program to account for the greater corrosiveness, regardless of Whether ft'i~ water is bo(ated.

In the LRA, the applicant stated that stainless steel and stee/with stainless steel cladding components exposed to treated b()r~ted wateriwill,be managed for loss of material due to pitting and crevice corrosion and cracking due to stress corrosion cracking with the Water Chemistry Program for those items associated with LRA Table 3.2.1, item 3.2.1-48; Table 3.2.1, item 3.2.1-49; Table 3,3.1, item 3.3:1";90; and Table.(3.3.1, item 3.3.1-91.

Issue

1. The staff noted..that several AMR items reference the LRA Table 3.2.1 and 3.3.1 items

<;ibove; however,+tbe associat~,d treated borated water environments may not be co:ptrolled to less ft'ian 100 ppbdissolved oxygen, and thus, the aging effects may not be effectively managed.'! Examples of applicable systems in the LRA include, but are not limited to, the containment spray system, safety injection system, and the spent fuel cooling system.

2. The staff bEHiev:eSfhat the UFSAR Supplement should include AMP changes that address the up'aated staff guidance to ensure that the licensing basis for the period of extended operation is clear.

Request

1. Identify the AMR items that use only the Water Chemistry Program to age manage stainless steel and steel with stainless steel cladding components exposed to treated borated water with greater than 100 ppb oxygen for loss of material due to pitting and crevice corrosion and cracking due to stress corrosion cracking.

Enclosure A LR-N11-0148 Page 2 of 2

2. For the identified items, state how the effectiveness of the Water Chemistry Program will be verified.
3. Update the UFSAR Supplement for the Water Chemistry Program, and the program used to verify its effectiveness, to ensure that the usage of these programs to manage treated borated water with greater than 100 ppb oxygen is reflected in the licensing basis for the period of extended operation.

PSEG Response:

1. Enclosure B identifies the AMR items that use only the WatetChemistry Program to age manage stainless steel and steel with stainless steel claddingco!1lPonents exposed to treated borated water with greater than 100 ppb oxygen for loss of:rnaterial due to pitting and crevice corrosion and cracking due to stress corrosion cracking.
2. As shown in the AMR tables in

Enclosure:

s'i:the One-Time Inspection Program will be used to verify the effectiveness of the Water'Chemistryprogram in managing the aging effects for stainless steel components in a treated bor$ted water environment, where dissolved oxygen may not be controlled to less tha!11l100 ppb.

3. Enclosure B provides the PSEGl.Jpdat~t?t~e UFSARSlJ,pplement for the Water Chemistry Program, and the One~rime Inspection Program used to verify its effectiveness, to ensure that the usage of the~~pr()gramstO:)11anage treated borated water with greater than 100 ppb oxygen is refleCted in the licensing basis for the period of extended operation.

Enclosure B LR-N11-0148 Page 1 of 34 Enclosure B Salem Generating Station License Renewal Application (LRA) Changes The PSEG response results in changes to the LRA. The affected LRA Sections and Enclosure pages for the associated LRA Section markups are identified below. For clarity, portions of the original LRA, as updated by subsequent PSEG Nuclear license renewal correspondence, are repeated in this Enclosure. Added text is shown in Bold Italics, and deletions are shown with strikethrough text. .

LRA Section EnclosurePage.

3.2.2.2.3 .................................................................2 Table 3.2.1 .................................................................3 Table 3.2.2-1 .............................................................4 Table 3.3.2-2 .............................................................5 Table 3.3.2-3 .............................................................9 Table 3. 3.1.........................................................;~;."..13 Table 3.3.2-5 ...........................................................15 Table 3.3.2-14 ........................*;;.....;,***................... ..1a Table 3.3.2-21 .........................................................20 Table 3.3.2-22.........................................................22 Table 3.3.2-25................."...........................................24 Table 3.5.2-3...........................................................26 Table 3.5.2-5*.~ .........................................................27 A.2.1.2......................................................................28 A.2.1.20 ...................................................................28 A5.......... "-,, . " "...................... .... .................................................................................... .M

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B.2.1.2.......................................................................32 8.2.1.20.....................................................................34

Enclosure B LR-N11-0148 Page 2 of 34 3.2.2.2.3 Loss of Material due to Pitting and Crevice Corrosion

1. Loss of material due to pitting and crevice corrosion could occur for internal surfaces of stainless steel containment isolation piping, piping components, and piping elements exposed to treated water. The existing AMP relies on monitoring and control of water chemistry to mitigate degradation. However, control of water chemistry does not preclude loss of material due to pitting and crevice corrosion at locations of stagnant flow conditions. Therefore, the effectiveness of the chemistry control program should be verified to ensure that corrosion is not occurring. The GALL Report recommends further evaluation of programs to verify the effectiveness of the chemistry control program: 'A one-time inspection of select components at susceptible locations is an acceptablfimethod to determine whether an aging effect is not occurring or an aging effect is progressing very slowly such that the component's intend(Jdfunction will be maintained during the period of extended operation.

Item Number 3.2.1-3 is not applicable to Salem. The stainless steel piping and piping components internal surfaces in the Engineered Safety Features are exposed to treated borated water and are evaluated with Item Number 3.2.1-49.

Water Chemistry program activities provide for monitoring and controlling the chemical environments onhe> primary cycle~ystems in accordance with EPRI, Pressurized Water Reactor Primary Chemistry.::(3uidelines. The Water Chemistry program activities mitigate t~e loss of material aging effect to ensure there is no loss of component intendedfunction..7;h,::pne- Time Inspection program will be used to ver(fJt the effectiveness of the Wa(er Chemistry program in managing theagi'19 effects for stainless steel components in a treated borate.dwster environment, where dissolved oxygen may not be control/ed to les.sthan 100 ppb.

Enclosure B LR-N11-0148 Page 3 of 34 Table 3.2.1 Summary of Aging Management Evaluations for the Engineered Safety Features

---

Item Component Aging Aging Further Evaluation Discussion Number Effect/Mechanism Management Recommended Programs 3.2.1-48 Stainless steel or stainless Cracking due to Water Chemistry No ponsistent with NUREG-1801. The Water Chemistry steel-clad steel piping, stress corrosion program, 8.2.1.2, will be used to manage the effects of piping components, piping cracking cracking due to stress corrosion cracking in stainless steel elements, and tanks piping!; piping components, and piping elements exposed to (including safety injection treated bOrated water >140°F in the Chemical & Volume tanks/accumulators) Control System, Residual Heat Removal System, and exposed to treated borated Safety Injectio... System. The Safety Injection Accumulators water >60*C (>140°F) are exposed to treated borated water less than 140°F, and are included in Item Number 3.2.1-49.

The One-Time Inspection program will be used to verify the effectiveness of the Water Chemistry program to manage cracking of stainless steel components in the Residual Heat Removal System, and Safety Injection System, where dissolved oxygen may not be controlled

.': .'

to Jess than 100 ppb.

3.2.1-49 Stainless steel piping, Loss of material due Water Chemistry No Consistent with NUREG-1801. The Water Chemistry piping components, piping to pitting and cr~vice program, 8.2.1.2, will be used to manage loss of material elements, and tanks corrosion due to pitting and crevice corrosion in stainless steel piping, exposed to treated borated piping components, piping elements, heat exchangers, and water tanks exposed to treated borated water in the Chemical &

Volume Control System, Containment Spray System, Residual Heat Removal System, and Safety Injection

System.

The One-Time Inspection program will be used to verify the effectiveness of the Water Chemistry program to manage loss of material in stainless steel components in the Containment Spray System, Residual Heat i Removal System, and Safety Injection System, where dissolved oxygen may not be controlled to less than 100 ppb.

Enclosure B LR-N11-0148 Page 4 of 34 Table 3.2.2-1 Containment Spray System

--- ------ ----------- ----------

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item Manaaement Eductor Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting '" . Water Chemistry V.D1-30 3.2.1-49 A (Internal) and Crevice Corrosion - - - - - _ ..

Eductor Pressure Boundary Stainless Steel Treated Borated Wate! Loss of Material/Pitting One.;.Time Inspection V.D1-30 3.2.1-49 E,2 (Internal) and Crevice Coaosion Flow Device Pressure Boundary Stainless Steel Treated Borated Water Loss of Mat~rillllPitting Water Chemistry V.D1-30 3.2.1-49 A 1----------

(Internal) and Crevice Corrosion Flow Device Pressure Boundary Stainless Steel Treated Borated Wate, Loss ofMaterial/Pitting One-Time Inspectio", V.D1-30 3.2.1-49 E,2 afJt~rnal) and Crevice Corrosion"*

Flow Element Pressure Boundary Stainless Steel Treated Borated Water Loss of Mate[EW'fiUing Water Chemistry V.D1-30 3.2.1-49 A

_. ------- -------

(Internal) and Crevice Cbrrosion Flow Element Pressure Boundary Stainless Steel Treated Borated Wate, Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,2 (lnternalJ and Cre.vice Corrosion Piping and Fittings Pressure Boundary Stainless Steel Treated Borated Water ',,' Lossdf':~rial/Pitting 'ii:[!:' Water Chemistry V.D1-30 3.2.1-49 A (Internal) and Crevice Gorrosion --------

Piping and Pressure Boundary Stainless Steel Treated:Bqf8ted Watel LQ~ of Material/Pittillg One-Time Inspection V.D1-30 3.2.1-49 E,2 Fittings ji"ternal) andnCretlice Coaosioll -

-'m",,

Pump Casing Pressure Boundary Stainless Steel Borated Water Loss' of Material/Pitting Water Chemistry V.A-27 3.2.1-49 A (Containment (Internal) and Crevice Corrosion Spray Pumps) >; ,i:

Pump Casing Pressure Boundary Stainless Steel Treated BQrated Water l.,()s~,,()f Mi!.terial/Pitting One-Time Inspection V.A-27 3.2.1-49 E,2 (Containment (Internal) and'Crevice Corrosion Spray Pumps) --------

""i*,; ... _

Strainer Body Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A (Internal) and Crevice Corrosion --------

Strainer Body Pressure Boundary Stainless Steel Treated Borated ,Water Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,2 (Internal) and Crevice Corrosion Valve Body Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A

~ __ T (Internal) and Crevice Corrosion Valve Body Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,2 (Internal) and Crevice Corrosion Plant Specific Notes:

Enclosure 8 LR-N11-0148 Page 5 of 34

2. The One- Time Inspection program will be used to verify the effectiveness of the Water Chemistry program in managing the aging effects for stainless steel components in a treated borated water environment, where dissolved oxygen may not be controlled to less than 100 ppb.

Enclosure B LR-N11-0148 Page 6 of 34 Table 3.2.2-2 Residual Heat Removal System ~~~~- ----

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item

Management --------

Flow Element Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry V.D1-31 3.2.1-48 A

~~~~~~

(Internal) > 140 F CrackinQ ------

Flow Element Pressure Boundary Stainless Steel Treated Borated Wate, Cracking/Stress One-Timf1lnspection V.D1-31 3.2.1-48 E,4

(Internal) > 140 F Corrosion C{aCkina

-=c ~~~~~~

Flow Element Pressure Boundary Stainless Steel Treated Borated Water Loss of Mat~rial/Pitting Water Chemistry V.D1-30 3.2.1-49 A i------- (Internal) > 140 F and Crevice Corrosion ,::~ r-------~~ ------ ----

Flow Element Pressure Boundary Stainless Steel Treated Borated Wate, Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,4 (Internal) > 140 F and CreviCf.J.Corrosion r- ----

'"

Piping and Fittings Leakage Boundary Stainless Steel Treated Borated Water Cracking/Stres,s,:G9rrosion Water Chemistry V.D1-31 3.2.1-48 A

------

(Internal) > 140 F Cracking',i Piping and Leakage Boundary Stainless Steel Treated Borated Watel .Cracking/Stress One-Time Inspection V.D1-31 3.2.1-48 E,4 Fitting~ (InternaQ> 140 F Corrosion Cracking Piping and Fittings Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A

- ~~------

(Internal) > 140 F and Crevice COrrosion ~ ~

Piping and Leakage Boundary Stainless Steel Treated Borated Wate, Loss of MateriaVPitting One-Time Inspection V.D1-30 3.2.1-49 E,4 Fittings ~~~~

(Intema/J~;;140 F and Crevice Corrosion ~~~~~~~

Piping and Fittings Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry V.D1-31 3.2.1-48 A

- ~--~~ ----

(Internal) > 140 F Crackina ------- ~ ~ ~ ~~ ---_.. ~ ~ ~------ ~~~ _.. ~~-------

Piping and Pressure Boundary Stainless Steel Treated Borated'Wate, Cracking/Stress One-Time Inspection V.D1-31 3.2.1-48 E,4 Fittings (Internal)? 14(H=~,. Corrosion Cracking ------ ------ -_ ..

Piping and Fittings Pressure Boundary Stainless Steel Treated Borated Water Ldss ~rMateriallPitting Water Chemistry V.D1-30 3.2.1-49 A (Internal) > 140 F and Crevice Corrosion -------- ~ ~~~~- ~--.. ~~------- ~~- -------

Piping and Pressure Boundary Stainless Steel Treated Borated Wate, Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,4 Fittings (Internal) > 1f1JJ;,F and Crevice Corrosion ------

Pump Casing Leakage Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry V.D1-31 3.2.1-48 A (Letdown Booster (Internal) > 140 F Cracking

, Pump) ~

~~-~ -~~~~-

Pump Casing Leakage Boundary Stainless Steel Treated Borated Water CrackinglStress One-Titnelnspection V.D1-31 3.2.1-48 E,4 (Letdown Booster (Internal) > 140 F Corrosion Cracking

Putnp) ~~~'--- -------- -------- -------- ~~J_ __ .. ------- ~~~----'- ~~------

Enclosure B LR-N11-0148 Page 7 of 34 Table 3.2.2-2 Residual Heat Removal System (Continued)

------

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item

Management Pump Casing Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting, Water Chemistry V.D1-30 3.2.1-49 A (Letdown Booster (Internal) > 140 F and Crevice Corrosion Pump) ,

<c ,

Pump Casing Leakage Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One- Timelnspection V.D1-30 3.2.1-49 E,4 I (Letdown Boostel (Internal) > 140 F and Crevice,Corrosion Pump) -------

,

Pump Casing Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry V.D1-31 3.2.1-48 A (Residual Heat (Internal) > 140 F Cra~ing

".

Removal) -------- ------

Pump Casing Pressure Boundary Stainless Steel Treated Borated Wate, Cracking/Str,efJS One- Time Inspection V.D1-31 3.2.1-48 E,4 (Residual Heat (Internal) > 140 F, Corrosion Cracking Removal)

Pump Casing Pressure Boundary Stainless Steel Treated Borated Water Loss of Mat~riallPitting I; Water Chemistry V.D1-30 3.2.1-49 A (Residual Heat (Internal) > 140 F and Crevicei(ilorrosion Removal) ------ " .... ~ ... -------

".,

!tump Casing Pressure Boundary Stainless Steel Treated BOrated Wate, Loss ofM;~tiJriaIIPitiiHg One-Time Inspection V.D1-30 3.2.1-49 E,4 (Residual Heat (Internal) '> 140 F and Crevice Corrosion

~Removal) I,c+, ------ , .... ---------

Restricting Orifices Leakage Boundary Stainless ", Treated Borated Water Cracking/~tress Corrosion Water Chemistry V.D1-31 3.2.1-48 A

_ .. T(lnternal) > 140F Cracking ------ ~ ...

Restricting Leakage Boundary Stainless Steel Treated ** Borated Watel Cracking/Stress One-Time Inspection V.D1-31 3.2.1-48 E,4 Orifices (Internal) > 140 F Corrosion Cracking

'---'"

.... c"

  • Restricting Orifices Leakage Boundary l,mi~~~11 "'"' ' Steel Treated Borated Water 1, (Internal) > 140 F Loss of Material/Pitting and Crevice Corrosion Water Chemistry

V.D1-30

3.2.1-49 A Restricting Leakage Boundary Stainless Steel Treated Borated Wate, Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,4 Orifices (Internal) > 140F and Crevice Corrosion Restricting Orifices Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry V.D1-31 3.2.1-48 A (Internal) > 140 F Cracking Restricting Pressure Boundary Stainless Steel Treated BOrated Wate, Cracking/Stress One-Time Inspection V.D1-31 3.2.1-48 E,4

_Orifices (Internal) > 140 F Corrosion Cracking Restricting Orifices Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A (Internal) > 140 F and Crevice Corrosion

..... ~

f..* .. ------------ ... ," ------------ ---------

Restricting Pressure Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,4 Orifices (lnternal)>,14Q F and Crevice Corrosion --------- . . . ~-

Enclosure B LR-N11-0148 Page 8 of 34 Table 3.2.2-2 Residual Heat Removal System (Continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item Management Restricting Orifices Throttle Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry V.D1-31 3.2.1-48 A (Internal) > 140 F CrackinQ Restricting Throttle Stainless Steel Treated Borated Watel Cracking/Stress One-Time Inspection V.D1-31 3.2.1-48 E,4 Orifices (Internal>> 140 F Corrosion Ctackina Restricting Orifices Throttle Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A (Internal) > 140 F and Crevice Corrosion

~~~~ - - -------

Restricting Throttle Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,4 r- ... Orifices Lffi1ternal) >u14O F and Crevice Corrosion --------

Strainer Body Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress Oorrol,'lion Water Chemistry V.D1-31 3.2.1-48 A (Internal) > 140 F Crackin~ ,

Strainer Body Pressure Boundary Stainless Steel Treated Borated Walel Cracking/Stress One-Time Inspection V.D1-31 3.2.1-48 E,4 (Internal) > 140 F Corrosion Crac.king ------ ------ ------

Strainer Body Pressure Boundary Stainless Steel Treated Borated Water Loss of Ma~ertal/Pitting Water Chemistry V.D1-30 3.2.1-49 A

(Internal) > 140 F and CrevicetCorrosion ------

Strainer Body Pressure Boundary Stainless Steel Treated BOrtfted Wate, Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,4 (Internal>>J4Q F .3!!!t!C;revic.~-,~C)rrosion Thermowell Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry V.D1-31 3.2.1-48 A

....... ~

(internal) > 140 F Crackina Thermowell Pressure Boundary Stainless Steel Tteated BoratedWatel Cracking/Stress One-Time Inspection V.D1-31 3.2.1-48 E,4 (lnternalJii;;':i140 F .;f;orros;on Cracking -------

Th ermowe II Pressure Boundary Stainless Steel Treated, Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A (internall> 140 F and Crevice Corrosion ..... ~

ThermowelJ Pressure Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,4 (Internal) > 140 F and Crevice Corrosion _ . . . . . . ._

~----- ---------- ...

Valve Body Leakage Boundary Stainless Steel Treated::Borated Water Cracking/Stress Corrosion Water Chemistry V.D1-31 3.2.1-48 A

(Inten"l~1) > 140 F CrackinQ Valve Body Leakage Boundary Stainless Steel Treated Borated Water Cracking/Stress One-Time Inspection V.D1-31 3.2.1-48 E,4 (lnterna/) > 140 F Corrosion Cracking .....

Valve Body Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A I (Internal) > 140 F and Crevice Corrosion ------

Valve Body Leakage Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,4

_ (Internal) > 140 F and Crevice Corrosion

Enclosure B LR-N11-0148 Page 9 of 34 Table 3.2.2-2 Residual Heat Removal System (Continued) r ----- -----------

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 11tem I Notes Type Function Requiring Programs Vol. 2 Item Management valve Body Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry V.D1-31 3.2.1-48 A (Internal) > 140 F Cracking Valve Body Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress One-Timelnspection V.D1-31 3.2.1-48 E,4

- - - - - - - - - - r-------------------- r------------------

(Internal) > 140 F CorrOSion Cflicking Valve Body Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A (Internal) > 1~O F and Crevice Corrosion Valve Body Pressure Boundary Stainless Steel Treated Borated Watel Loss ofMaterial/Pitfing, One-Time Inspection V.D1-30 3.2.1-49 E,4 (Internal) > 140 F and Crevice Corrosion <1'

Plant Specific Notes:

4. The One-Time Inspection program will be used to verify the effectiveness of the Water Chemistry program in managing the aging effects for stainless steel components in a treated borated water environment, w"~fe dissolved oxygen may not be controlled to less than 100 ppb.

Enclosure B LR-N11-0148 Page 10 of 34 Table 3.2.2-3 Safety

-

Injection System

---- ----

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item

Management Class 1 Piping, Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting - Water Chemistry V.D1-30 3.2.1-49 A Fittings and Branch (Internal) > 140 F and Crevice Corrosion Connections <

NPS4" Class 1 Piping, Pressure Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Tim; Inspection V.D1-30 3.2.1-49 E,8 Fittings and (Internal) > 140 F and CrevicifCorrosion Branch Connections <

NPS4" -------------

Flow Element Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A (Internal) and Crevice Corrosion Flow Element Pressure Boundary Stainless Steel Treated Borated Watel l,,~ of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,8 (Internal) _and-Crevice Corrosion Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 C Components (Shellside (Internal) and Crevice Corrosion (Refueling Water Components)

Storage Tank)

Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,8 Components (Shellside (Internal) and Crevice Corrosion (Refueling Water Components)

Storage Tank)

Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 C Components (Tube Smeet) _ (External) and Crevice Corrosion (Refueling Water Storage Tank)

Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,8 Components (Tube Sheet) (External) and Crevice Corrosion (Refueling Water Storage Tank) I

Enclosure B LR-N11-0148 Page 11 of 34 Table 3.2.2-3 Safety Injection System (Continued)

~~~- ~~-----~ -------- -------

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item Manaaement I

i------~~ ---- -------- ----~ --------

Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 C Components (Tubes) (External) and Crevice Corrosion (Refueling Water Storage Tank) ~~~~~~~ ------ -------

Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,B Components (Tubes) (External) and Crevice Corrosion (Refueling Water'

,.

~"(I!lF!Tank) 'i ---- r-----~ ------ f----~~ ~~-

Piping and Fittings Pressure Boundary Stainless Steel Treated Borated Water Loss of Matbrial/Pitting Water Chemistry V.D1-30 3.2.1-49 A

~~- --------

(Internal) and CreviceCofrosion Piping and Pressure Boundary Stainless Steel Treated Borated Wate, Loss of Material/Pitting One- Time Inspection V.D1-30 3.2.1-49 E,B Fittings (Interna/) and Crevice Corrosion --------

Piping and Fittings Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry V.D1-31 3.2.1-48 A (Internal) > 140 F .... Cracf{lna Piping and Pressure Boundary Stainless Steel Treated Bor~ted Water Cracki"gtStress One- Time Inspection V.D1-31 3.2.1-48 E,B Fittings (Internal)>: 14.() F Corrosirli'Pcrackina ~~-

Piping and Fittings Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.149 A (Internal) > 140F and Crevice Corrosion ----- --~~ ------ ~~~~~~~ ~-~~ ------ ~~~~~~~~ ------

Piping and Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,B Fittings (Internal) > 140.F and Crevice Corrosion

--~~

. -------- ----~~

Pump Casing Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A (RWST Heating (fnternal) and Crevice Corrosion Circulator) ---- ** -~ ~~~-

Pump Casing Pressure Boundary Stainless Steel Trea~~d Borated Watel Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,B (RWST Heating (Internal) and Crevice Corrosion

---.f!rculator) ------ ---- --~~ ---

Pump Casing Pressure Boundary Stainless Steel TreatecU:lorated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A (Safety Inj~l::~ Clhternal) ~nd Crevh;e Corrosion ------ ~~~~~-

~~~~-

Pump Casing Pressure Boundary Stainless Steel Treated ~rated Wate, Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E, B (Safety Injection) (Internal) and Crevice Corrosion

Enclosure B LR-N11-0148 Page 12 of 34 Table 3.2.2-3 Safety Injection System (Continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item Management Restricting Orifices Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A (Internal) and Crevice Corrosion Restricting Pressure Boundary Stainless Steel Treated Borated Wate, Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,8 Orifices (lnterna/) and Crevice Corrosion Restricting Orifices Throttle Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A (Internal) and Crevice Corrosion Restricting Throttle Stainless Steel Treated Borated Wate, Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,8 Orifices (lnterna/) and Crevice Corrosion Strainer Body Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A (Internal) and Crevice Corrosion

<"

Strainer Body Pressure Boundary Stainless Steel Treated Borated Wale, Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,8 (lnterna/) and Crevice Corrosion Tanks (Boron Pressure Boundary Carbon or Low Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A Injection Tank) Alloy Steel with (Internal) and Crevice Corrosion Stainless Steel Cladding Tanks (Boron Pressure Boundary Carbon or Low Treated BoratedWatel Loss of Material/Pitting One- Time Inspection V.D1-30 3.2.1-49 E,8 Injection Tank) Alloy Steel with (Internal) and Crevice Corrosion Stainless Steel Cladding Tanks (Refueling Pressure Boundary Stainless Steel Treated Borated Water Loss ofMaterial/Pitting Water Chemistry V.D1-30 3.2.1-49 A Water Storage (Internal) and Crevice Corrosion Tank)  :

Tanks (Refueling Pressure Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,8 Water Storage (Internal) and Crevice Corrosion Tank) c" Tanks (Safety Pressure Boundary Carbon or Low Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A Injection Alloy Steel with (Internal) and Crevice Corrosion Accumulators) Stainless Steel Cladding  :'

Tanks (Safety Pressure Boundary Carbon or Low Treated Borated Watel Loss of Material/Pitting One-Time Inspection V.D1-30 3.2.1-49 E,8 Injection Alloy Steel with (Internal) and Crevice Corrosion Accumulators) Stainless Steel Cladding

Enclosure B LR-N11-0148 Page 13 of 34 Table 3.2.2-3 Safety Injection System (Continued)

---------

Component Intended Material Environment Aging Effect Aging. Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item Management Valve Body Pressure Boundary Carbon or Low Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A Alloy Steel with (Internal) and Crevice Corrosion Stainless Steel I

Cladding Valve Body Pressure Boundary Carbon or Low Treated Borated Wate, Loss of Material/Pitting One-Time Inspection V.01-30 3.2.1-49 E,8 Alloy Steel with (Internal) and Crevic(f Corrosion Stainless Steel Cladding ---------

,.;.'

Valve Body Pressure Boundary Cast Austenitic Treated Borated Water Cracking/Str~~s Corrosion Water Chemistry V.D1-31 3.2.1-48 A Stainless Steel (Internal) > 140 F Cracking (CASS)

- r-- I Valve Body Pressure Boundary Cast Austenitic Treated Borated Watet Cracking/Stress One-Time Inspection V.01-31 3.2.1-48 E,8 Stainless Steel (Internal) > 140 F .*.*.* CorrosiOn Cracking

- ---------

(CASS)  ::

Valve Body Pressure Boundary Cast Austenitic Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A Stainless Steel (Internal) > 140 F and Crevice Corrosion

{gASS) ------- ------

Valve Body Pressure Boundary Cast Austenitic Treated Borated Watel Loss 01 Material/Pitting One-Time Inspection V.01-30 3.2.1-49 E,8 Stainless Steel (Internal) > 140 F and Crevice Corrosion

(CASS)

Valve Body Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A

(I;ntemal) and Crevice Corrosion Valve Body Pressure Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection V.01-30 3.2.1-49 E,8

EH (Internal) and Crevice Corrosion H-- ------

Valve Body Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry V.D1-31 3.2.1-48 A (Internal) > 140F Cracking --------- ------

Valve Body Pressure Boundary Stainless Steel Treated Borated Wate, Cracking/Stress One-Time Inspection V.01-31 3.2.1-48 E,B (lnterrlal) > 140 F Corrosion Cracking ---------

Valve Body Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry V.D1-30 3.2.1-49 A (Internal) > 140 F and Crevice Corrosion --------

Valve Body Pressure Boundary Stainless Steel Treated Borated Wate, Loss of Material/Pitting One-Time Inspection V.01-30 3.2.1-49 E,8 (Internal) > 140 F and Crevice Corrosion --------- -----,-- --------

Plant Specific Notes:

Enclosure B LR-N11-0148 Page 14 of 34

8. The One- Time Inspection program will be used to verify the effectiveness of the Water Chemistry program in managing the aging effects for stainless steel components in a treated borated water environment, where dissolved oxygen may not be controlled to less than 100 ppb.

Enclosure B LR-N11-0148 Page 15 of 34 Table 3.3.1 Summary of Aging Management Evaluations for the Auxiliary Systems Item Component Aging Aging Further Discussion Number Effect/Mechanism Management Evaluation Programs Recommended 3.3.1-90 Stainless steel and steel Cracking due to Water Chemistry No Consistent with NUREG-1801. The Water Chemistry with stainless steel stress corrosion program, B.2.1.2, will be used to manage cracking cladding piping, piping cracking due to stress corrosion cracking of the stainless steel components, piping piping, pipingi~ponents, piping elements, heat elements, tanks, and fuel exchanger components, and tanks exposed to storage racks exposed to treated borated water >60*C (> 140°F) for the treated borated water Component Cooling System, Radwaste System, and

>60*C (>140°F) Sampling System.

The One-Time Inspection program will be used to verify the effectiveness of the Water Chemistry program to manage cracking of stainless steel components in the Component Cooling System, Radwaste System, and Sampling System, where dissolved oxygen may not be controlled to less than 100 ppb.

Enclosure B LR-N 11-0148 Page 16 of 34 Table 3.3.1 Summary of Aging Management Evaluations for the Auxiliary Systems Item Component Aging Aging Further Discussion Number Effect/Mechanism Management Evaluation Programs Recommended 3.3.1-91 Stainless steel and steel Loss of material due Water Chemistry No Consi$t~nt with NUREG-1801. The Water Chemistry with stainless steel to pitting and crevice program. B.2.1.2. will be used to manage loss of cladding piping. piping corrosion material dlle to pitting and crevice corrosion of the components. and piping stainless steel ard steel with stainless steel cladding elements exposed to piping, piping components. piping elements, heat treated borated water exchanger components, cranes and hoists, fuel storage racks, tanks. liners. penetration bellows and other structural components exposed to treated borated water for the Chemical & Volume Control System, Component Cooling System, Fuel Handling and Fuel Storage System, Radwaste System.

Sampling System, Spent Fuel Cooling System, Component Supports Commodity Group, Containment Structure, and Fuel Handling Building.

The One-Time Inspection program will be used to verify the effectiveness of the Water Chemistry program to manage loss of material in stainless steel components in the Component Cooling System, Fuel Handling and Fuel Storage System, Radwaste System, Sampling System, Spent Fuel Cooling System, Containment Structure, and Fuel Handling Building, where dissolved oxygen may not be controlled to less than 100 ppb.

Components in the Component Supports Commodity Group have been aligned to this item number based upon material, environment and aging effect. The ASME Section XI, Subsection IWF program, B.2.1.30, will be added to manage loss of material due to pitting and crevice corrosion for the support members, welds, bolted connections, and support anchorages to building structure for the Component Supports Commodity Group.

Enclosure B LR-N11-0148 Page 17 of 34 Table 3.3.2-5 Component Cooling System Component Intended Material Environment Aging Management NUREG-1801 Table 1 Item I Notes Type Function Programs Vol. 2 Item Heat Exchanger I Pressure Boundary Treated Borated Water I Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 C Components (Internal) > 140 F and Crevice Corrosion (Residual Heat Removal)

Heat Exchanger Pressure Boundary Carbon or Low ITreated Borated Wate1 Loss O..f..MateriallPitting lOne-Time Inspection I VII.E1-17 3.3.1-91 E,8 Components Alloy Steel with (Internal) > 140 F and Crevice Corrosion (Residual Heat Stainless Steel Removal) Cladding Tubesheet Heat Exchanger Pressure Boundary Carbon or Low Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 C Components Alloy Steel with (Internal) > 140 F *

  • and Crevice Corrosion (Residual Heat Stainless Steel Removal) Cladding (Tubeside Com onents Heat Exchanger Pressure Boundary Carbon or Low Treated BoratedWate Loss ofMateriaIIPifti~~ I* One-Time Inspection VII.E1-17 3.3.1-91 E,8 Components Alloy Steel with (Internal) >1'4'q..F and Crevice Corrosion (Residual Heat Stainless Steel Removal) Cladding (Tubeside Com onents)

I Heat Exchanger Components Pressure Boundary Stainless Steel (Tubes)

ITreated Borated Water I Loss of Material/Pitting I (Internal) > 140 F and Crevice Corrosion Water Chemistry VII.E1-17 3.3.1-91 C (Residual Heat WemOVal)

Heat Exchanger Ipressure BOUndaryl Stainless Steel ITreated Borated wate1 Loss of MateriallPitting lOne- Time Inspection I VII.E1-17 3.3.1-91 E, 8 Components (Tubes) (Internal) > 140 F and Crevice Corrosion (Residual Heat Removal)

Heat Exchanger I Pressure Boundary I Stainles~Steel .1 Treate.dBorated Water I Loss of Material/Pitting I Water Chemistry VII.E1-17 3.3.1-91 C Components (Tubes) (Internal) > 140 F and Crevice Corrosion (Sample)

Heat EXChangerlp;~ssure BOUndaryl Stainless Stee/lTreated Borated Wate~ Loss of MateriallPitting lOne-Time Inspection I VII.E1-17 3.3.1-91 E,8 Components (Tubes) (Internal) > 140 F ., and Crevice Corrosion I (Saf!JP~

Enclosure B LR-N11-0148 Page 18 of 34 Table 3.3.2-5 Component Cooling System (Continued)

~-- ---- --------,- ---- ---

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item

~--- ------ ------- ~---- ------ ------

Management Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII,E1-17 3.3.1-91 C Components (Seal (Tubes) (Internal) and Crevice Corrosion Coolers Charging/SI Pumps) ----

Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Watel Loss of MateriaVPitting One* Time Inspf1ction VII.E1-17 3.3.1-91 E,8 Components (Tubes) (Internal) and Crevice Corrosion (Seal Coolers*

Charging/SI Pumps) ,<

Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry VII,E1-20 3.3.1-90 C Components (Seal (Tubes) (Internal) > 140 Cracking Coolers-RHR '*'1 Pumps) ,,'c' Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Wate, Cracking/Stress One-Time Inspection VII.E1-20 3.3.1-90 E,8 Components (Tubes) (Internal)~J40 F Corrosion Cracking (Seal Coo/ers --

RHRPumps) ** -- ,------- ---- ----

Heat Exchanger Pressure Boundary Stainless Steel Treated BoratedWater Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 C Components (Seal (Tubes) (Internal) > 140 F and Crevice Corrosion Coolers-RHR

.c

---

Pumps) ---- ----

Heat Exchanger Pressure Boundary StainlessiSteel Treated80rated Watel Loss of Material/Pitting One- Time Inspection VII.E1-17 3.3.1-91 E,8 Components (Tubes) (Internal) > 140 F and Crevice Corrosion (Seal Coolers .-,  !>

RHRPumps) ----

Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 C Components (Tubes) (Internal) and Crevice Corrosion (Spent Fuel) ------ ------- -- r--------- ----

Heat Exchanger Pressure Boundary Stainless Steel TreatedBorated Watel Loss of Material/Pitting One-Time Inspection VII.E1-17 3.3.1-91 E,8 Components (Tubes). (Internal) and Crevice Corrosion (Spent Fuel)

Enclosure B LR-N11-0148 Page 19 of 34 Table 3.3.2-5 Component Cooling- System -

(Continued)

------

Component Intended Material Environment Aging Effect Aging. Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item f-------

Management .:

Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting ':i'.rl\"~l"" Chemistry VII.E1-17 3.3.1-91 C Components (Tubesheet) (Internal) and Crevice Corrosion (Spent Fuel) ---------

Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Wate, Loss of Materi;1I1Pitting One-Time Inspection VII.E1-17 3.3.1-91 E,8 Components (Tubesheet) (Internal) and Crevice Corrosion

~entFuel) :t/

Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Water Loss of MCiterialiPitting Water Chemistry VII,E1-17 3.3.1-91 C Components (Tubeside (Internal) and Crevioo:Corrosion (Spent Fuel) Components)

Heat Exchanger Pressure Boundary Stainless Steel Treated Borated Wate~ Loss of Materiallf'ittirig One-Time Inspection VII.E1-17 3.3.1-91 E,8 Components (Tubeside (Internal) and Crevice Corrosion (Spent Fuel) -------

Components) ~-- -------------- -------

Plant Specific Notes:

8. The One-Time Inspection program will be used to verifythe effective'l~iis of the Water Chemistry program in managing the aging effects for stainless steel components in a treated borated water: environm ent, where dissolved oxygen may not be controlled to less than 100 ppb.

Enclosure B LR-N11-0148 Page 20 of 34 Table 3.3.2-14 Fuel Handling & Fuel Storage System Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item

- --------------

Management Bolting Structural Support Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.A2-1 3.3.1-91 C Bolting (External) and Crevice Corrosion Bolting Structural Support Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection VII.A2-1 3.3.1-91 E,9 Boiting (External) and Crevice Corrosion Crane/hoist Structural Support Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII,A2-1 3.3.1-91 C (Grapple/Mast for (External) and Crevice Corrosion all Fuel Handling Cranes)

Crane/hoist Structural Support Stainless Steel Treated Borated Wate, Loss of Material/Pitting One-Time Inspection VII. A 2-1 3.3.1-91 E,9 (Grapple/Mast for (External) and Crevice Corrosion all Fuel Handling Cranes) ---------

Crane/hoist (New Structural Support Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII,A2-1 3.3.1-91 C

  • Fuel Elevator) (External) and Crevice Corrosion ---------

Crane/hoist (New Structural Support Stainless Steel TreatedBprated Watel Loss of Material/Pitting One-Time Inspection VII.A2-1 3.3.1-91 E,9 Fuel Elevator) -------------

(Ex(ernafJ and Crevice Corrosion Fuel Storage Structural Support Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII,A2-1 3.3.1-91 C Racks (Spent Fuel) ------------

(External} and Crevice Corrosion

Fuel Storage Structural Support Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection VII.A2-1 3.3.1-91 E,9 Racks (Spent (External) and Crevice Corrosion Fuel) ,';;: ---------

Piping and Fittings Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.A2-1 3.3.1-91 A (External) and Crevice Corrosion

-------------

Piping and Pressure Boundary . Stainless Steel Treated Borated Wate, Loss of Material/Pitting One- Time Inspection VII.A2-1 3.3.1-91 E,9 Fitting~ (External) and Crevice Corrosion Piping and Fittings Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII,A2-1 3.3.1-91 A (Internal) and Crevice Corrosion Piping and Pressure Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection VII.A2-1 3.3.1-91 E,9 Fittings (Int~r,,~/) and Crevice Corrosion ---------

Enclosure B LR-N11-0148 Page 21 of 34 Table 3.3.2-14 Fuel Handling & Fuel Storage System (Continued)

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item Management Valve Body Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.A2-1 3.3.1-91 A (External) and Crevice Corrosion Valve Body Pressure Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection VII.A2-1 3.3.1-91 E,9 (External) and Crevice Corrosion

.:'

Valve Body Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.A2-1 3.3.1-91 A (Internal) and Crevice Corrosion Valve Body Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting One-Time Inspection VII.A2-1 3.3.1-91 E,9 (Internal) and Crevice Corrosion Plant Specific Notes:

9. The One-Time Inspection program will be used to verify the effectiveness of the Water Chemistry program in managing the aging effects for stainless steel components in a treated borated water environment, where dissolved oxygen may not be controlled to less than 100 ppb.

Enclosure B LR-N11-0148 Page 22 of 34 Table 3.3.2-21 Radwaste System

------------ ------------

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item Management --------

Flow Element Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 A (Internal) and Crevice Corrosion Flow Element Leakage Boundary Stainless Steel Treated Borated Wate, Loss of MateriaVPitting One-Time Inspection VII.E1-17 3.3.1-91 E,4 (Internal) and

Crevice7Y Corrdsion Piping and Fittings Leakage Boundary Stainless Steel Treated Borated Water Cracking/Stress.Corrosion Water Chemistry VII.E1-20 3.3.1-90 A (External) > 140 F Cracll.inQ Piping and Leakage Boundary Stainless Steel Treated Borated Wate, Cracking/Stress One-Time Inspection VII.E1-20 3.3.1-90 E,4

_ Fittings .....

(External) > 140 F Corrosion Crackina Piping and Fittings Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 A (External) > 140 F and Crevice Corrosion ------------

Piping and Leakage Boundary Stainless Steel Treated Borated Wate, Loss of Material/Pitting One-Time Inspection VII.E1-17 3.3.1-91 E,4 Fittings (External) > 140 F and Crevice Corrosion Piping and Fittings Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 A (Internal) and Crevice CorfQsion --------

-c-Piping and Leakage Boundary Stainless Steel Treated Borated Watet Loss of Material/Pitting One-Time Inspection VII.E1-17 3.3.1-91 E,4 Fittings (Internal). and Crevice Corrosion Piping and Fittings Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 A (Internal) and Crevice Corrosion Piping and Pressure Boundary Stainless Steel Treated BoratedWatet Loss of Material/Pitting One-Time Inspection VII.E1-17 3.3.1-91 E,4 Fittings (Internal) and Crevice Corrosion Pump Casing Leakage Boundary StainlessSteel Treated Borated Water Cracking/Stress Corrosion Water Chemistry VII.E1-20 3.3.1-90 A (Reactor Coolant (I ntel113ll?' 140 F Cracking Drain) -------- ------------

Pump Casing Leakage Boundary Stainless Steel Treated Borated Water Cracking/Stress One-Time Inspection VII.E1-20 3.3.1-90 E,4 (Reactor Coolant (Internal) > 140 F Corrosion Cracking Drain) ------------

Pump Casing Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 A (Reactor Coolant (Internal) > 140 F and Crevice Corrosion Drain)

Pump Casing Leakage Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection VII.E1-17 3.3.1-91 E,4 (Reactor Coolant (Internal) > 140 F and Crevice Corrosion Drain) ------------ ------------

Enclosure B LR-N11-0148 Page 23 of 34 Table 3.3.2-21 Radwaste System (Continued)

Tanks (Reactor Leakage Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry VII.E1-20 3.3.1-90 A Coolant Drain) (Internal) > 140 F CrackinQ Tanks (Reactor Leakage Boundary Stainless Steel Treated Borated Watel Cracking/Stress One-Time Inspection VII.E1-20 3.3.1-90 E,4 Coolant Drain) (Internal) > 140 F Corrosion Cracking Tanks (Reactor Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 C Coolant Drain) (Internal) > 140 F and Crevice Corrosion Tanks (Reactor Leakage Boundary Stainless Steel Treated Borated Wate, Loss of Material/Pitting One-Time Inspection VII.E1-17 3.3.1-91 E,4 Coolant Drain) (Internal) > 140 F and Crevice Corrosion Valve Body Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 A (Internal) and Crevice Corrosion Valve Body Leakage Boundary Stainless Steel Treated Borated Wate, Loss of Material/Pitting One-Time Inspectior, VII.E1-17 3.3.1-91 E,4 (Internal) and Crevice CorroSIon Valve Body Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 A (Internal) < " and Crevice Corrosion' Valve Body Pressure Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection VII.E1-17 3.3.1-91 E,4 (Internal) and Crevice Corrosion Plant Specific Notes:

4. The One-Time Inspection program will be used to verify the effectiveness of the Water Chemistry program in managing the aging effects for stainless steel components in a treated borated water environment, where dissolved oxygen may not be controlled to less than 100 ppb.

Enclosure B LR-N11-0148 Page 24 of 34 Table 3.3.2-22 Sampling System Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item Management Piping and Fittings Leakage Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Chemistry VII.E1-17 3.3.1-91 A (Internal) > 140 F Crac;i<il1fL.---'.

Piping and Leakage Boundary Stainless Steel Treated Borated Wate, Cracking/Stress One~Time Inspection VII.E1-17 3.3.1-91 E,4 Fittings (Internal) > 140 F Corrosion Cracking Piping and Fittings Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-20 3.3.1-90 A (Internal) > 140 F and Crevice Corrosion Piping and Leakage Boundary Stainless Steel Treated Borated Water Loss of Ma,terial/Pitting One-Time Inspection VII.E1-20 3.3.1-90 E,4 Fittings (Internal) > 140 F and Crevice Corrosion Piping and Fittings Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry VII.E1-20 3.3.1-90 A (Internal) > 140 F Cracking Piping and Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress One-Time Inspection VII.E1-20 3.3.1-90 E,4 Fittings (Intern a/) > 140 F CorrOsion Cracking Piping and Fittings Pressure Boundary Stainless Steel Treated Borated Water .* Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 A (Internal) > 140 F and Crevice Corrosion Piping and Pressure Boundary Stainless Steel Tre;i1J!itl,Borated Water L~s of MateriaVPitting One-Time Inspection VII.E1-17 3.3.1-91 E,4 Fittings ,(tn.ternal) > 140 F and Crevice Corrosion Sink Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 C (I nternal)';; and Crevice Corrosion Sink Leakage Boundary Stainless Steel Treated Borate~iWatel' Loss of Material/Pitting One-Time Inspection VII.E1-17 3.3.1-91 E,4

, (lnternalf . and Crevice Corrosion Valve Body Leakage Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry VII.E1-20 3.3.1-90 A

" ......... (Internal) > 140 F Cracking Valve Body Leakage Boundary Stainless Steel Treated Borated Water Cracking/Stress One-Time Inspection VII.E1-20 3.3.1-90 E,4 (Interna/) > 140 F Corrosion Cracking Valve Body Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 A (Internal) > 140 F and Crevice Corrosion Valve Body Leakage Boundary Stainless Steel Treated Borated Wafe! Loss of MateriallPitting One-Time Inspection VII.E1-17 3.3.1-91 E,4 (Internal) > 140 F and Crevice Corrosion

Enclosure B LR-N11-0148 Page 25 of 34 Table 3.3.2-22 Sampling System (Continued)

,---------

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item Management Valve Body Pressure Boundary Stainless Steel Treated Borated Water Cracking/Stress Corrosion Water Chemistry VII.E1-20 3.3.1-90 A (Internal) > 140 F Cracking Valve Body Pressure Boundary Stainless Steel Treated Borated Watel Cracking/Stre§s One* Time Inspection VlI.E1*20 3.3.1-90 E,4 (Internal) > 140 F Corrosion Cracking Valve Body Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.E1-17 3.3.1-91 A (Internal) > 140 F and Crevice Corrosion Valve Body Pressure Boundary Stainless Steel Treated Borated Wate! Loss ofMaJeriallPitting , One-Time Inspection VII.E1-17 3.3.1-91 E,4 (Internal) > 140 F and Crevice Corrosion Plant Specific Notes:

4. The One-Time Inspection program will be used to verify the effectiveness of the Water Chemistry program in managing the aging effects for stainless steel components in a treated borated water environment, where dissolved oxygen may not be controlled to less than 100 ppb.

Enclosure 8 LR-N11-0148 Page 26 of 34 Table 3.3.2-25 Spent Fuel Cooling System

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item

------- -------

Management Filter Housing Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.A3-8 3.3.1-91 A

(internal) and Crevice Corrosion Filter Housing Leakage Boundary Stainless Steel Treated Borated Watet Loss of MateriaUPitting One-Time Inspection VII.A3-8 3.3.1-91 E,2 (Internal) and Crevice Corrosion Flow Element Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.A3-8 3.3.1-91 A

---

(Internal) and Crevice Corrosion Flow Element Leakage Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection VII.A3-8 3.3.1-91 E,2

,--- (Internal) and Crevice Corrosion -------- --------

Piping and Fittings Leakage Boundary Stainless Steel Treated Borated Water Loss of MateriallPittii:1g Water Chemistry VII.A3-8 3.3.1-91 A

(Internal) and Crevice Corrosion Piping and Leakage Boundary Stainless Steel Treated Borated Watel Loss of MateriaUPitting One-Time Inspection VII.A3-8 3.3.1-91 E,2 Fittings (Internal) and Crevice Corrosion -----------

Piping and Fittings Pressure Boundary Stainless Steel Treated Borated Water .Loss of Material/Pitting Water Chemistry VII.A3-8 3.3.1-91 A

(Internal) . and Crevice Corrosion Piping and Pressure Boundary Stainless Steel Trea(~Borated Watet Loss of Material/Pitting One-Time Inspection VII.A3-8 3.3.1-91 E,2 Fittings , . (Internal) and. Crevlcec;orrosiCJ.TI~ ._-- -------

Pump Casing Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.A3-8 3.3.1-91 A (Purification Pump) , (Internal) and Crevice Corro~iol!..... --- ----------- -----------

Pump Casing Leakage Boundary Stainless Steel Treated Borated Watet Loss of Material/Pitting One-Time Inspection VII. A 3-8 3.3.1-91 E,2 (Purification (Internal) -and Crevice Corrosion Pump) -------

Pump Casing Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.A3-8 3.3.1-91 A (Skimmer Pump) (Internal) and Crevice Corrosion -----------

Pump Casing Leakage Boundary Stainless Steel Treated Borated Watel Loss of Material/Pitting One-Time Inspection VII.A3-8 3.3.1-91 E,2 J§1<l!rltr1er Pump) (Internal) and Crevice Corrosion I Pump Casing Pressure Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VII.A3-8 3.3.1-91 A (Spent Fuel (Internal) and Crevice Corrosion Cooling Pump) ----------

Pump Casing Pressure Boundary Stainless Steel Treated Borated Watet Loss of Material/Pitting One-Time Inspection VII. A 3-8 3.3.1-91 E,2 (Spent Fuel (Internal) and Crevice Corrosion Cooling Pump) ---------- -----

Enclosure B LR-N11-0148 Page 27 of 34 Table 3.3.2-25 Spent Fuel Cooling System (Continued)

I C~rt1~~nent Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item Management -------

Strainer Body Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting .* Water Chemistry VILA3-8 3.3.1-91 A (Internal) and Crevice Corrosion ----------

Strainer Body Leakage Boundary Stainless Steel Treated Borated Watel Loss of MateriaUPitting One- Time Inspection VII.A3-8 3.3.1-91 E,2 (internal) and Crevice Corrosion Tanks Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VILA3-8 3.3.1-91 C (Demineralizer) --------

(Internal) and Crevice Corrosion Tanks Leakage Boundary Stainless Steel Treated Borated Wate, Loss of Material/Pitting One-Time Inspection VII.A3-8 3.3.1-91 E,2 (Demineralizer) _(!nternall and Crevice Corrosion Thermowell Pressure Boundary Stainless Steel Treated Borated Water Loss of MateriallPjffing Water Chemistry VILA3-8 3.3.1-91 A

(Internal) and Crevice Corrosion Thermowell Pressure Boundary Stainless Steel Treated Borated Wate, Loss of MateriaUPitting One- Time Inspection VII.A3-8 3.3.1-91 E,2 1---

(Internal) and Crevice Corrosion Valve Body Leakage Boundary Stainless Steel Treated Borated Water Loss of Material/Pitting Water Chemistry VILA3-8 3.3.1-91 A (Internal) and Crevice Corrosion -------

Valve Body Leakage Boundary Stainless Steel Treated Borated Wate, Loss of Material/Pitting One-Time Inspection VII.A3-8 3.3.1-91 E,2

--------------

(internal) and Crevice Corrosion ----------

Valve Body Pressure Boundary Stainless Steel Treated Borated:Water Loss of Material/Pitting Water Chemistry VII.A3-8 3.3.1-91 A (Internal) and Crevice Corrosion Valve Body Pressure Boundary Stainless Steel Treated BoratedWatel Loss of Material/Pitting One- Time Inspection VII.A3-8 3.3.1-91 E,2 1.....---------- _________________

(Internal) land Crevice Corrosion ----------

Plant Specific Notes:

2. The One- Time Inspection program will be used to verify the effectiveness of the Water Chemistry program in managing the aging effects for stainless steel components in a treated borated water environment, where dissolved oxygen may not be controlled to less than 100 ppb.

Enclosure B LR-N11-0148 Page 28 of 34 Table 3.5.2-3 Containment Structure

Type Function Requiring Programs Vol. 2 Item r-----

Management ----

Penetration Structural Support Stainless Steel Treated Borated Water Loss of Material/Pittingrl< Water Chemistry VII.A2-1 3.3.1-91 C sleeves (cap and Crevice Corrosion I r--- plates} r--- ---- --

Penetration Structural Support Stainless Steel Treated Borated Watel Loss of MateriaVPitting One-Time Inspection VII.A2-1 3.3.1-91 E,15 sleeves (cap and Crevice Corrosion plates) ------ ----- - - - - - - - ------

Steel Components: Water retaining Stainless Steel Treated Borated Water Loss ofMateria II Pitting Water Chemistry VII.A2-1 3.3.1-91 C Reactor cavity boundary and CreVice Corrosion en. .,

liner, Fuel Transfer Canal liner ------

<';>' ------ -----

Steel Water retaining Stainless Steel Treated Borated Wate, Loss of Material/Pit:tlng One-Time Inspection VII.A2-1 3.3.1-91 E,15 Components: boundary aJj~.Crevice Corrosion Reactor cavity liner, Fuel Transfer Canal liner ------

Transfer Tube: Water retaining Stainless Steel Treated BoratedWater L6SS o(Material/Pitting Water Chemistry VII.A2-1 3.3.1-91 C Bellows (excludes boundary and Crevice Corrosion containment penetration

, bellows) ------

.'.' , ------

Transfer Tube: Water retaining Stainless Steel Trea,ted Borated Wate1 ;L~s of /lAaterial/Pitting One- Time Inspection VII.A2-1 3.3.1-91 E,15 Bellows (excludes boundary and Crevice Corrosion containment ii!'

penetration bellows) ----~---- --

Plant Specific Notes:

15. The One- Time Inspection program will be used to;; verify the effectiveness of the Water Chemistry program in managing the aging effects for stainless steel components in a treatedborated;;vr.ater environment, where dissolved oxygen may not be controlled to less than 100 ppb.

Enclosure B LR-N11-0148 Page 29 of 34 Table 3.5.2-5 Fuel Handling Building-

---~-- ---

Component Intended Material Environment Aging Effect Aging Management NUREG-1801 Table 1 Item Notes Type Function Requiring Programs Vol. 2 Item

Manaaement iT: --- f--- ------

Penetration bellows Water retaining Stainless Steel Treated Borated Water Loss of Material/Pitting Chemistry VII.A2-1 3.3.1-91 C (2 bellows for boundary and Crevice Corrosion Transfer tube; excluding containment penetration bellows) -;,;; -'i:_

----

Penetration Water retaining Stainless Steel Treated Borated Wate, Loss of M/lteriaIlPitting, One-Time Inspection VII.A2-1 3.3.1-91 C bellows (2 boundary and Creiiice'Corrosioif.

bellows for Transfer tube; excluding ,.

containment ';';' ..

penetration bellows) ,

Steel components: Direct Flow Stainless Steel Treated Borated Water l.O!?S of Matflrial/Pitting Water Chemistry VII.A3-8 3.3.1-91 C Leak chase system arid CreviceCorroskin .:;; --

Steel Direct Flow Stainless Steel TreiJted Borated Wate, Loss of Material/Pitting One-Time Inspection VII.A3-B 3.3.1-91 C components: and Crevice Co"osion Leak chase "

system ---- -----

Plant Specific Notes:

10. The One-Time Inspection program will be us~d to Verify the effectiveness of the Water Chemistry program in managing the aging effects for stainless steel components in a treated borated water environment, where dissolved oxygen may not be controlled to less than 100 ppb.

Enclosure B LR-N11-0148 Page 30 of 34 A.2.1.2 Water Chemistry The Salem Water Chemistry aging management program is an existing program that provides activities for monitoring and controlling the chemical environments of the Salem primary cycle and secondary cycle systems such that aging effects of system components are minimized. Aging effects include cracking, loss of material, reduction of neutron absorbing capacity and reduction of heat transfer. The primary cycle scope of this program consists of the reactor coolant system and related auxiliary systems containing treated water, reactor coolant, treated borated water and steam, including the primary side of the steam generators that contain treated water and steam. Th~secondary cycle portion of the program consists of the various secondary side systems and the secondary side of the steam generators. Major component types include reacto[Vessel, reactor internals, piping, piping elements and piping components, heat exchangers andtanks. The Water Chemistry aging management program is consistent with EPRI, Pressurized Water Reactor Primary Chemistry Guidelines, and Plant UFSAR limits for fluorides, chlorides, and dissolved oxygen. The Water Chemistry program is consi$tent with EPRI, Pressurized Water Secondary Water Chemistry Guidelines.

The One-Time Inspection program will be.Llsed to verify the effectiveness of the Water Chemistry program in managing thij',igil)geffects for stainless steel components in a treated borated water environment. where dissolved oxygen may not be controlled to less than:10Qppp.

A.2.1.20 One-Time Inspection The One-Time Inspection ~ging manag~rr!ent program is a new program that will provide reasonable as,t\~rance that aOc,qging effe~~is not occurring, or that the aging effect is occurring slowh enough to nptaffect a component intended function during the period of extended operation, ' and therefore will not require additional aging management. The program will be credited f()rcasesWh~~~eiJher (a) an aging effect is not expected to occur buttl]EH'eis il1sufficientdata to completelY rule it out, (b) an aging effect is expected to progress very> slowly in the specified environment, but the local environment may be more adverse than that generally expected, or (c) the characteristics of the aging effect include a lOng incubation period. MajorComponent types covered by the program include, piping, piping elements and 'piping components, steam generators, heat exchangers and tanks.

TheOne-Time Inspection aging management program will be used for the following:

1. To cOrl~rm the effectiveness of the Water Chemistry program to manage the loss of material,qracklng, and the reduction of heat transfer aging effects for aluminum, copper alloy, steeti, stSJnless steel, and cast austenitic stainless steel in treated water, treated borated water where dissolved oxygen may not be controlled to less than 100 ppb, steam, and reactor coolant environments.
2. To confirm the effectiveness of the Fuel Oil Chemistry program to manage the loss of material aging effect for aluminum, copper alloy, gray cast iron, steel and stainless steel in a fuel oil environment.
3. To confirm the effectiveness of the Lubricating Oil Analysis program to manage the loss of material and the reduction of heat transfer aging effects for aluminum, copper alloy,

Enclosure B LR-N11-0148 Page 31 of 34 ductile cast iron, gray cast iron, steel, stainless steel, cast austenitic stainless steel and titanium alloy in a lubricating oil environment.

The sample plan for inspections associated with the One-Time Inspection program will be developed to ensure there are adequate inspections to address each of the material, environment, and aging effect combinations. A sample size of 20% of the population (up to a maximum of 25 inspections) will be established for each of the sample groups. Inspection methods will include visual examination or volumetric examinations. Acceptance criteria are in accordance with industry guidelines, codes, and standards, including the applicable edition of ASME Boiler and Pressure Vessel Code, Section XL."The One-Time Inspection program provides for the evaluation of the need for follow-up,,~xaminations to monitor the progression of aging if age-related degradation is found that. could jeopardize an intended function before the end of the period of extended operation: Should aging effects be detected, the program triggers actions to characteriz~the nature and extent of the aging effect and determines what subsequent monitoringjs needed to ensure intended functions are maintained during the period of extended operation.

The new program, including performanceqf physical inspections and evaluation of results, will be implemented prior to the period of'extended operation.

Enclosure 8 LR-N11-0148 Page 32 of 34 A.5 License Renewal Comm itment List UFSAR SUPPLEMENT ENHANCEMENT OR NO. PROGRAM OR TOPIC COMMITMENT ,LOCATION I.MPLEMENTATION SOURCE (LRAAPP. A) SCHEDULE Section 8.2.1.20 20 I One-Time Inspection One-Time Inspection is a new program and will I A.2.1.20 Program to be be used for the following: implemented prior to the Salem Letter period of extended

1. To confirm the effectiveness of the LR-N 11-0005 operation. One-time Water Chemistry program to manage RAI 8.2.1.20-01 inspections to be the loss of material, cracldng, and the performed within the ten reduction of heat transfer aging'effects year period prior to the for aluminum, copper alloy,. nickel period of extended alloy, steel, stainless steel,at1d cast operation.

austenitic stainless steel in treated water, treatecCbmrated water Wl}ere dissolved oxygen may not be Salem Letter con~lIed to less than 100 ppb, LR-N11-0148

$team, and reactor coolant DRAI 3.2.1.48

'environments.

2. To confirm the effectiveness of the Fuel Oil Chemistry program to manage the.loss of material aging effeg for alUminum, copper alloy. gray casHrolJ, steel and stainless steel in a fuel oifenviron
3. To confirm the effectiveness of the LubricatintirOil Analysis program to manage the loss of material and the reduction ofheat transfer aging effects for aluminum~ copper alloy, ductile cast iron,gray cast iron, steel, stainless steel. cast austenitic stainless steel and titanium allov in a lubricatina oil

Enclosure B LR-N11-0148 Page 33 of 34 UFSAR SUPPLEMENT ENHANCEMENT OR NO. PROGRAM OR TOPIC COMMITMENT LOCATION IMPLEMENTATION SOURCE (LRA APP. A) SCHEDULE environment.

The sample plan for inspections associated with the One-Time Inspection program will be developed to ensure there are adequate inspections to address each of the material; environment, and aging effect combinations. A sample size of 20% of the population (up to a maximum of 25 inspections) will be established for each of the sample groups.

-3 B.2.1.2 WATER CHEMISTRY Program Description The Salem Water Chemistry aging management program is an existing program that provides activities for monitoring and controlling the chemical environments of the Salem primary cycle and secondary cycle systems such that aging effects of system components are minimized. This program manages the aging effects of cracking, loss of material, reduction of neutron-absorbing capacity and reduction of heat transfer. The program mitigates damage caused by corrosion and stress corrosion cracking (SCC) and other aging mechanisms. This program includes provisions specified by NUREG-1801 for the verification of proper chemistry control and aging management, such that the intended functions of plant components will be maintained during the period of extended operation for Salem.

The primary scope of this program consists of the reactor coolant system and related auxiliary systems containing treated water, reactor coolant, treated borated water and steam, including the primary side of the steam generators. Major component types include reactor vessel, reactor internals, piping, piping elements and piping components, heat exchangers and tanks. The primary water portion of the program is consistent with the EPRI 1014986, PWR Primary Water Chemistry Guidelines, Revision 6 and includes UFSAR limits for fluorides, chlorides, and dissolved oxygen. The secondary cycle scope of the program includes the various secondary side systems and the secondary side of the steam generators that contain treated water or steam. The secondary water portion of this program is consistent with the EPRI 1008224, PWR Secondary Water Chemistry Guidelines, Revision 6.

The Salem Water Chemistry aging management program includes periodic sampling of primary and secondary water for the known detrimental contaminants specified in the EPRI PWR water chemistry guidelines, such as chlorides, fluorides, dissolved oxygen, and sulfates, to maintain their concentrations below levels known to result in loss of material or cracking.

Sampling frequencies and action limits for each control parameter are defined in Salem specific procedures.

Salem follows the guidance set forth in EPRI 1014986, PWR Primary Water Chemistry Guidelines, Revision 6 and the EPRI 1008224, PWR Secondary Water Chemistry Guidelines, Revision 6, which are later revisions to the guidelines referenced in NUREG-1801, XI.M2 (EPRI TR-105714 and EPRI102134). However, NUREG-1801, XI.M2 states that later revisions are acceptable. The primary water portion of the program is consistent with the EPRI1014986, PWR Primary Water Chemistry Guidelines, Revision 6 and includes Plant UFSAR limits for fluorides, chlorides, and dissolved oxygen. The chemistry control strategy for Salem primary water systems, including the reactor coolant system and related auxiliary systems containing reactor coolant and treated borated water, is defined in the primary strategic water chemistry plan for recirculating steam generator plants. This program includes routine sampling of specific chemical control parameters

-4 including chloride, fluoride, sulfate, sodium, dissolved oxygen, hydrogen, and other parameters. The program functions to maintain these concentrations below recommended levels to mitigate SCC of austenitic stainless steel, Alloy 600, and Alloy 690 components in accordance with the EPRI guidelines. Additionally, limits are specified for chemistry parameters associated with PWR auxiliary systems and components, including the boric acid storage tanks, volume control tank, spent fuel pool, and other primary side auxiliaries. Routine control of reactor coolant and related auxiliary system contaminants is maintained by using submicron filters and mixed bed demineralizers, which provide mechanical filtration and ion exchange functions to remove contaminants. Lithium hydroxide addition is used to control reactor coolant pH, while hydrogen addition is utilized for oxygen scavenging.

Similarly, chemical control of the secondary water systems is consistent with the EPRI 1008224, PWR Secondary Water Chemistry Guidelines, Revision 6. Chemistry control for Salem secondary water systems is defined in the secondary water strategic chemistry plan for recirculating steam generator plants. The secondary cycle scope of the program includes the various secondary side systems and the secondary side of the steam generators. Chemical control of the Salem secondary water systems is established and maintained by removing contaminants with condensate demineralizers combined with steam generator blowdown. This program includes routine sampling of specific chemical control parameters including chloride, sulfate, sodium, hydrazine, dissolved oxygen, silica, total iron, pH, cation conductivity, and other parameters to mitigate steam generator tube degradation cause by denting, intergranular attack (IGA), outside diameter stress corrosion cracking (OOSCC), or crevice and pitting corrosion. Monitoring and control of these parameters is also intended to mitigate general, crevice, and pitting corrosion of the steam generator shell and secondary side plant components. Routine control of secondary water system contaminants is maintained by using condensate mixed bed demineralizers and steam generator blowdown. Volatile chemical addition, including use of an approved amine, is utilized for pH control. Hydrazine is used to scavenge oxygen in secondary water systems.

Routine primary and secondary system sampling frequencies and action limits for each control parameter are specified in station procedures in accordance with EPRI water chemistry guidelines. Critical parameters are monitored continuously while non-critical parameters have defined monitoring frequencies. For primary water systems, parameter-specific corrective actions include consideration of increased sampling frequencies until the parameters are returned to specifications. Increased sampling is considered and performed as required for primary and secondary system parameters with action level values. Increased sampling frequency is required when monitoring instruments are out of service in the feedwater and condensate systems.

Industry experience has shown that water chemistry programs may not be effective in low flow or stagnant flow areas of plant systems. The Water Chemistry aging management program does not provide for detection of aging effects. However, components located in selected areas at Salem, including in treated borated water systems where dissolved oxygen may not be controlled to less than 100 ppb. will receive a one-time visual inspection prior to the period of extended

-5 operation. This inspection will be performed as part of the Salem One-Time Inspection aging management program. This program includes provisions specified by NUREG-1801 for the verification of proper chemistry control and aging management; such that the intended functions of plant components will be maintained during the period of extend operation for Salem.

Site quality assurance procedures, review and approval processes, and administrative controls are implemented in accordance with the requirements of 10 CFR Part 50, Appendix B.

NUREG-1801 Consistency The Water Chemistry Program is consistent with the ten elements of aging management program XI.M2, "Water Chemistry Program", specified in NUREG-1801.

-6 B.2.1.20 ONE-TIME INSPECTION Program Description The One-Time Inspection aging management program is a new program that will provide reasonable assurance that an aging effect is not occurring, or that the aging effect is occurring slowly enough to not affect a components intended function during the period of extended operation, and therefore will not require additional aging management. The program will be credited for cases where either (a) an aging effect is not expected to occur but there is insufficient data to completely rule it out, (b) an aging effect is expected to progress very slowly in the specified environment, but the local environment may be more adverse than that generally expected, or (c) the characteristics of the aging effect include a long incubation period.

Major component types covered by the program include piping, piping elements and piping components, steam generators, heat exchangers and tanks.

The One-Time Inspection aging management program will be used for the following:

1. To confirm the effectiveness of the Water Chemistry program to manage the loss of material, cracking, and the reduction of heat transfer aging effects for aluminum, copper alloy, steel, stainless steel, and cast austenitic stainless steel in treated water, treated borated water where dissolved oxygen may not be controlled to less than 100 ppb, steam, and reactor coolant environments.
2. To confirm the effectiveness of the Fuel Oil Chemistry program to manage the loss of material aging effect for aluminum, copper alloy, gray cast iron, steel and stainless steel in a fuel oil environment.
3. To confirm the effectiveness of the Lubricating Oil Analysis program to manage the loss of material and the reduction of heat transfer aging effects for aluminum, copper alloy, ductile cast iron, gray cast iron, steel, stainless steel, cast austenitic stainless steel and titanium alloy in a lubricating oil environment.

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ML11139A346 *concurrence via email OFFICE LA:DLR* PM: DLRlRPB1 leC: DLRlRPB1 PM: DLRlRPB1 NAME SFigueroa SCuadrado BPham SCuadrado DATE 05/26/2011 05/25/2011 05/25/2011 05/26/2011

Letter to PSEG Nuclear from Samuel Cuadrado-De Jesus dated May 26, 2011

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MAY 10, 2011, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PSEG NUCLEAR, LLC, CONCERNING A DRAFT RESPONSE TO A DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2, (SALEM) LICENSE RENEWAL APPLICATION DISTRIBUTION:

HARD COPY:

DLR RlF E-MAIL:

PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RdsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsOgcMailCenter Resource BPham BBrady ACunanan SCuadrado LPerkins REnnis CSanders BHarris, OGC ABurritt, RI RConte, RI MModes, RI DTifft, RI NMcNamara, RI

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