View source for DCL-11-136, Annual Update to the DCPP License Renewal Application and License Renewal Application Amendment Number 45

{{Adams
| number = ML12009A070
| issue date = 12/21/2011
| title = Annual Update to the DCPP License Renewal Application and License Renewal Application Amendment Number 45
| author name = Becker J
| author affiliation = Pacific Gas &amp; Electric Co
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000275, 05000323
| license number = DPR-080, DPR-082
| contact person = 
| case reference number = DCL-11-136
| document type = Letter type:DCL, Report, Miscellaneous
| page count = 103
| project = 
| stage = Other
}}

=Text=
{{#Wiki_filter:Pacific Gas and Electric Company`                                                     James R.Becker         Diablo Canyon Power Plant Site Vice President    Mail Code 104/6 P. 0. Box 56 Avila Beach, CA 93424 December 21, 2011                                                                            805.545.3462 Internal: 691.3462 PG&E Letter DCL-1 1-136                                                                      Fax: 805.545.6445 U.S. Nuclear Regulatory Commission                                     10 CFR 54.21(b)
ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 10 CFR 54.21 (b) Annual Update to the DCPP License Renewal Application and License Renewal Application Amendment Number 45

==Dear Commissioners and Staff:==

By letter dated November 23, 2009, Pacific Gas and Electric Company (PG&E) submitted an application to the U.S. Nuclear Regulatory Commission (NRC) for the renewal of Facility Operating Licenses DPR-80 and DPR-82, for Diablo Canyon Power Plant (DCPP) Units 1 and 2, respectively. The application included the license renewal application (LRA), and Applicant's Environmental Report -
Operating License Renewal Stage. As required by 10 CFR 54.21(b), each year following submittal of the LRA, an amendment to the LRA must be submitted that identifies any change to the current licensing basis (CLB) that materially affects the contents of the LRA, including the Final Safety Analysis Report (FSAR) supplement.
Enclosure 1 identifies DCPP LRA changes that are being made to reflect CLB that materially affect the LRA. Enclosure 2 contains the affected LRA pages with changes shown as electronic mark-ups (deletions crossed out and insertions italicized). The LRA update covers the period from October 1, 2010, through September 30, 2011. As a reviewer aid, all pages of the Appendix B aging management program section are provided, including unchanged pages, when there is a change on any of the pages in that section.
Changes to existing commitments are contained in the changes to LRA Table A4-1 in Enclosure 2.
If you have any questions regarding this response, please contact Mr. Terence L. Grebel, License Renewal Project Manager, at (805) 545-4160.
A member  of  the STARS   (Strategic Teaming   and Resource    Sharing)     ALliance Catlaway
* Comanche Peak
* DiabLo Canyon
* Pato Verde
* San Onofre
* South Texas Project
* Wolf Creek

PG&E Letter DCL-11-136 December 21, 2011 Document Page 2       Control Desk I declare under penalty of perjury that the foregoing is true and correct.
Executed on December 21, 2011.
Sincerel ,
James R. Becker Site Vice President jwh/50412026 Enclosures cc:        Diablo Distribution cc/enc: Elmo E. Collins, NRC Region IV Regional Administrator Nathanial B. Ferrer, NRC Project Manager, License Renewal Michael S. Peck, NRC Senior Resident Inspector Alan B. Wang, NRC Licensing Project Manager A member  of the   STARS (Strategic Teaming   and Resource   Sharing) Atliance Cattaway
* Comanche Peak
* Diabto Canyon
* Palo Verde
* San Onofre
* South Texas Project
* Wolf Creek

PG&E Letter DCL-1 1-136 Page 1 of 2 DCPP License Renewal Application (LRA) Changes Reflected in the Annual LRA Update Amendment 45 Affected LRA Section                             Reason for Change Table 3.3.2-8             Completed. PG&E replaced the carbon steel with stainless steel Table A4-1, #23           clad Centrifugal Charging Pump (CCP) 2-2 pump casings in the Section 3.3.2.2.14        chemical and volume control system with a completely stainless steel pump casing.
Table A4-1, #71           Completed. The intake structure has been returned to (a)(2) status.
Section Al. 15            Updated to reflect the revised date for withdrawal of Unit 1 Section B2.1.15           Capsule B as approved in NRC letter dated October 29, 2010 (ML103010159).
Table 3.3.2-7             Updated to remove External Surfaces Monitoring Program for regulators and solenoid valves containing copper alloy (> 15%
Zinc). (Reference PG&E Letter DCL-1 0-130, dated October 12, 2010)
Table A4-1, #31           Completed. The Unit 2 gap repair work has been completed.
Table A4-1, #35           Completed. The procedure acceptance criteria to specifically preclude repositioning a tube more than once without capping or replacing has been revised. This precludes repositioning a tube having chrome plated surfaces from the chrome being moved out of the areas of known wear.
Table A4-1, #62           Completed. The Unit 2 diesel generator starting air and turbocharger air compressors have been upgraded.
Section 4.2.1             Pressurized Thermal Shock analyses results are updated to Table 4.2-1               reflect WCAP-1 7315-NP and WCAP-1 7299-NP.
Table 4.2-2               LRA Table A4-1, Item 24 is deleted.
Table 4.2-3 Section 4.2.2 Table 4.2-4 Table 4.2-5 Section 4.2.3 Table 4.2-6 Table 4.2-7 Section 4.9 Section A3.1.2 Table A4-1, #24 Section 3.2.2.1.1         Updated to reflect the re-evaluation of cast iron and gray cast iron Table 3.2.2-1             components based on lessons learned from a license renewal Table 3.2.2-4             inspection at a different nuclear power plant. Also, added Section 3.3.2.1.3         applicable aging management programs for components for Section 3.3.2.1.4         which there are multiple aging effects.
Section 3.3.2.1.5 Section 3.3.2.1.7 Section 3.3.2.1.8 Section 3.3.2.1.11 Section 3.3.2.1.12 Section 3.3.2.1.13

PG&E Letter DCL-1 1-136 Page 2 of 2 Affected LRA Section                         Reason for Change Section 3.3.2.1.14 Section 3.3.2.1.16 Section 3.3.2.1.17 Section 3.3.2.1.18 Section 3.3.2.1.19 Table 3.3.2-3 Table 3.3.2-4 Table 3.3.2-5 Table 3.3.2-7 Table 3.3.2-8 Table 3.3.2-11 Table 3.3.2-12 Table 3.3.2-13 Table 3.3.2-14 Table 3.3.2-16 Table 3.3.2-17 Table 3.3.2-18 Table 3.3.2-19 Section 3.4.2.1.1 Section 3.4.2.1.2 Section 3.4.2.1.4 Table 3.4.2-1 Table 3.4.2-2 Table 3.4.2-4 Table 2.3.1-2          Updated to reflect plant modifications (review of equipment Table 2.3.2-3          changes).
Table 2.3.3-4 Table 2.3.3-7 Table 2.4-1 Table 3.1.2-2 Section 3.2.2.1.3 Table 3.2.2-3 Table 3.3.2-4 Table 3.3.2-7 Table 3.5.2-1 Table 3.3.2-4          Updated to reflect abandonment of equipment associated with Table 3.3.2-5          the boric acid evaporator subsystem.
Table 3.3.2-8 Table 3.3.2-17 Table 3.3.2-18 Table 3.4.2-2

PG&E Letter DCL-11-136 Page 1 of 98 LRA Amendment 45 Affected LRA Sections, Tables, and Figures Table 2.3.1-2 Table 2.3.2-3 Table 2.3.3-4 Table 2.3.3-7 Table 2.4-1 Table 3.1.2-2 Section 3.2.2.1.1 Section 3.2.2.1.3 Table 3.2.2-1 Table 3.2.2-3 Table 3.2.2-4 Section 3.3.2.1.3 Section 3.3.2.1.4 Section 3.3.2.1.5 Section 3.3.2.1.7 Section 3.3.2.1.8 Section 3.3.2.1.11 Section 3.3.2.1.12 Section 3.3.2.1.13 Section 3.3.2.1.14 Section 3.3.2.1.16 Section 3.3.2.1.17 Section 3.3.2.1.18 Section 3.3.2.1.19 Section 3.3.2.2.14 Table 3.3.2-3 Table 3.3.2-4 Table 3.3.2-5 Table 3.3.2-7 Table 3.3.2-8 Table 3.3.2-11 Table 3.3.2-12 Table 3.3.2-13 Table 3.3.2-14 Table 3.3.2-16 Table 3.3.2-17 Table 3.3.2-18 Table 3.3.2-19 Section 3.4.2.1.1 Section 3.4.2.1.2 Section 3.4.2.1.4 Table 3.4.2-1 Table 3.4.2-2

PG&E Letter DCL-11-136 Page 2 of 98 LRA Amendment 45 Affected LRA Sections, Tables, and Figures Table 3.4.2-4 Table 3.5.2-1 Section 4.2.1 Table 4.2-1 Table 4.2-2 Table 4.2-3 Section 4.2.2 Table 4.2-4 Table 4.2-5 Section 4.2.3 Table 4.2-6 Table 4.2-7 Section 4.9 Section A.l15 Section A3.1.2 Table A4-1, #23, 24, 31, 35, 62, 71 Section B2.1.15 Section 2.3 PG&E Letter DCL-1 1-136                             SCOPING AND SCREENING RESULTS:
MECHANICAL SYSTEMS Page 3 of 98 Table 2.3.1-2  Reactor Coolant System Component Type                           Intended Function Filter                              Leakage Boundary (spatial)
Structural Integrity (attached)
Section 2.3 PG&E Letter DCL-1 1-136                            SCOPING AND SCREENING RESULTS:
MECHANICAL SYSTEMS Page 4 of 98 Table 2.3.2-3  Residual Heat Removal System Component Type                          Intended Function Indicator                          Leakage Boundary (spatial)
StructuralIntegrity (attached)
Section 2.3 PG&E Letter DCL-11-136                             SCOPING AND SCREENING RESULTS:
Page 5 of 98                                                      MECHANICAL SYSTEMS Table 2.3.3-4   Component Cooling Water System Component Type                          Intended Function Tubing                             Leakage Boundary (spatial)
Pressure Boundary StructuralIntegrity (attached)

Enclosure 2                                                            Section 2.3 PG&E Letter DCL-1 1-136                         SCOPING AND SCREENING RESULTS:
Page 6 of 98                                                 MECHANICAL SYSTEMS Table 2.3.3-7   CompressedAir System Component Type                       Intended Function Pressure Boundary I Orifice                            Throttle Section 2.4 PG&E Letter DCL-11-136                                  SCOPING AND SCREENING RESULTS:
STRUCTURES Page 7 of 98 Table 2.4-1        ContainmentBuildina Component Type                            Intended Function Hatch                                   Shelter, Protection
_StructuralSupport Structural Steel                        Missile Barrier Section 3.1 PG&E Letter DCL-11-136                                                               AGING MANAGEMENT OF REACTOR VESSEL, Page 8 of 98                                                                       INTERNALS, AND REACTOR COOLANT SYSTEM Table 3.1.2-2     Reactor Vessel, Internals, and Reactor Coolant System - Summary of Aging Management Evaluation -
Reactor Coolant System Component     Intended   Material    Environment      Aging Effect      Aging Management       NUREG- Table 1 Item    Notes Type     Function                                 Requiring              Program         1801 Vol.
Management                                 2 Item Filter        LBS, SIA  Stainless   Demineralized    Loss of material   Water Chemistry        V. C-4     3.2.1.03   C Steel       Water (Int)                        (B2.1.2) and One-Time Inspection (B2.1.16)
Filter        LBS, SIA  Stainless   PlantIndoor Air  None              None                   IV.E-2      3.1 . 1.86 A Steel       (Ext)           I                 I                      I           I _II Section 3.2 PG&E Letter DCL-11-136                                AGING MANAGEMENT OF ENGINEERED Page 9 of 98                                                          SAFETY FEATURES 3.2.2.1.1 Safety Injection System Materials The materials of construction for the safety injection system component types are:
         "   Cast IronR
           " Cast Iron (Gray Cast Iron)
Section 3.2 PG&E Letter DCL-1 1-136                              AGING MANAGEMENT OF ENGINEERED SAFETY FEATURES Page 10 of 98 3.2.2.1.3 Residual Heat Removal System Materials The materials of construction for the residual heat removal system component types are:
0     Glass Section 3.2 PG&E Letter DCL-1 1-136                                                                   AGING MANAGEMENT OF ENGINEERED SAFETY FEATURES Page 11 of 98 Table 3.2.2-1   En*---Enineered   Safety   Features        - Summarv of AaQina Manaaement Evaluation - Safetv Iniection System
                        '   ---   --
S  ---    --  -----------------------------------
                                                           -                                  --- - ........ .......... -                    .
Component Intended       Material       Environment               Aging Effect       Aging Management Program            NUREG-     Table 1   Notes Type   Function                                                  Requiring                                          1801 Vol. Item Management                                              2 Item Filter      PB          Cast Iron    Lubricating Oil            Loss of material Lubricating Oil Analysis (B2.1.23)     V.D1-28    3.2.1.16  B (Gray Cast (Int)                                            and One-Time Inspection Iron)                                                       (B2.1.16)
Filter      PB          Cast Iron    Plant IndoorAir            Loss of material External Surfaces Monitoring           V.E-7      3.2.1.31  B (Gray Cast (Ext)                                            Program (B2.1.20)
Iron)
Section 3.2 PG&E Letter DCL-11-136                                                        AGING MANAGEMENT OF ENGINEERED SAFETY FEATURES Page 12 of 98 Table 3.2.2-3        Engineered Safety Features- Summary of Aging ManagementEvaluation - Residual Heat Removal System Component        Intended      Material    Environment         Aging Effect      Aging Management      NUREG- Table I Item        Notes Type         Function                                       Requiring               Program       1801 Vol.
Management                                2 Item Indicator        LBS, SIA    Glass        BoratedWater       None               None                   None      None           H, 5 Leakage (Ext)
Indicator        LBS, SIA    Glass        Treated Borated    None               None                   V.F-9     3.2.1.52       A Water (Int)
Indicator        LBS, SIA    Stainless    Borated Water      None               None                   V. F- 13  3.2. 1.57      A Steel        Leakage (Ext)
Indicator        LBS, SIA Stainless       Treated Borated    Loss of material    Water Chemistry       V.D1-30   3,2.1.49       E, 3 Steel        Water (Int)                           (B2. 1.2) and One-Time I__IIInspection                                                             (B2.1.16)
Indicator        LBS, SIA Stainless       Treated Borated    Cracking            Water Chemistry       V.D1-31   3.2.1.48       E, 3 Steel        Water (Int)                           (B2.1.2) and One-Time Inspection (B2.1.16)
Notes for Table 3.2.2-3:
Plant Specific Notes:
5           There are no aging effects associatedwith glass with borated water leakage. This non-NUREG-1801 Revision I line is based upon NUREG-1801 Revision 2 line VlI.J.AP-96.
Section 3.2 PG&E Letter DCL-1 1-136                                                        AGING MANAGEMENT OF ENGINEERED SAFETY FEATURES Page 13 of 98 T~hlI. .' 2 2-4
* Fnnin,~~md P.~.f~tv ~          - .g,,mm~ri,  nf Aninc, M~n~n~m~nt gi,~Iu~finn rnnt~ainm~cint I-41/Afl CZietc~m
                                                                         ~                             ~    -
Component Intended            Material   Environment    Aging Effect      Aging Management Program           NUREG-      Table 1   Notes Type         Function                                  Requiring                                          1801 Vol. Item Management                                            2 Item Heat             HT, PB    Cast Iron     Secondary      Loss of material Water Chemistry (B2.1.2) and         VIII.F-28 3.4.1.03  A Exchanger                  (Gray Cast    Water (Int)                     One-Time Inspection (B2.1.16)
(Containment               Iron)
Purge)
Tubing           LBS, PB,  Stainless     Closed Cycle Loss of material Closed-Cycle Cooling Water             VII.C2-10 3.3.1.50  B SIA       Steel         Cooling Water                   System (B2.1.10)
I         (Int)
Tubing           LBS, PB, Stainless      Plant Indoor   None             None                                 VII.J-15  3.3.1.94  A SIA       Steel         Air (Ext)
Valve            PB        Cast Iron     Ventilation    Loss of material Inspection of Internal Surfaces in   VII.F3-3  3.3.1.72  D, 9 (Gray Cast    Atmosphere                      Miscellaneous Piping and Ducting I           Iron)        I(Int)                           Components (B2.1.22)
Plant Specific Notes:
9         The operatingtemperaturefor these components is above dew point. Condensationcan occurbut rarely. Components surfaces are normally dry.
Section 3.3 PG&E Letter DCL-11-136                                 AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 14 of 98 3.3.2.1.3 Saltwater and Chlorination System Materials The materials of construction for the saltwater and chlorination system component types are:
         '   Cast Iron Cast Iron (Gray Cast Iron)
Section 3.3 PG&E Letter DCL-1 1-136                               AGING MANAGEMENT OF AUXILIARY Page 15 of 98                                                               SYSTEMS 3.3.2.1.4 Component Cooling Water System Materials The materials of construction for the component cooling water system component types are:
0 Cast Iron Section 3.3 PG&E Letter DCL-11-136                               AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 16 of 98 3.3.2.1.5 Makeup Water System Materials The materials of construction for the makeup water system component types are:
0    Gast kron Section 3.3 PG&E Letter DCL-11-136                                AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 17 of 98 3.3.2.1.7 Compressed Air System Materials The materials of construction for the compressed air system component types are:
         '    Cast Iron Cast Iron (Gray Cast Iron)
Section 3.3 PG&E Letter DCL-1 1-136                               AGING MANAGEMENT OF AUXILIARY Page 18 of 98                                                                SYSTEMS 3.3.2.1.8 Chemical and Volume Control System Materials The materials of construction for the chemical and volume control system component types a re:
Cast Iron (Gray Cast Iron)
Section 3.3 PG&E Letter DCL-1 1-136                                  AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 19 of 98 3.3.2.1.11   Auxiliary Building HVAC System Materials The materials of construction for the auxiliary building HVAC system component types are:
* Gast Iron
* Cast Iron (Gray Cast Iron)
Section 3.3 PG&E Letter DCL-1 1-136                                  AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 20 of 98 3.3.2.1.12    Fire Protection System Materials The materials of construction for the fire protection system component types are:
0     Cast !FRo Section 3.3 PG&E Letter DCL-1 1-136                                 AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 21 of 98 3.3.2.1.13   Diesel Generator Fuel Oil System Materials The materials of construction for the diesel generator fuel oil system component types are:
         -   Cast Iron
         "   Ductile Iron Section 3.3 PG&E Letter DCL-1 1-136                                AGING MANAGEMENT OF AUXILIARY Page 22 of 98                                                                 SYSTEMS 3.3.2.1.14    Diesel Generator System Materials The materials of construction for the diesel generator system component types are:
Cast Iron C
* Cast Iron (Gray Cast Iron)
Aging Management Programs The following aging management programs manage the aging effects for the diesel generator system component types:
* Selective Leaching of Materials (B2.1.17)
Section 3.3 PG&E Letter DCL-11-136                               AGING MANAGEMENT OF AUXILIARY Page 23 of 98                                                               SYSTEMS 3.3.2.1.16   Gaseous Radwaste System Materials The materials of construction for the gaseous radwaste system component types are:
rCast Iron
        . Cast Iron (Gray Cast Iron)
Section 3.3 PG&E Letter DCL-1 1-136                                AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 24 of 98 3.3.2.1.17   Liquid Radwaste System Materials The materials of construction for the liquid radwaste system component types are:
        "    Cast IronR
* Cast Iron (Gray Cast Iron)
Section 3.3 PG&E Letter DCL-1 1-136                         AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 25 of 98 3.3.2.1.18   Miscellaneous Systems In-Scope ONLY based on Criterion 10 CFR 54.4(a)(2) &deg; Materials The materials of construction for the miscellaneous systems in scope ONLY based on Criterion 10 CFR 54.4(a)(2) component types are:
0   Cast !Fon Section 3.3 PG&E Letter DCL-11-136                                  AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 26 of 98 3.3.2.1.19    Oily Water and Turbine Sump System Materials The materials of construction for the oily water and turbine sump system component types are:
           *CasRt   Iron.
* Cast Iron (Gray Cast Iron)
Aging Management Programs The following aging management programs manage the aging effects for the oily water and turbine sump system component types:
0      Selective Leaching of Materials (B2. 1.17)
Section 3.3 PG&E Letter DCL-11-136                                    AGING MANAGEMENT OF AUXILIARY Page 27 of 98                                                                        SYSTEMS 3.3.2.2.14 Loss of Material due to Cladding Breach The Water Chemistry program (B2.1.2) and the One-Time Inspection program (B2.1.16) manage loss of material due to cladding breach for steel clad with stainless steel pump casings exposed to treated borated water. The one-time inspection includes each of the affected components and will address the full internal cladding surface exposed to treated borated water.
NRC Information Notice 80-38 and Information Notice 94-63 address loss of material due to cladding breach for CVCS pumps fabricated of steel with stainless steel cladding.
DCPP identifies pumps CCP 1-1 and CCP 2-2 as fabricated of steel with stainless steel cladding. NRC Information Notice 80-38 advises that the condition presents a "potential source of degradation over long term operations" and recommends a "non-destructive examination of this pump type." Information Notice 94-63 provides additional information about the condition described based on the analysis of industry operating experience and concludes that "corrosion of the base metal due to cladding cracks is usually relatively easy to identify through visual inspection". The One-Time Inspection program (B2.1.16) provides a non-destructive visual examination consistent with the guidance of Information Notice 80-38 and 94-63.
Prior to the period of extended operation, DGPP Will replace the current carbon steel wih stainlerss rMtoel c-lad-COrP 2 2 PUMP casings with a comspletely M.st ainless stee te!r pump
 ..... g 7During the Unit I and Unit 2 sixteenth refueling outages, PG&E replaced the CCP 1-l and CCP 2-2 carbon steel pump casings with completely stainless steel casings, respectively.
Section 3.3 PG&E Letter DCL-1 1-136                                                            AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 28 of 98 Table 3.3.2-3     Auxiliary Systems - Summary of Aging ManagementEvaluation - Saltwater and ChlorinationSystem Component    Intended     Material    Environment     Aging Effect     Aging Management      NUREG- Table 1 Item   Notes Type     Function                                   Requiring            Program         1801 Vol.
Management                               2 Item Piping        LBS        Cast Iron   Plant Indoor Air Loss of material External Surfaces      VII.I-8    3.3.1.58  B (Gray Cast  (Ext)                             Monitoring Program Iron)                                         (82.1.20)
Piping        LBS        Cast Iron   Raw Water (Int)  Loss of material Open-Cycle Cooling     VII.C1-19  3.3.1.76  A (Gray Cast                                    Water System (B12.1.9)
Iron)
Piping        LBS        Cast Iron   Raw Water (Int)  Loss of material Selective Leaching of  VII. Cl-11 3.3.1.85  A (Gray Cast                                    Materials (B2. 1.17)
Iron)
Pump          LBS        Cast Iron   Demineralized    Loss of matenal  Selective Leaching of  VII. G- 16 3.3. 1.85 A (Gray Cast  Water (Int)                       Materials (B2. 1.17)
Iron)
Pump          LBS        Cast Iron   Demineralized    Loss of material Water Chemistry        VIII.B1-11 3.4.1.04  A (Gray Cast  Water (Int)                       (B2.1.2) and One-Time Iron)                                         Inspection (B2.1.16)
Pump          LBS        Cast Iron   Plant Indoor Air Loss of material External Surfaces      VII.I-8    3.3.1.58  B (Gray Cast  (Ext)                             Monitoring Program Iron)                                         (82.1.20)
Strainer      LBS        Cast Iron   Plant Indoor Air Loss of material External Surfaces      VII.I-8    3.3.1.58  B (Gray Cast  (Ext)                             Monitoring Program Iron)                                         (B2.1.20)
Strainer      LBS        Cast Iron   Raw Water (Int)  Loss of material Open-Cycle Cooling     VII.C1-19  3.3.1.76  A (Gray Cast                                    Water System (B2.1.9)
Iron)
Strainer      LBS        Cast Iron   Raw Water (Int)  Loss of materal  Selective Leaching of  VII. Cl-11 3.3. 1.85 A (Gray Cast                                    Materials (B2.1,17)
Iron)
Valve         PB        Cast Iron    Atmosphere/      Loss of material External Surfaces      VII.I-9    3.3.1.58  B (Gray Cast  Weather (Ext)                     Monitoring Program Iron)                                         (82.1.20)
Section 3.3 PG&E Letter DCL-11-136                                                             AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 29 of 98 Table 3.3.2-3     Auxiliary Systems - Summary of Aging Management Evaluation- Saltwaterand ChlorinationSystem Component     Intended     Material    Environment     Aging Effect     Aging Management      NUREG- Table I Item    Notes Type     Function                                   Requiring             Program         1801 Vol.
Management                               2 Item Valve         LBS        Cast Iron   Demineralized    Loss of material Selective Leaching of  VII.G-16   3.3. 1.85 A (Gray Cast  Water (Int)                       Materials (B2. 1.17)
Iron)
Valve         LBS        Cast Iron   Demineralized    Loss of material Water Chemistry        VIII.B1-11 3.4.1.04  A (Gray Cast  Water (Int)                       (B2.1.2) and One-Time Iron)                                         Inspection (B2.1.16)
Valve         LBS        Cast Iron   Plant Indoor Air Loss of material External Surfaces      VII.I-8    3.3.1.58  B (Gray Cast  (Ext)                             Monitoring Program Iron)                                         (B2.1.20)
Valve         LBS, PB    Cast Iron   Raw Water (Int)  Loss of material Open-Cycle Cooling     VII.C1-19  3.3.1.76  A (Gray Cast                                    Water System (B2.1.9)
Iron)
Valve         LBS, PB    Cast Iron   Raw Water (Int)  Loss of material Selective Leaching of  VI1.CI-11  3.3.1.85  A (Gray Cast                                    Materials (B2. 1.17)
Iron)
Valve         PB         CopperAlloy Raw Water (Int)  Loss of material Open-Cycle Cooling     V11. C1-9  3.3.1.81  A (Aluminum >                                   Water System (B2. 1 9) 8%)

Enclosure 2                                                                                                                     Section 3.3 PG&E Letter DCL-1 1-136                                                                    AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 30 of 98 Table 3.3.2-4        Auxiliary Systems - Summary of Aging Management Evaluation - Component Cooling Water System Component      Intended     Material       Environment        Aging Effect     Aging Management      NUREG- Table 1 Item        Notes Type        Function                                         Requiring            Program        1801 Vol.
Management                               2 Item Piping          PB          Carbon Steel Atmosphere/          Loss of material Inspection of Internal VII..9    3.3.1.58       E, 4 Weather (Int)                        Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Piping          PB          Carbon Steel Closed Cycle         Loss of material Inspection of Internal VI1.C2-14 3.3.1.47       E, 5 Cooling Water (Int)                  Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Regulates       P-B         Gae6t-ler,,         a2 Ga,
                                                *-(4            NVOe             Ne                               3.3.-_-_-_-_-_-_-
A RegulateFs      PB          Cast  'rFO    Plant indoor Air    Lo66 of matera   E)enal Sufae           VI-8                     B (EA)Monitoring                        Program Regu4ateGs      PB          Cast-On       Atmgepe             Lo66 of Materiaa Etrna Surfacvies-            9   3.3. :158      B WeatheF (E*4)                        Monitoring Program Valve           PB          Carbon Steel Closed Cycle         Loss of material Inspection of Internal VII C2-14 3.3.1.47       E, 5 Cooling Water (Int)                  Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Valve           PB          Stainless     Closed Cycle        Loss of material Inspection of Internal VII C2-10 3.3.1.50       E, 5 Steel         Cooling Water (Int)                  Surfaces in MiscellaneousPiping and Ducting Components (B2.1.22) I Notes for Table 3.3.2-4:
Plant Specific Notes:
I 4       Closed Cooling Water piping with internalenvironment of atmosphere/weather.
Section 3.3 PG&E Letter DCL-11-136                                                                 AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 31 of 98 5     Components are associatedwith the boric acid evaporatorsubsystem which is abandoned-in-place. Thus, aging of the components will be managed by the Inspection of InternalSurfaces in MiscellaneousPiping and Ducting Components aging managementprogram.
Section 3.3 PG&E Letter DCL-1 1-136                                                                     AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 32 of 98 Table 3.3.2-5     Auxiliary Systems - Summary of Aging Management Evaluation - Makeup Water System Component     Intended     Material      Environment          Aging Effect       Aging Management      NUREG- Table I Item    Notes Type      Function                                          Requiring             Program         1801 Vol.
Management                                2 Item Piping        LBS        Stainless     Demineralized         Loss of material Inspection of Internal   VIII.E-29 3.4.1.16   E, 6 Steel         Water (Int)                            Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Pump          PB         Cast Iron     Demineralized         Loss of material  Water Chemistry        VIII. E-34 3.4.1.04   A (Gray Cast    Water (Int)                            (B2.1.2) and One- Time Iron)                                                Inspection (B2.1.16)
Valve         PB         Cast Iron    Atmosphere/            Loss of material External Surfaces       VII.I-9    3.3.1.58   B (Gray Cast    Weather (Ext)                          Monitoring Program Iron)                                                (B2.1.20)
Valve         PB         Cast Iron     Buried (Ext)          Loss of material Selective Leaching of   VII. G- 15 3.3. 1 85  A (Gray Cast                                           Materials(B2.1.17)
Iron)
Valve         PB         Cast Iron     Buried (Ext)          Loss of Material Buried Piping and Tanks VII.G-25   3.3.1.19   B (Gray Cast                                           Inspection (B2.1.18)
Iron)
Valve         LBS, PB    Cast Iron     Demineralized         Loss of material Water Chemistry         VIII.E-34  3.4.1.04   A (Gray Cast   Water (Int)                             (B2.1.2) and One-Time Iron)                                                Inspection (B2.1.16)
Valve         L-Bs       Gast-lre      Plant Indoor Air      Lns ,of material     drnal Sfa Extm)                   VI-r--     3.3.       B (k.,                                    Monitoring Program Valve         L43S       Gast !en+     P-otable W~ater (Int' Less of matorFal Inspecation of Internal Na~e       Nene       G Su~faGes4iR Miscellaneous    Piping Vav       g       G~4Fe&#xfd;        Raw VWateF (4pt) Loss of materia        Fire Water System       V47G-24    34.4-"B    B8 I                                    -     .    . )/g_
Section 3.3 PG&E Letter DCL-11-136                                                                     AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 33 of 98 Table 3.3.2-5        Auxiliary Systems - Summary of Aging Management Evaluation - Makeup Water System Component      Intended      Material     Environment        Aging Effect      Aging Management      NUREG- Table 1 Item      Notes Type        Function                                       Requiring              Program         1801 Vol.
Management                               2 Item Valve           LBS         Cast Iron    Potable Water (Int) Loss of material  Inspection of Internal None       None        G (Gray Cast                                         Surfaces in Iron)                                              Miscellaneous Piping and Ducting Components (B2.1.22)
Valve           LBS         Cast Iron    Potable Water (Int) Loss of material  Selective Leaching of  None       None        G (Gray Cast                                         Materials (82.1.17)
Iron)
Valve           LBS         Stainless    Demineralized       Loss of material  Inspection of Internal VIII.E-29  3.4.1.16    E, 6 Steel        Water (Int)                           Surfaces in MiscellaneousPiping and Ducting Components (B2.1.22) I Notes for Table 3.3.2-5:
Plant Specific Notes:
6       Components are associatedwith the boric acid evaporatorsubsystem which is abandoned-in-place. Thus, aging of the components will be managed by the Inspection of InternalSurfaces in Miscellaneous Pipingand Ducting Components aging management program.
Section 3.3 PG&E Letter DCL-1 1-136                                                                 AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 34 of 98 Table 3.3.2-7     Auxiliary Systems - Summary of Aging Management Evaluation- CompressedAir System Component     Intended     Material         Environment    Aging Effect      Aging Management      NUREG- Table 1 Item    Notes Type      Function                                       Requiring             Program         1801 Vol.
Management                                2 Item Filter        FIL, PB    Stainless       Atmosphere!      Loss of material  External Surfaces      None       None      G Steel           Weather (Ext)                      MonitoringProgram (B2.1.20)
Filter        FIL, PB    Stainless       Dry Gas (Int)    None              None                   VII.J- 19  3.3.1.97  A Steel Orifice       PB, TH     Stainless       PlantIndoor Air  None              None                   VII.J- 15  3.3.1.94  A Steel           (Ext)
Orifice       PB, TH     Stainless       Plant IndoorAir  Loss of material  Inspection of Internal VII.D-4    3.3.1.54  E, 3 Steel           (Int)                              Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Regulators    PB         Cast Iron       Plant Indoor Air Loss of material  External Surfaces      VII.D-3    3.3.1.57  B (Gray Cast      (Ext)                              Monitoring Program Iron)                                              (B2.1.20)
Regulators    PB         Cast Iron       Plant Indoor Air Loss of material  Inspection of Internal VII.D-2    3.3.1.53  E, 3 (Gray Cast      (Int)                              Surfaces in Iron)                                              Miscellaneous Piping and Ducting Components (B2.1.22)
Regulators    PB         Cast Iron       Plant IndoorAir  Loss of material  Selective Leaching of  None       None      G, 4 (Gray Cast      (Int)                              Materials (B2.1.17)
Iron)
RegulatEws    P-9        Goppef-Alloy1.- AfitspheFe/-     Loss of m~aterial External Surface6      None       None
(> 15% ZincG WeatheF (Ed)                          Monitoring Progr.am Regulators    PB         Copper Alloy PlantIndoor Air     Loss of material  Inspection of Internal VII. G-9   3.3.1.28  E, 3
(> 15% Zinc) (Int)                                 Surfaces in MiscellaneousPiping and Ducting Components (B2. 1.22)
Section 3.3 PG&E Letter DCL-1 1-136                                                                       AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 35 of 98 Table 3.3.2-7        Auxiliary Systems - Summary of Aging Management Evaluation- Compressed Air System Component      Intended      Material      Environment        Aging Effect        Aging Management      NUREG- Table 1 Item          Notes Type        Function                                        Requiring                Program         1801 Vol.
Management                                  2 Item Solenoid Valve P-9          GOP~eF Alkoy- AtnGmeeIWe/         Loss of mnaterilo~      ral Su~faces       None       NoneG
(> 1%-~       WeVVatheF (EA4)                         Mon40itrng Programn Solenoid Valve PB           CopperAlloy Plant IndoorAir       Loss of material    Inspection of Internal VII. G-9   3.3.1.28       E, 3
(> 15% Zinc) (Int)                                    Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Notes for Table 3.3.2-7:
Plant Specific Notes:
4       Gray Cast Iron SSCs with surfaces exposed to Ventilation Atmosphere (Internal)or Plant IndoorAir (Internal)are subject to wetting due to condensationand thus are subject to loss of material due to selective leaching.
Section 3.3 PG&E Letter DCL-1 1-136                                                                           AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 36 of 98 Table 3.3.2-8     Auxiliary Systems - Summary of Aging Management Evaluation- Chemical and Volume Control System Component     Intended     Material    Environment            Aging Effect     Aging Management Program         NUREG-      Table I     Notes Type      Function                                           Requiring                                     1801 Vol.      Item Management                                         2 Item Demineralizer  LBS         Stainless  Demineralized          Loss of material   Inspection of Internal Surfaces VIII.E-29 3.4.1.16    AE, 9 Steel      Water (Int)                               in Miscellaneous Piping and Ducting Components (B2.I. 22)W-ater GenspL (82.1.2) and One Time Inspection (/3B424.16 Evaporator     LBS         Stainless  Treated Borated Loss of material          Inspection of Intemal Surfaces VII.E1-17 3.3.1.91     E, 59 Steel      Water (Int)                               in MiscellaneousPiping and Ducting Components (B2. 1.22Watee r he e'-
(132.1.2) and One Time
___________Insmpectioni(82.1.16) r.ap..atGF     L-BS        Stainless- Teated Bo*r*od           G-rGkg           WWter Chemistr, (1.2        And VWI
                                                                                                                \Il=4    20 3.3.19      -
Filter         LBS         Stainless  Treated Borated Loss of material Inspection of Intemal Surfaces            V/I.E1-17 3.3.1.91   E, 9 Steel      Water (Int)                               in MiscellaneousPiping and Ducting Components (B2.1.22)
Flow Element   LBS, SIA    Stainless  Treated Borated Loss of material Inspection of InternalSurfaces            VII.E1-17 3.3.1.91   E, 9 Steel      Water (Int)                               in MiscellaneousPiping and Ducting Components (B2.1.22)
Heat           LBS, SIA,   Carbon     Closed Cycle           Loss of material Inspection of Intemal Surfaces    VII.E1-6    3.3.1.48  E, 9B Exchanger      SS          Steel      Cooling Water                             in Miscellaneous Piping and (Boric Acid                           (Int)                                     Ducting Components Evaporator/                                                                     (B2. 1.22)Clesed Cycle Cooling Condenser)                                                                       ^aIo+e Syste(1),,,                                   _    __\
Heat           LBS, SS     Carbon     Secondary              Loss of material Inspection of InternalSurfaces     VIII.E-34  3.4.1.04  E, 9 Exchanger                  Steel      Water (Int)                               in Miscellaneous Piping and (Boric Acid                                                                     Ducting Components (B2. 1.22)
Evaporator!
Condenser)

Enclosure 2                                                                                                                 Section 3.3 PG&E Letter DCL-1 1-136                                                                  AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 37 of 98 Table 3.3.2-8     Auxiliary Systems - Summary of Aging Management Evaluation- Chemical and Volume Control System Component     Intended     Material    Environment   Aging Effect       Aging Management Program NUREG-            Table 1   Notes Type     Function                                  Requiring                                      1801 Vol. Item Management                                          2 Item Heat-          Las,-SS     Ga*bGR     Steam-(10)     Loseof mraterial*,AlateAF Chmisty (2.1 .2) and V111.13,        4.14  E,5-Steel                                         One Time Inspection (B2.1.1*6 (0FwGr  Acid-Evapowator-Heat           LBS, SS     Stainless  Closed Cycle   Loss of material    Inspection of Intemal Surfaces VII.C2-10 3.3.1.50   E, 9D Exchanger                  Steel      Cooling Water                      in Miscellaneous Piping and (Boric Acid                           (Int)                              Ducting Components Evaporator/                                                              (B2.1.22)CGloed Cycle Cooling Condenser)                                                               Water System,, .1.10)
Heat           LBS, SS     Stainless  Secondary      Loss of material    Inspection of Internal Surfaces VIII.E-29 3.4.1.16  E, 9C Exchanger                  Steel      Water (Ext)                        in Miscellaneous Piping and (Boric Acid                                                              Ducting Components Evaporator/                                                              (B2.1.22)0Wate-r    eetry-Condenser)                                                               (92.1.2) and Ge* Time nspcion (B2.1.16)
                                                                          .....
Heat-          LBS-SS      Stainless- Serenday       GaGl,*,*,.,        Water Chemisty (B2.1.2) and V!.W=-         3.44-4    G Eha~ge--                   Steel      WateF--(EA                         One Ti*e InspGction (92.1.16)
(139kAGi4 Evapo-ator Heat           LBS, SS     Stainless  Closed Cycle   Loss of material    Inspection of Internal Surfaces VI1.C2-10 3.3.1.50  E, 9D Exchanger                  Steel      Cooling Water                      in Miscellaneous Piping and (Boric Acid                           (Ext)                              Ducting Components Distillate)                                                              (B2.1.22)Closed Cycle Cooling Heat           LBS, SIA,   Stainless  Closed Cycle   Loss of material    Inspection of InternalSurfaces VI1.C2-10 3.3.1.50   E, 9D Exchanger      SS          Steel      Cooling Water                      in Miscellaneous Piping and (Boric Acid                           (Int)                              Ducting Components Distillate)                                                              (B2.1.22)CGlsod Cycle Cooling
__-__ater Sytem4(*2.*110)

Enclosure 2                                                                                                                      Section 3.3 PG&E Letter DCL-1 1-136                                                                   AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 38 of 98 Table 3.3.2-8     Auxiliary Systems - Summary of Aging Management Evaluation - Chemical and Volume Control System Component    Intended     Material    Environment      Aging Effect     Aging Management Program           NUREG-      Table 1    Notes Type     Function                                   Requiring                                         1801 Vol.      Item Management                                           2 Item Heat          LBS, SS     Stainless   Demineralized    Loss of material  Inspection of Internal Surfaces VIII.E-29 3.4.1.16      E, 9G Exchanger                 Steel       Water (Int)                       in Miscellaneous Piping and (Boric Acid                                                             Ducting Components Distillate)                                                              (82.1.22)-Water Gher4stf&#xfd;-
(924.1.2), and One Time Heat          LBS         Stainless   Secondary        Loss of material Inspection of Internal Surfaces VIII.E-29 3.4.1.16       E, 9 Exchanger                 Steel       Water (Int)                       in Miscellaneous Piping and (Boric Acid                                                             Ducting Components (B2. 1.22)
Evaporator)
Heat-         LBS         Stanless- Steam-{k(-t)                        Water Chemistry (82.1,2) and- ."&#xfd;3. V.11431 2            E 5 E-xGhaRger-               Steel                                         One Time Inspection (82.1.16)
(69FOGAGi4 Heat-          L4B         Staimless-  Steamt(4nBt      Los of material  Waiter Chemistry (132.1.2) and      V*b,*B.3  34.4.1     E.3 ExGhafiger--               Steel                                         One Time Inspection (132.1.46)
(13FG GAGid-Heat           LBS9        2-tai ess,- TrFeated BerFate G~aGkinq         'ater Chemistry (62.1.2) ad VlkE445           3-3-1-O8   E1-EXGhanger-                 Steel       W~ateF (EA)                       Qnz TimeA Inspection (1324.W.6
{(BeiG -AGi Heat          LBS         Stainless   Treated Borated  Loss of material Inspection of Internal Surfaces VII.El-17 3.3.1.91       E,,69 Exchanger                 Steel       Water (Ext)                       in Miscellaneous Piping and (Boric Acid                                                             Ducting Components Evaporator)                                                             (B2.1.22)Water-Chlemietpy-(B..2ndOe Time Heat-          LBS-SIA-    Stainleess  Treated Batd     CGking           Water Chemit ,A,.           a       VI.E   5  3.3.0*
EGhaeref-      &S          Steel       VWat(I4                           OnAe TimEI         ion (182.1.16)
(BeP~i-Aeid-Section 3.3 PG&E Letter DCL-11-136                                                                      AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 39 of 98 Table 3.3.2-8       Auxiliary Systems - Summary of Aging Management Evaluation - Chemical and Volume Control System Component       Intended     Material   Environment     Aging Effect     Aging Management Program        NUREG-     Table 1   Notes Type        Function                                  Requiring                                     1801 Vol. Item Management                                        2 Item Heat             LBS, SIA,   Stainless  Treated Borated Loss of material  Inspection of Internal Surfaces VII.El-17 33.1.91   E, 59 Exchanger        SS          Steel      Water (Int)                       in Miscellaneous Pipingand (Boric Acid                                                               Ducting Components Evaporator)                                                               (B2.1.22)WateF Ghemistpy-(B2.1.2) and One Time n..p..tion (-2.1 .16)
Heat             LBS         Stainless  Secondary       Loss of material  Inspection of InternalSurfaces VIII.E-29  3.4.1.16  E, 9G Exchanger                    Steel      Water (Ext)                       in Miscellaneous Pipingand (Boric Acid                                                               Ducting Components Feed)                                                                     (B2.1.22)Water Ghemtpy-(132.1.2) and One Time inspection (B32.1 .6)             ___
Heat-           L--          Stainleess SeGOsday           ar-,ki.rng     Watcr-Chemistry, (2.1.2) and- V4lO         .4.4-.4  G EXehanger-                   Steel      Water-(E-d*                       One Time Inspection A(,-B2.1,16)
F-ee Heat             LBS         Stainless  Secondary       Loss of matenal Inspection of InternalSurfaces VIII.E-29    3.4.1.16  E, 9 Exchanger                    Steel      Water (Int)                       in Miscellaneous Pipingand (Boric Acid                                                               Ducting Components (B2. 1.22)
Feed)
Neat-           L-BS         Stainless- Steam-(It)      G.a.k.,.          Water Chemistry (92.1.2) and VIk13, 2     3.44.39 Steel                                        One Time Inspection (B2.1.!6)
F-ee Neat-           L-88         Stainle6s  Steam-(R        Lo*ss of material Water Chemistry (B2. 1.2) and   VI.131-3 4.1.-
F.~agsteel                                                        One Time Inspection (132.1416)
Feed)
Neat-           1B8          Stainless- Treated Be*ated GraGking          WateFG hemistry (132.1.2) and VWE513.1.08           E Ehanger-                     Steel      WateF (I t)                       One Time Inspection (B2.1416)
(-ee AG4

Enclosure 2                                                                                                               Section 3.3 PG&E Letter DCL-1 1-136                                                                  AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 40 of 98 Table 3.3.2-8     Auxiliary Systems - Summary of Aging Management Evaluation - Chemical and Volume Control System Component    Intended     Material    Environment   Aging Effect     Aging Management Program        NUREG-     Table 1   Notes Type     Function                                 Requiring                                     1801 Vol. Item Management                                        2 Item Heat          LBS         Stainless  Treated Borated Loss of material Inspection of Internal Surfaces VII.El-17 3.3.1.91  E, 59 Exchanger                 Steel      Water (Int)                      in Miscellaneous Piping and (Boric Acid                                                           Ducting Components Feed)                                                                 (B2. 1.22)W1at A-Gfhp.ietfV-(92.1.2) and One Time Heat          LBS, SIA,   Carbon     Closed Cycle    Loss of material Inspection of Internal Surfaces VII.E1-6  3.3.1.48  E, 98 Exchanger     SS          Steel      Cooling Water                    in Miscellaneous Piping and (Boric Acid                          (Int)                            Ducting Components Vent)                                                                  (B2. 1.22)CGosed Cycle Ceeling W..ater Sytem (B2..1.1
                                                                                          ....
Heat          LBS, SS     Carbon     Demineralized   Loss of material Inspection of InternalSurfaces VIII.E-37  3.4.1.03  E, 9A Exchanger                 Steel      Water (Int)                      in Miscellaneous Piping and (Boric Acid                                                           Ducting Components Vent)                                                                  (B2.1.22)WateF-GemieFy-(832.1.2) and One Time
__________     ncpetion (821.16)  4 Heat           LBS, SS     Stainless  Closed Cycle    Loss of material Inspection of Internal Surfaces VI1.C2-10 3.3.1.50  E, 9D Exchanger                  Steel      Cooling Water                    in Miscellaneous Piping and (Boric Acid                           (Int)                            Ducting Components Vent)                                                                  (B2. 1. ),G2,*Ced Cycle Cooling Water S-yrtem(2.1)
Heat           LBS, SS     Stainless  Secondary       Loss of material Inspection of Internal Surfaces VIII.E-29 3.4.1.16  E, 9G Exchanger                  Steel      Water (Ext)                      in Miscellaneous Piping and (Boric Acid                                                            Ducting Components Vent)                                                                  (B2. 1.22)0Water Chewstp (62.1.2) and One Time
__________   Inpcin I           (812.1.1 6)
Heat-          LBS S&      Stainless- SeGendaFy-      G~aeliR9         Wate Cei It1y (32.1.2) and      VIWI.E30  3.444.4   G Steel      Water-(EA)                       One Time !nspectiGn (B2.1.16)
(BerOGAGi Section 3.3 PG&E Letter DCL-11-136                                                                    AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 41 of 98 Table 3.3.2-8     Auxiliary Systems - Summary of Aging Management Evaluation - Chemical and Volume Control System Component     Intended     Material    Environment     Aging Effect    Aging Management Program        NUREG-      Table I   Notes Type      Function                                  Requiring                                     1801 Vol.      Item Management                                       2 Item Piping        LBS, SIA    Stainless   Demineralized Loss of material Inspection of Internal Surfaces   VIII.E-29 3.4.1.16   E, 9 Steel       Water (Int)                      in Miscellaneous Piping and Ducting Components (B2.1.22)
Piping        LBS, SIA    Stainless   Sodium          Loss of material Inspection of Internal Surfaces None      None       G, 9 Steel       Hydroxide (Int)                  in MiscellaneousPiping and Ducting Components (82.1.22)
Piping        LBS, PB,    Stainless   Treated Borated Loss of material Inspection of Intemal Surfaces  VII.El-17 3.3.1.91   E, 9 SIA         Steel       Water (Int)                      in MiscellaneousPiping and Ducting Components (B2.1.22)
Pump          LBS, RB*-   Carbon      Borated Water   Loss of material Boric Acid Corrosion (B2.1.4)   VII.El-1  3.3.1.89   A SIA         Steel with  Leakage (Ext)
Stainless Steel Cladding Pump          LBS         Carbon      Demineralized   Loss of material Inspection of Internal Surfaces VIII.E-29 3.4.1.16   E, 9A Steel with  Water (Int)                      in MiscellaneousPiping and Stainless                                    Ducting Components Steel                                        (B2.1.22)WateF    Chem'tiy-Cladding                                     (132.1.2) and One Time hIQn (B21 .16)
I_________-np PupB            P-14      Garbon      Treated Borated     faGkir       Water Chemistry (B2.1.2) and VI-17        3.3.1.Q9   E Steel with- WateF (It)                       One-Time Inspection (B2.1..16)
StRA'PeeF Steel-Pump          LBS, RB--   Carbon      Treated Borated Loss of material Water Chemistry (132.1.2) and VII.E1-17 3.3.1.91     E, 5 SIA         Steel with  Water (Int)                      One-Time Inspection (132.1.16)
Stainless Steel Cladding Section 3.3 PG&E Letter DCL-1 1-136                                                                         AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 42 of 98 Table 3.3.2-8     Auxiliary Systems - Summary of Aging Management Evaluation- Chemical and Volume Control System Component    Intended       Material    Environment      Aging Effect       Aging Management Program              NUREG-       Table 1         Notes Type     Function                                      Requiring                                              1801 Vol.      Item Management                                                2 Item pUMP        P9          GaFbon        Treated Berated *-esrs fWmaterial        ater Chemistry (82.1.2* and       V11...4-.2 3I.31.36      E-Steel-with- WateF-(,I4t                            One Time Inspection (12.1.16) stainese-Steel-Pump          LBS          Stainless    Treated Borated Loss of material Inspection of Internal Surfaces           VIlE1-17 3.3.1.91        E, 9 Steel        Water (Int)                          in Miscellaneous Piping and Ducting Components (B2.1.22)
Sight Gauge   LBS, SIA    Stainless Treated Borated Loss of material Inspection of Internal Surfaces               VII. El-17 3.3.1.91      E, 9 Steel         Water (Int)                          in MiscellaneousPiping and Ducting Components (B2. 1.22)
Tank          LBS         Stainless Secondary            Loss of material Inspection of Internal Surfaces          VIII.E-29 3.4.1.16       E, 9 Steel         Water (Int)                          in MiscellaneousPiping and Ducting Components (B2.1.22)
Tak           L4B         S-tainiees- Steam-(nt-)        Granl4              Water Chcmistry (12.1.2) and-
                                                                             )                                     V11..91 2 3.4..-.3       E-,5 Steel                                              One    Ti.,   I         InDEtien 4 4(2 \
T~*LBS                Sainies6-     Steam-(l!nt)     Loss of mnaterial   Water Chemnistry (132.1.2) and-       Vl44.B1   3 3.4..37      E Tank          LBS         Stainless Treated Borated Loss of material         Inspection of Internal Surfaces VII.E1-17 3.3.1.91             E, &9 Steel Cast Water (Int)                             in Miscellaneous Piping and Austenitic                                         Ducting Components (B2. 1.22)AWetear-Ghenis~tfy-(82.1.2) and One Time rIrnspection (82.1.6)                                           ____
Trap          LBS         Carbon        Secondary        Loss of material Inspection of InternalSurfaces VIII.E-34             3.4. 1.04    E, 9 Steel         Water (Int)                          in Miscellaneous Pipingand Ducting Components (B2. 1.22)
Trap          LBS         GaFIbeG       Steam I.nt)      Loss- of mnaterial  Watepr Chemistry (132.1.2) and4       V1119184   3.4.37        E~                           Stee.1                                             Qn     Tm     In        (62n'     -r)
Valve         LBS         Cast Iron     Plant Indoor Air Loss of material    External Surfaces Monitoring          VII.1-8     3.3.1.58     B (Gray Cast (Ext)                                   Program (82.1.20)
Iron)        I_                                   IIII_                                                        __
Section 3.3 PG&E Letter DCL-11-136                                                                              AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 43 of 98 Table 3.3.2-8        Auxiliary >ystems - Summary of Aging Management Evaluation- Chemical and Volume Control System Component        Intended         Material     Environment       Aging Effect      Aging Management Program       NUREG-      Table I        Notes Type         Function                                         Requiring                                       1801 Vol.      Item Management                                         2 Item Valve            LBS            Cast Iron     Ventilation      Loss of material    Inspection of Internal Surfaces V.A-19    3.2.1.32      B (Gray Cast    Atmosphere (Int)                     in Miscellaneous Piping and Iron)                                              Ducting Components (B2.1.22)
Valve            LBS            Cast Iron     Ventilation      Loss of material Selective Leaching of Materials None         None          G, 8 (Gray Cast    Atmosphere (Int)                     (82.1.17)
Iron)
Valve            LBS, PB,       Stainless     Demineralized    Loss of material Inspection of Internal Surfaces    VIII.E-29 3.4. 1.16     E, 9 SIA            Steel         Water (Int)                          in Miscellaneous Pipingand Ducting Components (B2.1.22)
Valve            LBS, SIA       Stainless Sodium               Loss of material Inspection of Internal Surfaces    None      None          G, 9 Steel         Hydroxide (Int)                      in Miscellaneous Piping and Ducting Components (B2.1.22)
Valve            LBS, PB,       Stainless Treated Borated Loss of material Inspection of Internal Surfaces         VIlE.1-17 3.3.1.91      E, 9 SIA            Steel         Water (Int)                          in Miscellaneous Piping and Ducting Components (B2.1.22)
Valve            LBS, SIA       Stainless Treated Borated Loss of material Inspection of Internal Surfaces         VIlE1-17 3.3.1.91       E, 9 Steel Cast Water (Int)                            in Miscellaneous Piping and Austenitic                                         Ducting Components (82.1.22)
Vessel           LBS            Stainless Treated Borated Loss of material Inspection of Intemal Surfaces          VIILE1-17 3.3.1.91      E, 69 Steel         Water (Int)                          in MiscellaneousPiping and Ducting Components (B2.1.22)Water Chemistry (B2.1.2) and One-Time Inspection (B2.1.16)WateF-Chemistry (132.1.2) and Ono-
___ ___
___ ___ _____ ___  _  ___   ___  ___  __   ___  ___    _    imoe !nSPectiOn B .. 6          _  _  _ _  _   _  _ _ _  _  _ _
Notes for Table 3.3.2-8:
Plant Specific Notes:
Section 3.3 PG&E Letter DCL-11-136                                                                   AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 44 of 98 8     Gray Cast Iron SSCs with surfaces exposed to Ventilation Atmosphere (Internal)or Plant Indoor Air (Internal)are subject to wetting due to condensation and thus are subject to loss of material due to selective leaching.
9     Components are associatedwith the boric acid evaporatorsubsystem which is abandoned-in-place. Thus, aging of the components will be managed by the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components aging management program.
Section 3.3 PG&E Letter DCL-1 1-136                                                              AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 45 of 98 Table 3.3.2-11   Auxiliary Systems - Summary of Aging Management Evaluation - Auxiliary Building HVAC System Component     Intended     Material   Environment    Aging Effect        Aging Management        NUREG-      Table 1   Notes Type      Function                                Requiring                Program           1801 Vol.      Item Management                                    2 Item Damper         PB         Cast Iron    Plant Indoor  Loss of material External Surfaces Monitoring VII.F2-2 3.3.1.56   B (Gray Cast   Air (Ext)                      Program (B2.1.20)
Iron)
Damper         PB         Cast Iron    Ventilation   Loss of material Inspection of Internal       VII.F2-3  3.3.1.72  B (Gray Cast   Atmosphere                     Surfaces in Miscellaneous Iron)        (Int)                          Piping and Ducting Components (B2.1.22)
Damper         PB         Cast Iron    Ventilation   Loss of material Selective Leaching of        None      None      G, 5 (Gray Cast   Atmosphere                     Materials(B2.1.17)
Iron)        (Int)
Pump           LBS        Carbon Steel Closed Cycle  Loss of material Closed-Cycle Cooling Water VII.F2-18 3.3.1.47    B Cooling Water                  System (B2. 1.10)
(Int)
Pump           LBS        Carbon Steel Plant Indoor  Loss of material External Surfaces Monitoring VII. I-8  3.3. 1.58 B Air (Ext)                      Program(B2.1.20)
Pump           LBS        Cast Iron    Closed Cycle  Loss of material Closed-Cycle Cooling Water VII.F2-18 3.3.1.47    B (Gray Cast Cooling Water                    System (B2. 1.10)
Iron)        (Int)
Pump           LBS        Cast Iron    Plant Indoor  Loss of material External Surfaces Monitoring VII.I-8   3.3.1.58  B (Gray Cast Air (Ext)                        Program (B2.1.20)
Iron)
Pump           LBS        Cast Iron    Closed Cycle  Loss of material Selective Leaching of        VII. C2-8 3.3. 1.85 A (Gray Cast Cooling Water                    Materials (B2. 1.17)
Iron)        (Int)
Valve          LBS        CopperAlloy Closed Cycle   Loss of material Closed-Cycle Cooling Water VII.F2-13 3.3.1.51    B
(> 15% Zinc) Cooling Water                  System (B2. 1.10)
(Int)
Valve          LBS        CopperAlloy Demineralized  Loss of material Water Chemistry (B2. 1.2)    VIII.A-5  3.4.1.15  A
(> 15% Zinc) Water (Int)                    and One-Time Inspection (B2.1.16)

Enclosure 2                                                                                                                         Section 3.3 PG&E Letter DCL-11-136                                                                        AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 46 of 98 Table 3.3.2-11       Auxiliary Systems - Summary of Aging Management Evaluation - Auxiliary Building HVAC System Component         Intended    Material     Environment       Aging Effect          Aging Management       NUREG-       Table I       Notes Type          Function                                     Requiring                 Program          1801 Vol.      Item Management                                     2 Item Valve              LBS         CopperAlloy Potable Water Loss of material Inspection of Internal            None       None         G
(> 15% Zinc) (Int)                                 Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Notes for Table 3.3.2-11:
Plant Specific Notes:
I 5       Gray Cast Iron SSCs with surfaces exposed to Ventilation Atmosphere (Internal)or Plant IndoorAir (Internal)are subject to wetting due to condensation and thus are subject to loss of material due to selective leaching.
Section 3.3 PG&E Letter DCL-11-136                                                                          AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 47 of 98 Table 3.3.2-12 Auxiliary Systems - Summary of Aging Management Evaluation - Fire Protection System Component            Intended     Material     Environment      Aging Effect     Aging Management Program NUREG-            Table 1      Notes Type             Function                                     Requiring                                    1801 Vol.      Item Management                                       2 Item Hydrant               PB         Gasbt.Frn      Buried (Ext)     Loss of material   Buried Piping and Tanks      VII.G-25 3.3.1.19       B Carbon Steel                                       Inspection (B2.1.18)
Hydrant               PB         Cast-rGn       Raw Water (Int)  Loss of material   Fire Water System (B2.1.13)  VII.G-24 3.3.1.68       B Carbon Steel Piping                PB         Cast Iron      Buried (Ext)     Loss of material Selective Leaching of           VII. G-15 3.3.1.85     A (Gray Cast                                         Materials(B2.1.17)
Iron)
Piping                PB         Cast Iron      Buried (Ext)     Loss of material   Buried Piping and Tanks      VII.G-25   3.3.1.19     B (Gray Cast                                         Inspection (B2.1.18)
Iron)
Piping                PB         Cast Iron      Raw Water (Int) Loss of material Selective Leaching of            VII. G-14 3.3.1.85     A (Gray Cast                                         Materials(B2.1.17)
Iron)
Piping                PB         Cast Iron      Raw Water (Int)  Loss of material   Fire Water System (B2.1.13)  VII.G-24   3.3.1.68     B (Gray Cast Iron)
Pump                  PB, SS     Cast Iron      Plant Indoor Air Loss of material   External Surfaces Monitoring VII.1-8    3.3.1.58     B (Gray Cast     (Ext)                               Program (B2.1.20)
Iron)
Pump                  PB, SS     Cast Iron      Raw Water (Int)  Loss of material Selective Leaching of          VII. G-14  3.3.1.85     A (Gray Cast                                         Materials (B2.1.17)
Iron)
Pump                  PB, SS     Cast Iron      Raw Water (Int)  Loss of material   Fire Water System (B2.1.13)  VII.G-24   3.3.1.68     B (Gray Cast Iron)
Straine               PB         Cast trn       Plnt IndoorAir- Less of Mat            ernal Surfaces Monitoring V11-.-8    3-3--.58     B St-a*e+               P19B       CGa    ,t-,,,, Raw-WateF-IR     Loess of Mate alFe      Water Sytem, (B2.113)   V11G-24    3-1-6        B Valve                 PB9        C;stI          At!oenep    /-n  Losseofmato        External Surfaces Monitoring V11-.9     23-4
___________Weatherf-&#xfd;                                                     Program (62.1.20)
Section 3.3 PG&E Letter DCL-1 1-136                                                                       AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 48 of 98 Table 3.3.2-12 Auxiliary Systems - Summary of Aging ManagementEvaluation - Fire Protection System Component          Intended    Material     Environment       Aging Effect     Aging Management Program          NUREG-       Table 1     Notes Type           Function                                     Requiring                                        1801 Vol. Item Management                                          2 Item Valve              P9         Gaet 'FO     B~ied(E~d)         LOSS Of mAaterial  3Urfied Piping and Tanks         V1 G :25   3.4.49      a nsperti*n (B21 2,18)
Valve              124B       C;-t Itn      PlAnt Indoor Ar   Loss of matr       'nspection of internal S'urfaces VJ G-2,                B34.71 (14#,n                                   M.scc        uneo'us Piping and Durting Components Valve              P-B        Ga6t ken     Raw-WateF-(IP      Lo6ss ef materia   Fire Water System (B2.1.13)      VWG 24     331.6       a Valve              PB9        Cast-!Fen     Dy Ga&-{(I4t      Ne.R               Ne.~e                            Vlk-2~3    3.3.1.7~ A Valve              PB         Cast Iron    Plant IndoorAir    Loss of material Inspection of InternalSurfaces VII. G-23      3.3.1.71    B (Gray Cast   (Int)                                 in MiscellaneousPiping and Iron)                                              Ducting Components (B2.1.22)
Valve              PB         Cast Iron    Plant IndoorAir    Loss of material Selective Leaching of              None       None        G, 4 (Gray Cast   (Int)                                 Materials (B2.1.17)
Iron)
Notes for Table 3.3.2-12:
Plant Speciflc Notes:
4       Gray Cast Iron SSCs with surfaces exposed to Ventilation Atmosphere (Internal)or Plant IndoorAir (Internal)are subject to wetting due to condensationand thus are subject to loss of materialdue to selective leaching.
Section 3.3 PG&E Letter DCL-1 1-136                                                                   AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 49 of 98 I aDle ,.J. 3- 7,1   AUXllar  -ysrems - ,ummary OT i*-glng managemenrtvaiuarion- ulesei ueneraror -uel (iIl >ysrem Component        Intended    Material   Environment     Aging Effect         Aging Management           NUREG-      Table I   Notes Type          Function                                Requiring                 Program              1801 Vol. Item Management                                       2 Item Pump               PB        Gast-        Fuel Oil (Int) Loss of material Fuel Oil Chemistry (B2.1.14) VII.H1-10 3.3.1.20      B GeaDuctile                                 and One-Time Inspection Iron                                         (B2.1.16)
Pump               PB        Cast-        Plant Indoor   Loss of material External Surfaces Monitoring VII.1-8       3.3.1.58  B k-GeDuctile Air (Ext)                        Program (B2.1.20)
Iron Valve              PB        cast r!O       FUeI-Gil-(E))  Loss o-f Matei   Fuel, Oil Chem*.istF (132.1.14). V14*1..
                                                                                                              -. 0 3.1.20      B
                                                                          *and- One Tirnc Inspepion Valve              P-B       Cas4t Iron   FUGl      Int) L0o6 Of materl   FuRlOil ChemiQtr4 (B2.1.11) V4.H! 10 3.3.20          B and One Time Inspection Section 3.3 PG&E Letter DCL-1 1-136                                                                 AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 50 of 98 Table 3.3.2-14    Auxiliary Systems - Summary of Aging ManagementEvaluation - Diesel GeneratorSystem Component    Intended     Material     Environment        Aging Effect     Aging Management        NUREG- Table 1 Item    Notes Type      Function                                      Requiring              Program          1801 Vol.
Management                                 2 Item Compressor    SIA        Cast Iron    Plant Indoor Air    Loss of material External Surfaces        VII.I-8    3.3.1.58  B (Gray Cast   (Ext)                                Monitoring Program Iron)                                             (B2.11.20)
Compressor    SIA        Cast Iron    Plant Indoor Air    Loss of material Inspection of Internal   VIII.G-34  3.4.1.30  D (Gray Cast   (Int)                                Surfaces in Iron)                                             Miscellaneous Piping and Ducting Components (B2.1.22)
Compressor    SIA        Cast Iron    Plant Indoor Air    Loss of material Selective Leaching of    None       None      G, 3 (Gray Cast   (Int)                                Materials(B2.1.17)
Iron)
Pump          PB         Cast Iron    Closed Cycle        Loss of material Selective Leaching of    VII. C2-8  3.3.1.85  A (Gray Cast   Cooling Water (Int)                  Materials(B2.1.17)
Iron)
Pump          PB         Cast Iron    Closed Cycle        Loss of material Closed-Cycle Cooling     VII.H2-23  3.3.1.47  B (Gray Cast   Cooling Water (Int)                  Water System (B2. 1.10)
Iron)
Pump          LBS, PB,   Cast Iron    Fuel Oil (Int)      Loss of material Fuel Oil Chemistry       VII.H2-24  3.3.1.20  B SIA         (Gray Cast                                        (B2.1.14) and One-Time Iron)                                             Inspection (B2.1.16)
Pump         LBS, PB     Cast Iron    Lubricating Oil     Loss of material Lubricating Oil Analysis VII.H2-20  3.3.1.14  B (Gray Cast   (Int)                                (B2.1.23) and One-Time Iron)                                             Inspection (B2.1.16)
Pump         LBS, PB,   Cast Iron     Plant Indoor Air    Loss of material External Surfaces        VII.I-8    3.3.1.58  B SIA         (Gray Cast   (Ext)                                Monitoring Program Iron)                                             (B2.1.20)
Sight Gauge  PB          Carbon Steel Fuel Oil (Int)      Loss of material Fuel Oil Chemistry       VII.1H2-24 3.3.1.20  B (B2. 1.14) and One-Time Inspection (B2.1.16)
Sight Gauge  PB          Carbon Steel Plant IndoorAir     Loss of material External Surfaces        VII. 1-8   3.3.1.58  B (Ext)                                Monitoring Program (B2.1.20)
Section 3.3 PG&E Letter DCL-1 1-136                                                                 AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 51 of 98 Table 3.3.2-14   Auxiliary Systems - Summary of Aging Management Evaluation - Diesel GeneratorSystem Component   Intended     Material     Environment         Aging Effect     Aging Management        NUREG- Table I Item    Notes Type     Function                                       Requiring              Program          1801 Vol.
Management                                 2 Item Sight Gauge  PB         Cast Iron   Fuel Oil (Int)      Loss of material   Fuel Oil Chemistry       VII.H2-24 33.1.20    B (Gray Cast                                         (B2.1.14) and One-Time Iron)                                              Inspection (B2.1.16)
Sight Gauge  PB         Cast Iron   Plant Indoor Air    Loss of material   External Surfaces        VII.I-8    3.3.1.58  B (Gray Cast  (Ext)                                  Monitoring Program Iron)                                              (B2.1.20)
Valve        PB         Cast Iron   Closed Cycle        Loss of material   Selective Leaching of    VII. C2-8  3.3.1.85  A (Gray Cast  Cooling Water (Int)                    Materials(B2.1.17)
Iron)
Valve        PB         Cast Iron   Closed Cycle        Loss of material   Closed-Cycle Cooling     VII.H2-23  3.3.1.47  B (Gray Cast  Cooling Water (Int)                    Water System (B2.! .10)
Iron)
Valve        PB9        Cast-'FOR   Fuel-Oil-(IPA)      L-eocs of material Fuel Oil Chemictry       VIWH2-224  3.3.1.20  B (B2.1.141) and One Time Valve        PB         Cast Iron   Lubricating Oil     Loss of material   Lubricating Oil Analysis VII.H2-20  3.3.1.14  B (Gray Cast  (Int)                                  (B2.1.23) and One-Time Iron)                                              Inspection (B2.1.16)
Valve        PB         Cast Iron   Plant Indoor Air    Loss of material   External Surfaces        VII.I-8    3.3.1.58  B (Gray Cast  (Ext)                                  Monitoring Program Iron)                                              (B2.1.20)
Valve        PB         Cast Iron   Plant Indoor Air    Loss of material   Inspection of Internal   VII.H2-21  3.3.1.71  B (Gray Cast  (Int)                                  Surfaces in Iron)                                              Miscellaneous Piping and Ducting Components (B2.1.22)
Valve        PB         Cast Iron   Plant IndoorAir     Loss of material   Selective Leaching of    None       None      G, 3 (Gray Cast  (Int)                                  Materials(B2. 1.17)
Ilron)
Section 3.3 PG&E Letter DCL-11-136                                                                     AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 52 of 98 Notes for Table 3.3.2-14:
Plant Specific Notes:
3       Gray Cast Iron SSCs with surfaces exposed to Ventilation Atmosphere (Internal)or Plant IndoorAir (Internal)are subject to wetting due to condensationand thus are subject to loss of materialdue to selective leaching.
Section 3.3 PG&E Letter DCL-1 1-136                                                            AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 53 of 98 Table 3.3.2-16 Auxiliary Systems - Summary of Aging Management Evaluation- Gaseous Radwaste System Component    Intended    Material     Environment     Aging Effect     Aging Management      NUREG- Table 1 Item    Notes Type     Function                                   Requiring             Program        1801 Vol.
Management                               2 Item Compressor    LBS, SS  Cast Iron    Plant Indoor Air Loss of material External Surfaces      VII.1-8    3.3.1.58  B (Gray Cast   (Ext)                             Monitoring Program Iron)                                          (92.11.20)
Compressor    LBS, SS  Cast Iron    Plant Indoor Air Loss of material Inspection of Internal VII.G-23   3.3.1.71  B (Gray Cast   (Int)                             Surfaces in Iron)                                          Miscellaneous Piping and Ducting Components (B2.11.22)
Compressor   LBS, SS   Cast Iron    PlantIndoor Air  Loss of material Selective Leaching of  None       None      G, 6 (Gray Cast   (Int)                             Materials(B2.1.17)
Iron)
Compressor   LBS, SS   Cast Iron    Raw Water (Int)  Loss of material Selective Leaching of  VII. Cl-11 3.3.1.85  A (Gray Cast                                     Materials(B2.1.17)
Iron)
Compressor   LBS, SS   Cast Iron    Raw Water (Int)  Loss of material Inspection of Internal VII.C1-19  3.3.1.76  E, 3 (Gray Cast                                     Surfaces in Iron)                                          Miscellaneous Piping and Ducting Components (B2.11.22)
Valve        LBS       CopperAlloy Plant Indoor Air  Loss of material Inspection of Internal VII. G-9   3.3.1.28  E, 5
(> 15% Zinc) (Int)                             Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Valve        LBS, SS   CopperAlloy Raw Water (Int)   Loss of material Inspection of Internal VI1.C1-9   3.3.1.81  E, 3
(> 15% Zinc)                                   Surfaces in Miscellaneous Piping and Ducting Components (B2. 1.22)
Section 3.3 PG&E Letter DCL-11-136                                                                     AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 54 of 98 Notes for Table 3.3.2-16:
Plant Specific Notes:
5       NUREG-1801, Section XI. M24, CompressedAir Monitoring applies to monitoring of the piping and components associatedwith the air compressors and dryers. Air compressorand dryerpiping and components are not in scope for DCPP. In scope piping and components are associatedwith containmentpenetrationsand air/nitrogengas piping and components for backup operationof valves. Therefore NUREG-1801, Section XI.M24 is not considered applicableto DCPPand different aging managementprogramsare specified for the in scope piping and components.
6       Gray Cast Iron SSCs with surfaces exposed to Ventilation Atmosphere (Internal)or Plant Indoor Air (Internal)are subject to wetting due to condensation and thus are subject to loss of materialdue to selective leaching.
Section 3.3 PG&E Letter DCL-1 1-136                                                             AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 55 of 98 Table 3.3.2-17 Auxiliary Systems - Summary of Aging Management Evaluation- Liquid Radwaste System Component    Intended    Material     Environment     Aging Effect     Aging Management      NUREG- Table 1 Item    Notes Type     Function                                  Requiring              Program        1801 Vol.
Management                               2 Item Piping        LBS       Carbon Steel Raw Water (Int)  Loss of material Inspection of Internal VII.C1-19 3.3.1.76   E, 8 Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Piping        LBS       Stainless    Raw Water (Int)  Loss of material Inspection of Internal VII.C1-15  3.3.1.79  E, 8 Steel                                          Surfaces in Miscellaneous Piping and Ducting Components (B2. 1.22)
Sample Cooler LBS, SIA  Copper Alloy Raw Water (Int)  Loss of material Inspection of Internal VII CI-9   3.3 1.81  E, 3
(> 15% Zinc)                                   Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Strainer      LBS       Cast Iron    Plant Indoor Air Loss of material External Surfaces      VII.I-8    3.3.1.58  B (Gray Cast   (Ext)                             Monitoring Program Iron)                                          (82.1.20)
Strainer      LBS       Cast Iron    Raw Water (Int)  Loss of material Selective Leaching of  VII. Cl-11 3.3.1.85  A (Gray Cast                                     Materials (B2. 1.17)
Iron)
Strainer      LBS       Cast Iron    Raw Water (Int)  Loss of material Inspection of Internal VII.C1-19  3.3.1.76  E, 2 (Gray Cast                                     Surfaces in Iron)                                          Miscellaneous Piping and Ducting Components (12.1.22)
Trap          LBS       Cast Iron    Plant Indoor Air Loss of material External Surfaces      VII.I-8    3.3.1.58  B (Gray Cast   (Ext)                             Monitoring Program Iron)                                          (B2.1.20)
Trap          LBS       Cast Iron    Raw Water (Int)  Loss of material Selective Leaching of  VII.Cl-11  3.3. 1.85 A (Gray Cast                                     Materials(B2.1.17)
Iron)
Section 3.3 PG&E Letter DCL-1 1-136                                                                   AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 56 of 98 Table 3.3.2-17 Auxiliary Systems - Summary of Aging Management Evaluation - Liquid Radwaste System Component      Intended    Material       Environment       Aging Effect      Aging Management      NUREG- Table 1 Item       Notes Type        Function                                       Requiring             Program         1801 Vol.
Management                                2 Item Trap             LBS      Cast Iron      Raw Water (Int)    Loss of material  Inspection of Internal VII.C1-19 3.3.1.76      E, 2 (Gray Cast                                          Surfaces in Iron)                                               Miscellaneous Piping and Ducting Components (B2.11.22)
Valve            LBS, PB, Cast Iron      Plant Indoor Air   Loss of material  External Surfaces      VII.I-8    3.3.1.58     B SIA       (Gray Cast     (Ext)                                Monitoring Program Iron)                                               (B2.1.20)
Valve           LBS, SIA  Cast Iron      Raw Water (Int)    Loss of materal   Selective Leaching of  VII. C1-11 3.3.1.85     A (Gray Cast                                          Materials(B2.1.17)
Iron)
Valve           LBS, PB,  Cast Iron      Raw Water (Int)    Loss of material  Inspection of Internal VII.C1-19  3.3.1.76     E, 2 SIA       (Gray Cast                                          Surfaces in Iron)                                               Miscellaneous Piping and Ducting Components (B2.1.22)
Valve           LBS       Copper Alloy Demineralized        Loss of material  Water Chemistry        VIII. F-15 3.4.1.15     A
(> 15% Zinc) Water (Int)                            (B2.1.2) and One-Time Inspection (B2.1.16)
Valve           LBS       Stainless      Raw Water (Int)    Loss of material  Inspection of Internal VII. C1-15 3.3. 1.79    E, 8 Steel                                               Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22) I Notes for Table 3.3.2-17:
Plant Specific Notes:
8       Components are associatedwith the boric acid evaporatorsubsystem which is abandoned-in-place. Thus, aging of the components will be managed by the Inspection of InternalSurfaces in MiscellaneousPiping and Ducting Components aging managementprogram.
Section 3.3 PG&E Letter DCL-1 1-136                                                              AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 57 of 98 Table 3.3.2-18   Auxiliary Systems - Summary of Aging Management Evaluation- Miscellaneous Systems in scope ONLY for Criterion 10 CFR 54.4(a)(2)
Component   Intended     Material      Environment    Aging Effect      Aging Management      NUREG- Table 1 Item    Notes Type     Function                                   Requiring               Program        1801 Vol.
Management                                2 Item Piping       LBS        Carbon Steel Secondary Water Loss of material   Inspection of Internal VIII. C-7  3.4. 1.04 E, 7 (Int)                              Surfaces in MiscellaneousPiping and Ducting Components (B2. 1.22)
Piping       LBS        Cast Iron    Plant Indoor Air Loss of material  External Surfaces      VII.I-8    3.3.1.58  B (Gray Cast   (Ext)                              Monitoring Program Iron)                                           (B2.11.20)
Piping       LBS        Cast Iron    Plant Indoor Air Loss of material  Inspection of Internal VII.G-23   3.3.1.71  B (Gray Cast   (Int)                              Surfaces in Iron)                                           Miscellaneous Piping and Ducting Components (B2.1.22)
Piping       LBS        Cast Iron    Plant Indoor Air Loss of material  Selective Leaching of  None       None      G, 6 (Gray Cast   (Int)                              Materials(B2.1.17)
Iron)
Piping       LBS        Cast Iron    Raw Water (Int)  Loss of material  Selective Leaching of  VII.C1-11  3.3.1.85  A (Gray Cast                                      Materials(B2.1.17)
Iron)
Piping       LBS        Cast Iron    Raw Water (Int)  Loss of material  Inspection of Internal VI1.C1-19  3.3.1.76  E, 5 (Gray Cast                                      Surfaces in Iron)                                           Miscellaneous Piping and Ducting IComponents (B2.1.22)
Section 3.3 PG&E Letter DCL-11-136                                                                                    AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 58 of 98 Table 3.3.2-18 Auxiliary Systems - Summary of Aging Management Evaluation- Miscellaneous Systems in scope ONLY for Criterion 10 CFR 54.4(a)(2)
Component    Intended       Material         Environment                Aging Effect         Aging Management        NUREG- Table 1 Item            Notes Type    Function                                                     Requiring                 Program          1801 Vol.
Management                                      2 Item Piping        LBS       Stainless         Treated Borated             Loss of material      Inspection of Internal   VILE1-17 3.3.1.91            E, 47 Steel             Water (Int)                                       Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)Wate-Chemistry (92.1.2) and One Time InSPetionr PR9LiS              StP4ee            Trceated BorFated           G~aeking             WateFCemnistry            VlLE 1-2-0   134,90          E,-4 Stee4             Wateriont)                                       (12.1.2) and One Time
_.n.p.ction (B2.1.16)
PVPLas              Gast-lken         GlosedeGyGde-r....,:. A+.. i^-
I,*/.,*\
Loas s of ma teri;al Glesod    Cycle Cooling
                                                                                           *^AI4,r e,**, /0' 1 10)\
VWC.2-44     3.3.1.7         9 PUM                     Ca1st-ken         Plant Indoor Air            Loss of materil      ExteRl SrfRAce            VIW4         3.4i598         B Monitoring Program (B\......                                              __  _  _   _
Strainer      LBS       Cast Iron         Closed Cycle                Loss of material     Selective Leaching of     VII. C2-8    3.3. 1 85       A (Gray Cast        Cooling Water (Int)                              Materials (B2. 1.17)
Iron)
Strainer      LBS       Cast Iron         Closed Cycle               Loss of material      Closed-Cycle Cooling      VII.C2-14    3.3.1.47        B (Gray Cast        Cooling Water (Int)                              Water System (B2.1 .10)
Iron)
Strainer      LBS       Cast Iron         Plant Indoor Air           Loss of material      External Surfaces         VII.I-8      3.3.1.58        B (Gray Cast        (Ext)                                            Monitoring Program Iron)                                                              (B2.1.20)
Valve                   Cast
                           ,       oeR    GIed' G*'le-               Loss of material      OlGoso6d Cycle C9ooing    VIIIG2 44    3.347           B
                                                        ~
I~~~~   ~        Geln Wae4#4                 Sytex&#xfd;       *1te Valve        LBS        Gast eFeR         Pat Indoo Air                      of material   Eternal SurfacFs          VWIP         3.-.-fl         B kEA)                                             Monitorn*g Program
___
__ __
_ ___
_   __ __   __ _  _   __  __    ___     __     __    ___   _      k&  24,20)                     _     _   __-    __ ___    __    _
Section 3.3 PG&E Letter DCL-11-136                                                                               AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 59 of 98 Table 3.3.2-18       Auxiliary Systems - Summary of Aging Management Evaluation- Miscellaneous Systems in scope ONLY for Criterion 10 CFR 54.4(a)(2)
Component      Intended            Material              Environment   Aging Effect     Aging Management       NUREG- Table I Item      Notes Type        Function                                                  Requiring             Program         1801 Vol.
Management                               2 Item Valve            LBS             Stainless            Secondary Water Loss of material  Inspection of Internal  VIII.D1-4 3.4. 1.16  E, 7 Steel                (Int)                             Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Valve            LBS             Stainless            Treated Borated  Loss of material Inspection of Internal  VII.E1-17  3.3.1.91  E, 47 Steel                Water (Int)                       Surfaces in Miscellaneous Piping and Ducting Components (B2.1. 22)ater-CheFmistry (62.1.2) and Gno  Time Inspection Valve           LB.S             Stai$ ess-             rated RBrted-  G4aGk4Rg         Water-GlCh              V.E4-20     .. 1.90  E--4 Steel                Water {l,                         (132.1.2) ad GRe Time
__________________
__________________________________                     Inspection (B324-4.6)
Notes for Table 3.3.2-18:
Plant Specific Notes:
6       Gray Cast Iron SSCs with surfaces exposed to Ventilation Atmosphere (Internal)or Plant Indoor Air (Internal)are subject to wetting due to condensationand thus are subject to loss of material due to selective leaching.
7       Components are associatedwith the boric acid evaporatorsubsystem which is abandoned-in-place. Thus, aging of the components will be managedby the Inspection of Internal Surfaces in Miscellaneous Pipingand Ducting Components aging managementprogram.

Enclosure 2                                                                                                          Section 3.3 PG&E Letter DCL-1 1-136                                                              AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 60 of 98 Table 3.3.2-19     Auxiliary Systems - Summary of Aging Management Evaluation- Oily Water and Turbine Sump System Component Intended          Material     Environment    Aging Effect     Aging Management      NUREG- Table 1 Item    Notes Type      Function                                    Requiring            Program         1801 Vol.
Management                               2 Item Piping         PB         Cast Iron   Encased in       None             None                   VII.J-21   3.3.1.96  A (Gray Cast  Concrete (Ext)
Iron)
Piping         LBS        Cast Iron   Plant Indoor Air Loss of material External Surfaces      VII.I-8    3.3.1.58  B (GrayCast   (Ext)                             Monitoring Program Iron)                                         (B2.1.20)
Piping         LBS, PB    Cast Iron   Plant Indoor Air Loss of material Inspection of Internal VII.G-23   3.3.1.71  B (Gray Cast  (Int)                             Surfaces in Iron)                                         Miscellaneous Piping and Ducting Components (B2.1.22)
Piping         LBS, PB    Cast Iron   Plant IndoorAir  Loss of material Selective Leaching of  None       None      G, 3 (Gray Cast  (Int)                             Materials (B2. 1.17)
Iron)
Piping         LBS, PB    Cast Iron   Raw Water (Int)  Loss of material Selective Leaching of  VII.C1-11  3.3.1.85  A (Gray Cast                                    Materials(B2.1.17)
Iron)
Piping         LBS, PB    Cast Iron   Raw Water (Int)  Loss of material Inspection of Internal VII.C1-19  3.3.1.76  E, 2 (Gray Cast                                    Surfaces in Iron)                                         Miscellaneous Piping and Ducting Components (B2.11.22)
Pump           LBS        Cast Iron   Plant Indoor Air Loss of material External Surfaces      VII.I-8    3.3.1.58  B (Gray Cast  (Ext)                             Monitoring Program Iron)                                         (B2.1.20)
Pump           LBS        Cast Iron   Raw Water (Int)  Loss of material Selective Leaching of  VII. Cl-11 3.3. 1.85 A (Gray Cast                                    Materials (B2. 1.17)
Iron)
Section 3.3 PG&E Letter DCL-11-136                                                                          AGING MANAGEMENT OF AUXILIARY SYSTEMS Page 61 of 98 Table 3.3.2-19       Auxiliary Systems - Summary of Aging Management Evaluation- Oily Water and Turbine Sump System Component       Intended      Material    Environment          Aging Effect        Aging Management       NUREG- Table I Item         Notes Type        Function                                        Requiring                Program          1801 Vol.
Management                                  2 Item Pump             LBS        Cast Iron   Raw Water (Int)      Loss of material     Inspection of Internal VII.C1-19 3.3.1.76         E, 2 (Gray Cast                                            Surfaces in Iron)                                                 Miscellaneous Piping and Ducting Components (12.1.22)   1 Notes for Table 3.3.2-19:
Plant Specific Notes:
3        Gray Cast Iron SSCs with surfaces exposed to Ventilation Atmosphere (Internal)or Plant IndoorAir (Internal)are subject to wetting due to condensationand thus are subject to loss of material due to selective leaching.
Section 3.4 PG&E Letter DCL-1 1-136                               AGING MANAGEMENT OF STEAM AND Page 62 of 98                                                POWER CONVERSION SYSTEM 3.4.2.1.1    Turbine Steam Supply System Materials The materials of construction for the turbine steam supply system component types are:
           *Cast   Iron
* Cast Iron (Gray Cast Iron)
Aging Management Programs The following aging management programs manage the aging effects for the turbine steam supply system component types:
* Selective Leaching of Materials (B2.1.17)
Section 3.4 PG&E Letter DCL-11-136                                AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Page 63 of 98 3.4.2.1.2    Auxiliary Steam System Materials The materials of construction for the auxiliary steam system component types are:
         -   Cact Iron Section 3.4 PG&E Letter DCL-1 1-136                               AGING MANAGEMENT OF STEAM AND POWER CONVERSION SYSTEM Page 64 of 98 3.4.2.1.4     Condensate System Materials The materials of construction for the condensate system component types are:
* Cas t Iron
* Cast Iron (Gray Cast Iron)
Aging Management Programs The following aging management programs manage the aging effects for the condensate system component types:
* Selective Leaching of Materials (B2. 1.17)
Section 3.4 PG&E Letter DCL-1 1-136                                                                     AGING MANAGEMENT OF STEAM AND Page 65 of 98                                                                                        POWER CONVERSION SYSTEM Table 3.4.2-1    Steam and Power Conversion System - Summary of Aging Management Evaluation- Turbine Steam Suppl, System Component    Intended     Material     Environment    Aging Effect     Aging Management        NUREG- Table 1 Item   Notes Type     Function                                  Requiring             Program          1801 Vol.
Management                                2 Item Valve         LBS       Cast Iron   Plant Indoor Air Loss of material External Surfaces       VIII.H-7   3.4.1.28   B (GrayCast   (Ext)                             Monitoring Program Iron)                                         (B2.1.20)
Valve         LBS       Cast Iron   Secondary Water Loss of material  Selective Leaching of    VIII.A-8  3.4.1.36   A (Gray Cast  (Int)                             Materials(B2.1.17)
Iron)
Valve         LBS       Cast Iron   Secondary Water  Loss of material Water Chemistry         VIII.D1-8  3.4.1.04   A (Gray Cast  (Int)                             (B2.1.2) and One-Time Iron)                                         Inspection (B2.1.16)
Section 3.4 PG&E Letter DCL-11-136                                                                                   AGING MANAGEMENT OF STEAM AND Page 66 of 98                                                                                                     POWER CONVERSION SYSTEM Table 3.4.2-2      Steam and Power Conversion System - Summary of Aging Management Evaluation - Auxiliary Steam System Component      Intended         Material      Environment        Aging Effect     Aging Management           NUREG- Table 1 Item     Notes Type       Function                                             Requiring           Program             1801 Vol.
Management                                   2 Item Heat           LBS, SIA, Carbon Steel Closed Cycle              Loss of material Inspection of Internal    VIII.G-5     3.4.1.24  BE, 8 Exchanger      SS                           Cooling Water (Int)                  Surfaces in (Aux Steam                                                                       Miscellaneous Piping Drain Rec Vent                                                                   and Ducting Cond)                                                                            Components (B2.1.22)CGesed-Cy*e Cooling Water System Heat           LBS, SIA, Carbon Steel Secondary Water Loss of material           Inspection of Internal    VIII.B 1-11  3.4.1.04  E, 8 Exchanger      SS                           (Int)                                Surfaces in (Aux Steam                                                                       Miscellaneous Piping Drain Rec Vent                                                                   and Ducting Cond)                                                                            Components (B2. 1.22)
Heati          LBS.SLA- GarIbon Steel Steaondat)                Loss of material Inspection of Intemal     VIII.B1-1    3.4.1.47  E-,8 Ss                            Int)er-                             Surfaces in Miscellaneous Piping Drain Rec Vent                                                                   and Ducfing (32,44a)Water-Ghemicstry (132.1.2) and Ono Time InsPection CGI1 om~ponents(2..2)
Piping         LBS            Carbon Steel Secondary Water Loss of material      Inspection of Internal    VIII. BI-11 3.4.1.04   E, 8 (Int)                                Surfaces in Miscellaneous Piping and Ducting,
__________ __  ____
______ __   ____   ____ ___    ___________     Components (B2. 1.22)      _   _  _ __   _____   _____
Section 3.4 PG&E Letter DCL-1 1-136                                                                                     AGING MANAGEMENT OF STEAM AND Page 66 of 98                                                                                                        POWER CONVERSION SYSTEM Table 3.4.2-2       Steam and Power Conversion System - Summary of Aging Management Evaluation- Auxiliary Steam System Component       Intended        Material          Environment       Aging Effect     Aging Management          NUREG- Table 1 Item      Notes Type       Function                                               Requiring           Program            1801 Vol.
Management                                   2 Item Heat            LBS, SIA, Carbon Steel Closed Cycle                Loss of material Inspection of Internal    VIII.G-5      3.4.1.24 BE, 8 Exchanger       SS                             Cooling Water (Int)                  Surfaces in (Aux Steam                                                                          Miscellaneous Piping Drain Rec Vent                                                                      and Ducting Cond)                                                                               Components (B2.1.22)GIosed Heat            LBS, SIA, Carbon Steel Secondary Water Loss of material             Inspection of Internal    VIII.B1-11 3.4.1.04    E, 8 Exchanger       SS                             (Int)                                Surfaces in (Aux Steam                                                                          Miscellaneous Piping Drain Rec Vent                                                                      and Ducting Cond)                                                                               Components (B2. 1.22)
Heatn           LBS13        Carb Steel Steam(ondrt           e Loss of material    Inspection of Internmal   V.ILB13     1 3.4.1.37 E, 8 nha)e-                             Surfaes in (Auteasclanous                                                                                      Piping rFain Rcc Vent                                                                     and Ducting oemponents Ghomistr; (62.1.2) and One Time !neopectiOn Piping          LBS          Carbon Steel Secondary Water Loss of material          Inspection of Internal    VIII. B 1-11 3.4.1.04  E, 8 (Int)                                Surfaces in Miscellaneous Piping and Ducting
____ ____ __ _ ____
______ __ _   ____  ___ ___    ___________     Components (B2. 1.22)     _   _   _  __   _____  _____
Section 3.4 PG&E Letter DCL-11-136                                                                             AGING MANAGEMENT OF STEAM AND Page 67 of 98                                                                                               POWER CONVERSION SYSTEM Table 3.4.2-2          Steam and Power Conversion System - Summary of Aging Management Evaluation- Auxiliary Steam System Component          Intended    Material     Environment     Aging Effect     Aging Management        NUREG- Table 1 Item     Notes Type          Function                                   Requiring            Program           1801 Vol.
Management                                2 Item Piping             LBS       Stainless    Secondary Water Loss of material  Inspection of Internal   VIII.B 1-4 3.4.1.16   E, 8 Steel        (Int)                             Surfaces in MiscellaneousPiping and Ducting Components (B2.1.22)
Pump               LBS       Cast Iron    Plant Indoor Air Loss of material External Surfaces        VIII.H-7   3.4.1.28   B (Gray Cast   (Ext)                             Monitoring Program Iron)                                          (B2.1.20)
Pump               LBS       Cast Iron    Raw Water (Int)  Loss of material Selective Leaching of    VIII. G-24 3.4.1.36   A (Gray Cast                                     Materials (B2.1.17)
Iron)
Pump               LBS       Cast Iron    Raw Water (Int)  Loss of material Inspection of Internal   VIII.G-36  3.4.1.08   E (Gray Cast                                     Surfaces in Iron)                                          Miscellaneous Piping and Ducting Components (B2.1.22)
Strainer           LBS       Cast Iron    Plant Indoor Air Loss of material External Surfaces        VIII.H-7   3.4.1.28   B (Gray Cast   (Ext)                             Monitoring Program Iron)                                          (B2.1.20)
Strainer           LBS       Cast Iron    Steam (Int)      Loss of material Water Chemistry          VIII.B1-8  3.4.1.37   E, 6 (Gray Cast                                     (B2.1.2) and One-Time Iron)                                          Inspection (B2.1.16)
Strainer           LBS       Cast Iron    Steam (Int)      Wall thinning    Flow-Accelerated         VIII.B1-9  3.4.1.29   B (Gray Cast                                     Corrosion (B2.1.6)
_____________    ~    Iron)________
Strainer           LBS       Carbon Steel Secondary Water Loss of material  Inspection of Internal   VIII.B1-11 3.4.1.04   E, 8 (Int)                             Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22) I Section 3.4 PG&E Letter DCL-11-136                                                                            AGING MANAGEMENT OF STEAM AND Page 68 of 98                                                                                              POWER CONVERSION SYSTEM Table 3.4.2-2      Steam and Power Conversion System - Summary of Aging Management Evaluation- Auxiliary Steam System Component     Intended    Material      Environment      Aging Effect       Aging Management         NUREG- Table I Item        Notes Type     Function                                    Requiring               Program           1801 Vol.
Management                                   2 Item Strainer      LBS       Carbon Steel Secondary Water Loss of material      Inspection of Internal    VIII.B 1-11 3.4.1.04     E, 8 (Int)                                Surfaces in Miscellaneous Piping and Ducting Components (B2. 1.22)
Tank          LBS       Carbon Steel Secondary Water Loss of material      Inspection of Internal   VIII, G-41   3.4.1.06     E, 8 (Int)                                Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Trap          LBS       Carbon Steel Steam (Int)       Loss of material   Inspection of Internal    VIII.B 1-8   3.4.1.37     E, 8 Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Valve         LBS       Carbon Steel Secondary Water Loss of material     Inspection of Internal    VIII. B 1-11 3.4.1.04     E, 8 (Int)                                Surfaces in Miscellaneous Piping and Ducting Components (B2.1.22)
Valve                   Ga64,4rem    Plant IndCoo Air  Lose of Materi     Et4ornal ,,urAr,          VIII.,N7     34.1.28      a kE-xoMonitoring                       Program VaI~e LBaSs4-l ~    Raw Wate f-( 4~~  Lose of at eri al
* ep e t o f I t r al      VI. - 6     3 40 S"Gem.....    (92.1.22)
Valve         LBS       Cast Iron    Plant Indoor Air  Loss of material   External Surfaces         VIII.H-      3.4. 1.28Nen BG (Gray Cast   (Ext)                                Monitoring Program        7Nene        e Iron)                                             (B2.1.20)
Section 3.4 PG&E Letter DCL-11-136                                                                                 AGING MANAGEMENT OF STEAM AND Page 69 of 98                                                                                                    POWER CONVERSION SYSTEM Table 3.4.2-2        Steam and Power Conversion System - Summary of Aging Management Evaluation - Auxiliary Steam System Component      Intended     Material      Environment        Aging Effect       Aging Management         NUREG- Table 1 Item     Notes Type        Function                                        Requiring              Program           1801 Vol.
Management                                   2 Item Valve           LBS        Cast Iron     Raw Water (Int)     Loss of material   Selective Leaching of     VIII. G-24 3.4. 1.36  A (Gray Cast                                           Materials (B2. 1.17)
Iron)
Valve           LBS        Cast Iron     Raw Water (Int)     Loss of material   Inspection of Internal    VIII. G-36 3.4. 1.08  E (GrayCast                                            Surfaces in Iron)                                                MiscellaneousPiping and Ducting Components (B2.1.22)
Valve           LBS        Cast Iron     Secondary Water Loss of material       Water Chemistry          VIII.B 1-11 3.4.1.04   A (Gray Cast (Int)                                     (B2.1.2) and One-Time Iron)                                                Inspection (B2.1.16)
Valve           LBS        CopperAlloy Raw Water (Int)       Loss of material   Inspection of Internal   VIII.A-4    3.4.1.32   E, 5
(> 15% Zinc)                                         Surfaces in MiscellaneousPiping and Ducting Components (B2.1.22)
Valve           LBS        Copper Alloy Raw Water (Int)      Loss of material   Selective Leaching of    VIII.A-6    3.4. 1.35  A (Aluminum >                                          Materials(B2. 1.17)
_8%)
Notes for Table 3.4.2-2:
Plant Specific Notes:
8       Components are associatedwith the boric acid evaporatorsubsystem which is abandoned-in-place. Thus, aging of the components will be managed by the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components aging management program.
Section 3.4 PG&E Letter DCL-1 1-136                                                                     AGING MANAGEMENT OF STEAM AND Page 70 of 98                                                                                       POWER CONVERSION SYSTEM Table 3.4.2-4     Steam and Power Conversion System - Summary of Aging ManagementEvaluation - Condensate System Component     Intended    Material      Environment   Aging Effect     Aging Management        NUREG- Table 1 Item    Notes Type      Function                                  Requiring             Program         1801 Vol.
Management                                2 Item Valve         LBS, PB   Cast Iron    Plant IndoorAir Loss of material External Surfaces       VIII.H-7   3.4.1.28   B (Gray Cast   (Ext)                            Monitoring Program Iron)                                         (B2.11.20)
Valve         LBS, PB   Cast Iron    Secondary Water Loss of material Selective Leaching of    VIII.E-23 3.4.1.36   A (Gray Cast   (Int)                            Materials (B2.1.17)
Iron)
Valve         LBS, PB   Cast Iron    Secondary Water Loss of material Water Chemistry         VIII.E-34  3.4.1.04   A (Gray Cast   (Int)                            (B2.1.2) and One-Time Iron)                                         Inspection (B2.11.16)
Valve         PB        Cast Iron    Secondary Water Wall thinning    Flow-Accelerated        VIII.E-35  3.4.1.29   B (Gray Cast   (Int)                            Corrosion (B2.1.6)
Iron)
Valve         LBS       Cast Iron    Steam (Int)     Loss of material Water Chemistry         VIII.A-16  3.4.1.02   A (Gray Cast                                    (B2.1.2) and One-Time Iron)                                         Inspection (B2.1.16)
Valve         PB        Ductile Iron Plant IndoorAir Loss of material External Surfaces        VIII.H-7  3.4.1.28   B (Ext)                            Monitoring Program S(2.1.20)
Valve         PB        Ductile Iron Secondary Water Loss of material Water Chemistry          VIII.E-34 3.4.1.04   A (Int)                            (B2.1.2) and One-Time Inspection (B2.1.16)
Section 3.5 PG&E Letter DCL-11-136                                                                     AGING MANAGEMENT OF CONTAINMENTS, Page 71 of 98                                                                            STRUCTURES AND COMPONENT SUPPORTS Table 3.5.2-1        Containments, Structures, and Component Supports - Summary of Aging Management Evaluation -
Containment Buiildinai Component       Intended   Material      Environment       Aging Effect     Aging Management     NUREG- Table 1 Item    Notes Type        Function                                     Requiring            Program        1801 Vol.
Management                              2 Item Hatch            SH, SS   Stainless    Plant IndoorAir    None             None                  VII.J-15   3.3.1.94  C Steel        (Structural) (Ext)
Structural Steel MB, SS   Carbon Steel Plant Indoor Air   Loss of material Structures Monitoring III.A4-5   3.5.1.25  A (Structural) (Ext)                  Program (B2.1.32)
Section 4 PG&E Letter DCL-1 1-136                                     TIME-LIMITED AGING ANALYSES Page 72 of 98 4.2.1    Neutron Fluence Values Summary Description Loss of fracture toughness is an aging effect caused by the neutron embrittlement aging mechanism that results from prolonged exposure to neutron radiation. This process results in increased tensile strength and hardness of the material with reduced toughness. The rate of neutron exposure is defined as neutron flux, and the cumulative degree of exposure over time is defined as neutron fluence. As neutron embrittlement progresses, the toughness/temperature curve shifts down (lower fracture toughness as indicated by Charpy upper-shelf energy or Cv USE), and the curve shifts to the right (brittle/ductile transition temperature increases). Neutron fluence projections are made in order to estimate the effect on these reactor vessel material properties (Section 4.2.2 and Section 4.2.3), and to determine if additional reactor vessel materials will be exposed to fluence greater than 1 x 1017 n/cm 2 (E>1.0 MeV) as a result of license renewal (extended beltline).
Analysis Unit 1 The last capsule withdrawn and tested from Unit 1 was Capsule V at the end-of-cycle (EOC) 11. At that point, Unit 1 had operated for 14.27 EFPY. This capsule had a lead factor of 2.26 resulting in an exposure equivalent to 32.25 EFPY of operation. The results were documented in WCAP-15958 [Reference 2].
This exposure is less than that expected at EOLE. In PG&E Letter DCL-08-021, PG&E requested a change to the withdrawal date of Unit 1 Capsule B from 20.7 EFPY to 21.9 EFPY in order to capture enough fluence data for EOLE. The change was approved by the NRC in a Safety Evaluation dated September 24, 2008, Diablo Canyon Nuclear Power Plant, Unit No. I - Approval of Proposed Reactor Vessel Material Surveillance Capsule Withdrawal Schedule (TAC No. MD8371) [Reference 2].
During the scheduled Unit 1 Sixteenth Refueling Outage (1R16), refueling personnel were not able to remove the Capsule B access plug on the reactor core barrel flange.
In PG&E Letter DCL-10-141, dated October 25, 2010, PG&E requested a change to the withdrawal date of Unit 1 Capsule B from 21.9 EFPY to 23.2 EFPY. The change was approved by the NRC in a Safety Evaluation dated October 29, 2010, Diablo Canyon Nuclear Power Plant, Unit No. 1 - Approval of Proposed Reactor Vessel Material Surveillance Program Withdrawal Schedule (TAC No. ME4924) [Reference 38].
Unit 2 The last remaining capsule withdrawn and tested from Unit 2 was Capsule V at EOC 9.
At that point, Unit 2 had operated for 11.49 EFPY. This capsule had a lead factor of 4.58 resulting in an exposure equivalent to 52.62 EFPY of operation. This exposure is Section 4 PG&E Letter DCL-1 1-136                                             TIME-LIMITED AGING ANALYSES Page 73 of 98 comparable to the predicted EOLE exposure of 54 EFPY, i.e., within the 20 percent limit specified as the acceptance criteria in Regulatory Guide 1.190. The results were documented in WCAP-1 5423 [Reference 3].
Both Units Based on the guidance specified in Regulatory Guide 1.190, a neutron fluence assessment of the beltline and extended beltline regions was performed Fesults Of he-Capsu!e V analyses provided by Westinghouse in WCAP45958 17299-NP [Reference 240], for Units 1 and 2, through EOLE.Cycles 1-11 and \W"AP 15782 [RefeRc- "e 17],
for Unit 2 CyleS 11-0,, t The peak calculated fast neutron fluence values at the pressure vessel clad/base metal interface inner surface of the DCPP reactor vessels are shown in Table 4.2-1 and Table 4.2-2 for Units 1 and 2, respectively. These fluence data tabulations include fuel cycle specific power distributionsexpoewes-through the end of Cycle 4-1-16 for Units I and 2, (Unit 1) and Gy'le 10 (Un       .- 2) as well as fluence projections at several intervals out to 54 EFPY.
The fluen"e values were projected Us*ig ENO"F8n B/VI cro66 se**ons, and the Capsule V analyses meet the requirements of Regulatory Guide :14100, Calculational and Dos6imetr MethodsI      for De term=.ining PrFeSSUr% V.__~esIsAl eutron Flu4ence.
The calculations account for a Unit 1 core power uprate from 3338 MWt to 3411 MWt at the onset of Cycle 11. Fluence projections beyond the end of Cycle 11-6 on Units 1 and GyG*.1.. GA. .Unit 2 are based on the assumption that the spatial core power distributions are defined by the average of Unit**--Cycles 4-1413-15 for Units 1 and 2.and Unit 2-Cycles 5 10. Power distributions for Cyclero 1 4 on both Units are not incl!uded sinc they are not representative of the ve.' low leakage cre loading patterns now being used*.
For license renewal, Westinghouse performed additional calculations to define which materials in the DCPP pressure vessels, other than beltline materials, are projected to exceed the threshold neutron fluence of lx1017 n/cm 2 at 54 EFPY (extended beltline materials). The results of these calculations are documented in WCAP-17299-NP
[Reference 40], for Units I and 2, through EOLE.LTR REA 09 90, Neutron F'-en-e Emvaluation for the Diable Canyon Units I and 2 ReactOr P-ressure Vessel Extended Bol*t-mo Mate^&#xf7;ril    [ReferenGe 37]. For both units, although the nozzle shell course and the associatednozzle shell to intermediateshell weld are projected to exceed the lx1017 n/cm 2 threshold,the nozzles themselves as well as the nozzle to nozzle shell welds remain below the lx1017 n/cm2 threshold through 54 EFPY. Likewise, the lower shell to lower head weld remains below lxI107 n/cm2 through 54 EFPY for both units.
The extended beltiIne material for both Units :neudes the upper shell plates, associated longitudinal welds, and the upper shell to intermediate Shell GiFcUmnferentia! weld Table 4.2-3 shows the EOLE fluence values for all beltline and extended beltline materials for both Units 1 and 2.
As discussed in Section B2.1.15, both units currently use ex-vessel monitoring dosimetry.
Section 4 PG&E Letter DCL-11-136                                    TIME-LIMITED AGING ANALYSES Page 74 of 98 Disposition: Revision, 10 CFR 54.21(c)(1)(ii); and Aging Management, 10 CFR 54.21(c)(1)(iii)
Revision The fluence projections were revised to quantify expected fluence at the end of the period of extended operation in accordance with 10 CFR 54.21 (c)(1)(ii).
Aging Management Neutron fluence will be monitored and its effects managed for the period of extended operation by the DCPP Reactor Vessel Surveillance program, which is summarized in Section B2.1.15. The validity of these parameters and the analyses that depend upon them will therefore be managed to the end of the period of extended operation in accordance with 10 CFR 54.21 (c)(1)(iii).
Section 4 PG&E Letter DCL-11-136                                      TIME-LIMITED AGING ANALYSES Page 75 of 98 Table 4.2-1 Unit 1 Ma ximum CalculatedFluence (E>1.0 Me V)
Cumulative                   Neutron Fluence (E>1.0 MeV)
Irradiation                             [n/cm 2]
Cycle     Time (EFPY)           00             150             300            450 4416      14.27-21.77     21-- 3.22        .52- 5.08     439 6.31       6.07- 8.63 E+18            E+18           E+18            E+18 Rf-ejeeGte6.0               2.44     4      3.91 E+19       486:+18        6.68- E+!
RfojeGti    _ 2400                            .81 E+1-8 5-.1-.48        7      F2-E+14 9.62-E--48 Projection      32.007.77.26                                9.39-9.05      1261.23 E+18            E+18           E+18            E+19 P4QfGt4Gfl_4070                    E+918E9.61 E+1-8         1.1 .7E+*1-    1.65 E+49 74W 6.85        14.5- 1.07     449- 1.33        -984 1.80 E+18            E+19           E+19            E+19 o7-94-7,68     4-.29-1.19      1,56-1.49      2,06-2.02 E+18            E+19           E+19            E+19 Table 4.2-2 Unit 2 Maximum CalculatedFluence (E>1.0 MeV)
Cumulative                    Neutron Fluence (E>1.0 MeV)
Irradiation                              [n/cm 2]
Cycle     Time (EFPY)           00             150             300            450 232-65.24       4r93 7.91       4v92 7.98     5.-7-9 9.42 E+18            E+18           E+18            E+18 RGOjeGtiea      1600         4.01-F*+8      6.04- F=1       6.03 E+!8      7.11 E+18 PvQJvGP         24700        5 93F-*4       8.89-F*+1       8.90-E*18      4.05 E+-19 7,867.51       4-48 1.13        -4841.14      47391.34 E+18            E+19           E+19            E+19
     -fG*OGtie     40.00        @-7g-E--+-18    14-6-F+9       1!         4      .73E+19 4-4-71.11      1-7-51.67       4-.75 1.69     2706.1.96 E+19            E+19           E+19            E+19 1421.24        4-7W6 1.87      4:-.6 1.89     2,322.19 E+19            E+19           E+19            E+19 Section 4 PG&E Letter DCL-11-136                                      TIME-LIMITED AGING ANALYSES Page 76 of 98 Table 4.2-3 Units I and 2 CalculatedFEuenc e (E>I.0 MeV) Values at EOLE (54 EFPY)
Unit 1                                         Unit 2 Material                  Fluence             Material           Fluence [n/cM2]
[n/cm 2 ]
Upper Shell Plate(a)                           Upper Shell Plate(a)
B4105-1                     2-.N3.41 E+17      B5453-1                 5-2-06.77 E+117 B4105-2                     2-63.41 E+17       B5453-3                 5-.206.77 E+17 B4105-3                     2-863.41 E+17      B5011-1R                &2-06.77 E+17 Intermediate Shell Plate                       Intermediate Shell Plate B4106-1                     2-062.02 E+19      B5454-1                 2-22.25 E+1 9 B4106-2                     2,062.02 E+ 19     B5454-2                 24212.25 E+ 19 B4106-3                     2-062.02 E+19      B5454-3                 2-,22.25 E+1 9 Lower Shell Plate                              Lower Shell Plate B4107-1                     2-042.01 E+19      B5455-1                 2-402.22 E+1 9 B4107-2                     2,042.01 E+19      B5455-2                 2-302.22 E+1 9 B4107-3                     2,042.01 E+19      B5455-3                 24302.22 E+1 9 Upper Shell Long. Welds(a)                     Upper Shell Long. Welds(a) 1-442 A                     2462.45 E+17       1-201 A                   4-06.33 E+17 1-442 B                     4-.241.49 E+17     1-201 B                 4.-26.29 E+17 1-442 C                     2-573.06 E+17      1-201 C                 3-Q35.14 E+17 Upper Shell to Intermed. Shell Weld(a)         Upper Shell to Intermed. Shell Weld(a) 8-442                       2-863.41 E+17      8-201                   &.2-06.77 E+17 Intermed. Shell Long. Welds                    Intermed. Shell Long. Welds 2-442 A                     4-4561.49 E+19     2-201 A                   4,321.24 E+19 2-442 B                     4-61.49 E+19       2-201 B                   4-,51.53 E+19 2-442 C                     746 7.68 E+18      2-201 C                   4461.30 E+19 Intermed. Shell to Lower Shell Weld            Intermed. Shell to Lower Shell Weld 9-442                       2,042.01 E+19      9-201                     2-402.22 E+19 Section 4 PG&E Letter DCL-11-136                                  TIME-LIMITED AGING ANALYSES Page 77 of 98 Table 4.2-3 Units I and 2 CalculatedFluence (E>1.0 Me V) Values at EOLE (54 EFPY)
Unit I                                    Unit 2 Material             Fluence              Material          Fluence [n/cm 2]
[n/cm2]
Lower Shell Long. Welds                    Lower Shell Long, Welds 3-442 A                 :21.19 E+19      3-201 A                 4-,31.28 E+19 3-442 B                 4-281.19 E+19       3-201 B                 4,341.23 E+19 3-442 C                 2-,042.01 E+19      3-201 C                 4-.-1.51 E+19 Section 4 PG&E Letter DCL-1 1-136                                     TIME-LIMITED AGING ANALYSES Page 78 of 98 4.2.2       Pressurized Thermal Shock Summary Description 10 CFR 50.61(b)(1) provides requirements for protection against pressurized thermal shock (PTS) events for pressurized water reactors. Licensees are required to perform an updated assessment of the projected values of reference temperature whenever a significant change occurs in projected values of the adjusted reference temperature for pressurized thermal shock (RTPTS), or upon request for a change in the expiration date for the operation of the facility.
Irradiation by high energy neutrons raises the value of RTNDT for the reactor vessel.
The initial RTNDT is determined through testing of unirradiated material specimens. The shift in reference temperature, ARTNDT, is the difference in the 30 ft-lb index temperatures from the average Charpy curves measured before and after irradiation.
Regulatory Guide 1.99 defines the calculation methods for ARTNDT (and end-of-life Cv USE). RTPTS is defined as the RTNDT value evaluated at the end of life fluence at the clad/base metal interface for each of the vessel beltline materials. 10 CFR 50.61(c) provides two methods for determining RTPTS. These methods are also described as Positions 1 and 2 in Regulatory Guide 1.99. Position 1 applies for material that does not have credible surveillance data available and Position 2 is used for material that does have two or more credible surveillance data sets available. The criteria for credible data are also provided in Regulatory'Guide 1.99. The adjusted reference temperatures are calculated for both Positions 1 and 2 by following the guidance in Regulatory Guide 1.99 (Sections 1.1 and 2.1, respectively), using the copper and nickel content of DCPP reactor vessel materials, and the EOLE fluence projections.
10 CFR 50.61(b)(2) establishes screening criteria for RTPTs as 270'F for plates, forgings, and axial welds and 300&deg;F for circumferential welds. If the RTPTs does not exceed the PTS screening criteria, then only the reactor pressure vessel is relied on to demonstrate compliance with 10 CFR 50.61, the PTS rule.
Analysis PG&E's original response to the issuance of the PTS rule, 10 CFR 50.61, indicated that the projected RTPTS for both units do not exceed the PTS screening criteria, 270'F, and 300'F, based on 32 EFPY.
Since Cycle 1, several actions taken by PG&E have resulted in changes to input parameters used to calculate RTPTS. Fluence projections for both units were reduced following Cycle 1 as a result of fuel management changes to lower-leakage core designs. Also, copper and nickel content for the Unit 1 beltline longitudinal welds have been updated to reflect chemical analyses performed for the evaluation of surveillance Section 4 PG&E Letter DCL-11-136                                                                          TIME-LIMITED AGING ANALYSES Page 79 of 98 capsules. 10 CFR 50.61 was revised in June 1991, which changed the method used to calculate RTPTS.
The most recent coupon examination results for both units show that the increase in RTNDT in plate and weld materials are bounded by that predicted by Regulatory Guide 1.99 Revision 2 for Units 1 and 2. The results demonstrate that the DCPP reactor vessel material ages consistent with Regulatory Guide 1.99 predictions, and provide a conservative means to satisfy the requirement of 10 CFR 50.61; thus providing assurance of the reactor vessel integrity.
Unit I The data from the most recently withdrawn surveillance capsule, Capsule V, were not deemed credible [Reference 2,- Appendix D]. Using Regulatory Guide 1.99 PositieFi4A.
metheds, RTPTS values were generated for beltline and extended beltline region materials of the Unit 1 reactor vessel for EOLE fluence values. The RTPTS values for the Unit 1 materials are provided in Table 4.2-4. The projected RTPTS values for EOLE dk4-Pet-meet the 10 CFR 50.61 screening criteria in all cases. The calculation [Reference 1-439] indicates the limiting weld material for Unit 1 is lower shell longitudinal (axial) weld 3-442C with a projected EOLE RTPTS value of 289"43&deg;F, using Position 2.1. LeweF-ru.hpfl   Inn         I   ~  V yq *fllfln&#xfd; lc    2~ 44:2       ii          fk*    OT I   -f     gLIn~ ~III       ^r~p; iinfN           rego-i   I   1 43 E vPY.          All other m.ateria.li-, m.eet the 10 C-Fn           R 5-0.6-1 creenn' criteria. The limiting plate material on Unit 1 is the lower shell plate B4107-1 with a projected EOLE RTPTS value of 156.2-F, using Position 1.1 [Reference 39].
The Unit 1 reactor Vessel fluencce will continuc to be moneitorcd in accordanGe wt 10 C.FR 50.61 as part of the DCPP21 Reactor Versel Sur.'eillance program (132.1.15) to ensure that the reactor Vessel mnaterial does Rot violate the PTS criteria.
In 2000, the NRC approved the Fina! Rule 10 CFR 50.61 a, Afternate FrFactUr Toughness Roguiromante for-Pr-etection Against Pr-essurzed Thermal ShGck Eivents toughnes
    *l~ IE   ~I rqIremeants based on V%*Vl    1**    V~       WI    vV~ I i    ~ updated analysis mnethods for protection against PTS tI  1Ili l     i-    * -  * -     -  -! I             I--- II~
                                                                                                                        -II       1I events for PWVR pressure vessels. it is anticipated that DCPP Unit 1 will m~eet these revised requirements_ through EOLE.
PG&FE will impIWment the revised PTS (10 CER 50.61 a) rule at least three years prior to exc~eeding the PTS screening criFterion Of 10 CFR 50.61. in the event that the poiin of 10Q C-F=R 50.61 a cannot be mnet, PG&E= wil! implement alternate4)options, such~ _As flux reduction, as provided in; 10 CFR 50.61.
The extended beltline materials were also evaluated. The results (Table 4.2-4) confirm the materials will not become limiting.

Enclosure 2                                                                         Section 4 PG&E Letter DCL-1 1-136                                      TIME-LIMITED AGING ANALYSES Page 80 of 98 Unit 2 The data from the most recently withdrawn surveillance capsule, Capsule V, was deemed credible [Reference 3, Appendix D]. RTPTS values were generated for beltline and extended beltline region materials of the Unit 2 reactor vessel for fluence values at EOLE. The RTPTS values for the Unit 2 materials are provided in Table 4.2-5. The projected RTPTS values for EOLE meet the 10 CFR 50.61 screening criteria. The I calculation [Reference 4439] indicates that the limiting weld material for Unit 2 is intermediate shell longitudinal (axial) weld 2-201 B with a projected EOLE RTPTS value of 244.2207'F using Regulatory Guide 1.99 Position 4-2.1. The limiting plate material on Unit 2 is the intermediate shell plate B5454-2 with a projected EOLE RTPTS value of I 223-.20 F.
The extended beltline materials were also evaluated. The results (Table 4.2-5) confirm the materials will not become limiting.
Disposition: Revision, 10 CFR 54.21(c)(1)(ii); and Aging Manag.m. nt, 10 CFR 54.21 (G)(1)(iiii)
Unit I - Aging MapnagemeniRevision The RTpTs was projected to the end of the period of extended operation in accordance with 10 CFR 54.21(c)(1)(ii). RTpTs remains within acceptable values for the period of extended operation.The Unit 1 reactor vessel fluence will continue to be monitored as pa~t of the DCPP Reactor Vessel Surveillance program (B2. 1.15) and its effectS will be adequately managed to the end of the period of extended operation in a*cordance with 10 CFR 54.21 (G)(4)(4ii.
Unit 2 - Revision The RTPTS was projected to the end of the period of extended operation in accordance with 10 CFR 54.21 (c)(1)(ii). RTPTs remains within acceptable values for the period of extended operation.
Section 4 PG&E Letter DCL-1 1-136                                                                                                            TIME-LIMITED AGING ANALYSES Page 81 of 98 TRhk~ 4 2-4 flCPP unit I ~                         PT,,,-~, ~f !54 FFP ~')
Material Description             SSeurG          Chemical                                                                                                 Extend eR.G         Composition      Chemistry   Initial      EOLE                 ART                            Screening      ed 0
1.2            u        N        Fa   r               Fluence      Fluence   RTNDT     Margin     RTpTs     Criteria      ed 1.99,                          Factors    RTN-T      1019 nlcm'     Factor                -F         F          F       Beltline Location        Heat No.      Type    Positl       Wt%       Wt%                           E>1.0 MeV                   -F                                      Region on Upper Shell Plate      C2624       A 533B   1.1Ref       0.120     0.56       82.2       28      0028960.03    0.21360. 4-7,619. 3     39, 8"387       <270        Yes B4105-1                                --44                                              1      41          2365        4         2             1 Upper Shell Plate     C2624-2      A533B     .lRef      0.120      0.57       82.4        9      0-2860.03     024360. 47-619. 3"39. 6"68        <270        Yes B4105-2         C642         A53        .-144            1                                      41          2365        5         2 Upper Shell Plate      C2608-      A 533B   11Ref       0                                        0.02980.03    0,2:3160. 24-023,    2,091. 4-,978     <270        Yes B4105-3            2B        A.-430,140                      0.56       98.2       14           41          2365        2         2 Intermediate Shell                          1,1PRef                                                      ,1. 45332      -t02-1 Plate B4106-1        2884-1     A 533B    -4            125     0.53       85.3      -10       282.02          1917     01.7        34      1264       <270         No Intermediate Shell    C2854-2      A 533B   1.lRef       0.12      0.50        81        -3       2-%2.02      4 1961. 09696,          34     42791 Plate B4106-2                                                                                                                                          5270         No
                                              -44                                              1                  1917        5                 28 Intermediate Shell    C2793-1      A 533B   1.1ef       0.086     0.476       55.2       30       2-062.02      i.49681.   "'465. 48.1     1444.-       270        No Plate B4106-3                              -.44             1                                                  1917        8
   -- Using non-credible        C2793-1      A 533B     2.1        0.086    0.476       37.4       30          2.02        1.1917    44.6       48.1      123       !5270        No surveillance data Lower Shell Plate     C3121-1      A533B    1.1Ref       0.13      0.56       89.8       15       2-042,01     41.9431. 407*21        34      1562       <270         No B4107-1 Loer Shell Plate             1.--14      1,lRe4                                                                1904 4t-40431. 06.9 98.297.       3 C3131-2      A 533B                0.12      0.56       82.2       20       2,042,01        19 B4107-2                                 -.--
44                                                                1904 4   899         34      1524       *5270        No Lower Shell Plate     03131-1      A 533B   1.41         0.12      0.52       81.4      -22       2,042.01               97496.
                                                                                                                           -40421. 34      1094       !5270        No B4107-3         C3131-4      A4                    0           .24                                          1904       9 Upper Shell Long.      27204/       Linde   1.1,o4      0.190     0.970      215.7      -20      0024-60.02    0-A4040.         42 3842.      &-64        S270        Yes Weld 1-442 A        12008        1092     -44                                                      45          1948                  0 Upper Shell Long. 27204/        Linde   1.Ref       0.190     0.970                          001270.01     0470. 2-7430,    27-830. 3"42        !270        Yes Weld 1-442 B        12008        1092     ,-44                                                     49          1428       8          8 Upper Shell Long. 27204 /       Linde   1.e         0190      0.970      215.7      -20      002570.03     00040. 4 47.             7.
Weld 1-442 C        12008        1092     -.1-4             1                                      06          2222       9          9 Upper Shell to Intermediate Shell     13253        Linde   1.1Re"         2      030                            0-2860,03     021360. 42,46.        -257   40448         300       Yes Circumferential                   1092     -44         05         .7       197.5      -56           41          2365        7         8 Weld 8-442      1                                                    1           1         1             1                                        1 Section 4 PG&E Letter DCL-11-136                                                                                                       TIME-LIMITED AGING ANALYSES Page 82 of 98 Table 4.2-4 DCPPUnit I Vessel RTPTs at 54 EFPY(")
Material Description          eR.G eR.G         Chemical Composition      Ceit Chemistry Initial                                                                        Exted ARET                          Screening    Extend Rev.299       .9,Fcos        FactorsF RNT RTNDTOF      Fluence 1019 nlcm2 Fluence Factor       RTNVOT F     Margin F      RTp~s OF      Crtra OF         ed Beltline Location        Heat No. Type     Posltl     Wt%      Wt%                         E>1.0 MeV                    OF                                      Region on Intermediate Shell               Linde   11Ref                                                         4-12291,     2M 7                264 2 Long. Welds 2-      27204     1092       44      0.203    1.018      226.8     -56       4     1.49   1104         51.8     65.5        61        5270        No 442A, B                         IIII_
  -. Using credible     27204    Linde      2.1     0.203     1.018     214.1     -56          1.49     1.1104       237.7     44.0       226        <270        No surveillancedata                1092 Intermediate Long. WeldShell   27204     Linde   1 1Ref                                                          9259*e0     -10.02-   655*4-*270                        No 2-442C                    1092      -44      0.203    1.018      226.8    -56      0,7W.768       9259         10.0     655         20!-20
 -. Using credible      27204               2.1     0.203    1.018      214.1     -56         0.768     0.9259       198.2     44.0       186        <270        No surveillance data               1092             _                 I                   III Lower Shell Long.      27204     Linde   1.1Ref     0.203    1.018      226.8    -56        4--1.19    446W71.      24242      65.5     2-.-92      <270         No Welds 3-442A, B                 1092     -44                                                            0485         37.8                47
 -- Using credible               Linde      2.1     0.203    1.018      214.1     -56          1.19     1.0485       224.5     44.0       213        <-270       No surveillance data     27204     1092 Lower Shell Long.                Linde   1.lRef                                                        41-4941. 270-92              2-02 Weld 3-442C        2    4    1092     4         0.203    1.018      226.8    -56        2,042.01     1904         7050                80
 -'Using credible                Linde      2.1     0,203    1.018      214.1     -56          2,01     1.1904       254.9     44.0       243        -270        No surveillance data      27204    1092 Intermediate to Lower Shell                 Linde   1.1PRef                                                               140-LwrSel       21935     Lid      .1Rf      0.183    0.704      172.2    -56        2-"42.01   1 49421. 20fi7230N 6.5       25 Circumferential                1092      .-4-4                                                         1904         05.0     65.5     215,2       -300         No Weld 9-442 Notes:
(i) Reference 39, WCAP-1 7315-NP

Enclosure 2                                                                                                                                                     Section 4 PG&E Letter DCL-11-136                                                                                                           TIME-LIMITED AGING ANALYSES Page 83 of 98 Table 4.2-5 DCPPUnit 2 Vessel RTPTs at 54 EFPY(')
R.G         Chemical,                                                                                              Etn Material Description                1.99,        Ccreening Composition    Chemistry                                      ARG                                        Extend Initial     Fluence 2    Fuenc     RTT      Margin 0          RTPT  Screening Rev.2                      Factors     RTNDT      1019n/cm      Factor             Mg  F                Criteria      ed Ni    OF          OF      E >1.0MeV       Factor     OF                             OF      BRegion Location          Heat       Type       Position     Cu No.       Tye          o.Fae    Wt%         Wt%                                                                                            Rgo Upper Shell       C5162-1     A 533B       1.1Ref-   0.110      0.600    74          28      045N0.06      04-W0     2-2-425   2-22425 '72-2279      <270        Yes Plate B5453-1                                  4-4                                                 77          3434       4         4 Upper Shell       05162-2     A 533B       1.ef      0.110      0.600    74           5      0.06200.06    0.2900. 2-2-425. 404642.      67,773   <270        Yes Plate B5453-3                                   -44                                                77          3434       4         4 Upper Shell       C417el-,                                                                   00107200.06   02099-0. 2-425. 40742.      &sect;348       5270       Yes Plate B5011-1R       4377-1     A 533           44     0110       0.650   748           077                     3434       7         6 Intermediate                                     ef.                                                       1 22741. 42401                 *00 Shell Plate       5161-1     A 533B                 0.140      0.650 086101.3       52       2-422.25        2196     23.5                    10 B5454-1 Using credible    C5161-1     A 533B         2.1     0.140      0.650   105.7        52         2.25         1.2196   128.9       17          198    <270         No surveillance data Intermediate                                1.1                                                              12                              2222 Shell Plate      C5168-2     A 533B                  0.14       0.59   99.6         67       2,322.25       219         21       34          222    <270         No B5454-2                                     44                                                              2196     21.5                   22 Intermediate                                1414ef-                                                         42741. 43661 Shell Plate      C5161-2     A533B           4-4     0.15       0.62   110.5        33       22,2.225        2196     34.8       34         202-6   *270         No B5454-3                    ___2196_34.8 Lower Shell       05175-1     A 5338           R1    0.14        0.56   98.2        -15       2,302.22     122f521. 420.31       34        -13*1    <270         No Plate B5455-1                                  4-4                                                             2161      19.4                   38 Lower Shell       C5175-2     A 533B        16Re4-   0.14        0.56   98.2          0       2,302.22     4,2621                 34                 <270         No Plate B5455-2                                  44              1                             1                 2161      19.4                   53 Lower Shell                               1CARef-      0.1       0.62   6572         15       2,W2.22                             34         128-9   *270         No Plate B5455-3       05176-1     A 533B                  062                                                    2161        3 Upper Shell       21935/       Linde      1. 1Re,00                      15                  0       0.06 0.29690. 62470       5 Long. Weld         12008       1092          44      0.220      0.870   211.2       -50          33          3317        1       5270                            Yes 1-201 A                                                                                        33I33t7__
I-.Using    credible Usincedata        21935 1 /      Linde 1092          2.1     0.220      0.870   204.6       -50 surveillancedata       120081      1092                                                            0.0633       0.3317     67.9       28          46     5270        Yes Upper Shell       21935/       Linde      1.1Ref4-                                            04820.06     0.287-00. 6&sect;069.
Long. Weld         12008       1092                  0.220      0.870  211.2        -50          2956.0                                    6"76      !270        Yes 1-201 B          12008                                     I9                 I_         I       9         3306_8

Enclosure 2                                                                                                                                                Section 4 PG&E Letter DCL-1 1-136                                                                                                        TIME-LIMITED AGING ANALYSES Page 84 of 98 Table 4.2-5 DCPPUnit 2 Vessel                R.G RTpTs at 54 EFPY(i)
Chemical Material Description              1.99,       Composition        Chemistry  Initial   Fluence              AgG                       Screening Screening    Extend eRTd Rev.2                             Factors  RTNDT    10W9  nlcm2 Fluence    RTNDT   Margin    RTpTs   Criteria      ed HeNo.             Position       Cu          Ni           &deg;F     OF    E >1.0MeV      Factor       FF              OF       OF       Beltline Location           Heat      Type     Saa          C            t                                                     F                                 Region
   -. Using credible     21935 /     Linde suveillance data       12008       1092       2.1      0.220      0.870        204.6    -50       0.0629      0.3306    67,6     28        46     <270         Yes Upper Shell        21935/      Linde    1.IRef-                                             0-0300.05    0-.2-40. 54462.
Long. Weld          12008      1092        4-       0.220      0.870        211.2      5014                 2971        7   64456     849,69   *5270       Yes 1-201 C
   -~Using credible      219351/     Linde       21       020        080          246       -0       001           .91     6.         8       3       57           e surveillance data       12008      1092 Upper Shell to Intermediate       21935       Linde    1.1Re     .17                                       0 036200.06  02900. 55.--4265.        sa469     <300        Yes Shell          21935       1092        4-4      0.22077                                      14         3434        1      5               5300        Y
   --,Using  credible Circumferential      21935 /     Linde surveillance Weld_8-201data      12008      1092    ____
Intermediate       21935/I     Linde    1 1~ef-                                                          4-07741. 227-52            23222     *70N Shell Long.         12008      1092        44        0.22       0.87        211.2    -50     14-21.24       0599     23.9     56       30        20N Weld 2-201 A Usillacedata        1208     1             2.1       0.22       0.87        204.6    -50        1.24       1.0599   216.      28       195     !270         NO Intermediate        21935/      Linde    1.lRe-                                                            1-284I1. 225922            24462      -270        No Shell Long.        12008       1092        4-4       0.22      0.87         211.2    -50     4491.53        1176     3610     56       42 Weld 2-201 B                                                                                                                        I                    I
  -. ULsing credible
  -MUsing    credible    21935 219351//    Linde Linde       21        02          .7         246      -0         15          A7        2.        8      27      :20N surveillance data       12008 Isurveillance    data     12008 110921 1092       2.          .2        08            0.      5          .3          .16    287       2         0       20N Intermediate        21935/      Linde    1.                                                               448341.
1         22842             22442 Shell Long.                                          0219322 0.87           211.2    -50     4-61.30        073          2    56       33      <270         No Weld 2-201A         12008       1092         44                                                              0730     26.6              33
    -Usincedata           1208     1            2.1        0.22       0.87        204.6    -50        1.30       1.0730   219.5     28       198     <270         No Lower Shell                    Linde    1. lRef-               01.                                                 42        6       4454      *270         No Long. Weld 3-       33A277        124        4-4      0.258      0.16          26.3    -56      1.         0687     35.0     56       44 201 A                                            ______ I____         __________
I________
  -Using     credible   33A277       Linde      2.1       0.258      0.165        115.9    -56        1.28       1.0687   123.9    44.0      112     *270         No surveillance data     12008         124  1           1__11_
Section 4 PG&E Letter DCL-11-136                                                                                        TIME-LIMITED AGING ANALYSES Page 85 of 98 Table 4.2-5 DCPP Unit 2 Vessel RTPTs at 54 EFPY')
R.G       Chemical Material Description          1.99,    Composition  Chemistry Initial  Fluence              ART-pT                   Screening    Extend Rev.2                  Factors  RTIDT   10'9n/cm2  Fluence     RTNDT  Margin    RTpTS   Criteria      ed HeatPosition                Cu      Ni      F        F    E >1.0MeV                                     F            Beltline No.        Type   Ar-      Wt%     Wt%                                                                                Region Lower Shell Long. Weld 3-     33A277       L4 124                                                        0577       33.6    65.5     43 201 B
-'Using credible     33A277       Linde   2.1    0.258   0.165   115.9    -56        123     1.0577     122.6    44.0     111     <270         No surveillance data                  124 Lower Shell                   Linde 1 lRef,                                             1-12461,   44201            44441 Long. Weld 3-      33A277        124    4-4    0.258   0.165   126.3    -56     4-1:71.51   1141       40.7    65.5     50      <270         No 201CC_11                                                                                           0      65
-- Using credible                 Linde   2.1    0.258   0.165   115.9    -56        1.51    1.1141     129.1    44.0     117     s270         No surveillance data    33A277        124 Intermediate to Lower Shell       10120       Linde 1.12Ref- 0.046   0.082    34      -56     2 ,302.22    .22521. 44441. 6354 53. 39 -4    <300         No Circumferential                  0091    4                                                2161        3        5 Weld 9-201 Notes:
(i) Reference 39, WCAP-17315-NP Section 4 PG&E Letter DCL-1 1-136                                     TIME-LIMITED AGING ANALYSES Page 86 of 98 4.2.3 Charpy Upper-Shelf Energy Summary Description Per Regulatory Guide 1.99, Radiation Embrittlement of Reactor Vessel Materials, the Charpy upper-shelf energy (Cv USE) is assumed to decrease as a function of fluence and copper content. Figure 2 of the guide determines this magnitude of decrease when surveillance data is not used (Position 1.2). In addition, if surveillance data is to be used (Position 2.2), the decrease in upper shelf energy may be obtained by plotting the plant surveillance data on Figure 2 of the guide and fitting the data with a line drawn parallel to the existing lines as the upper bound of all the data. This line can then be used in preference to the existing line. The Cv USE can be predicted using the corresponding 1/4T fluence projection, the copper content of the beltline materials, and the results of the capsules tested to date using Figure 2 of the guide.
10 CFR 50, Appendix G requires that the reactor vessel beltline materials must have a Cv USE of no less than 75 ft-lb initially, and must maintain Cv USE throughout the life of the vessel of no less than 50 ft-lb unless it is demonstrated in a manner approved by the Director, Office of Nuclear Reactor Regulation, that lower values of Cv USE will provide margins of safety against fracture equivalent to those required by ASME Section Xl, Appendix G (10 CFR 50, Appendix G, Section IV.A.1 .a).
Analysis The most recent coupon examination results for both units show that the decline in Cv USE in plate and weld materials are bounded by that originally predicted by Regulatory Guide 1.99, Revision 2. Thus the results demonstrate that the DCPP reactor vessel material ages consistently with Regulatory Guide 1.99 predictions and provides a conservative means to satisfy the requirements of 10 CFR 50, Appendix G. This provides assurance of the reactor vessel integrity.
Unit 1 In accordance with Regulatory Guide 1.99, the Cv USE data from Unit 1 surveillance Capsule V were determined not to be credible and were, therefore, not included in the EOLE Cv USE projections.
The Cv USE values were projected to 54 EFPY of operation using Regulatory Guide 1.99 Position 1.2. The EOLE Cv USE values for the Unit 1 beltline and extended beltline materials are provided in Table 42-6. The limiting value was 58-.58.2 ft-lbf for lower shell longitudinal weld 3-442C.
Section 4 PG&E Letter DCL-1 1-136                                 TIME-LIMITED AGING ANALYSES Page 87 of 98 The extended beltline materials were also evaluated to confirm they will not decrease below the 10 CFR 50, Appendix G criterion of 50 ft-lbf.
Unit 2 In accordance with Regulatory Guide 1.99, the Cv USE data from Unit 2 surveillance Capsule V were deemed credible for intermediate shell plate B5454-1.
The Cv USE values were projected to 54 EFPY of operation using Regulatory Guide 1.99 Position 1.2. The EOLE Cv USE values for the Unit 2 beltline and extended beltline materials are provided in Table 4.2-7. The limiting value was 53.7 ft-lbf for lower shell longitudinal weld 3-201 C.
The extended beltline materials were also evaluated to confirm they will not decrease below the 10 CFR 50, Appendix G criterion of 50 ft-lbf.
Disposition: Revision, 10 CFR 54.21 (c)(1)(ii)
The Cv USE values were re-evaluated with projections to the end of the period of extended operation in accordance with 10 CFR 54.21(c)(1)(ii). The re-evaluations demonstrated that the Cv USE in the limiting material of each unit will remain above the 10 CFR 50 Appendix G acceptance criterion of 50 ft-lbf for the period of extended operation.

Enclosure 2                                                                                                                      Section 4 PG&E Letter DCL-1 1-136                                                                              TIME-LIMITED AGING ANALYSES Page 88 of 98 Table 4.2-6 DCPPUnit 1 Reactor Vessel Material Cv USE at EOLE(')
EOOLC1/ US Material Description                        Unirradiated   EOL 1/4T                    Projected    EOL C, USE Reactor Vessel Beltline Region                 Heat               Cu wt%     Cv USE       Fluence 1019   n/cm2 % Drop USEin Ci,      CC,    S USE   Acceptance Criterion Location                                     Number     Type             ft-lbf    (E>A MeV)                        ft-lbf       ft-lbf Intermediate Shell Plate B4106-1             C2884-1   A 533B   0.125     116          1.204       2-223        _0089.3           ?50 Intermediate Shell Plate B4106-2             C2854-2   A 533B    0.12     114          1.204         22            9"808.9        2>50 Intermediate Shell Plate B4106-3             C2793-1   A 533B   0.086      77          1.204       4-120           92461.6        >50
-'Using surveillance data                    C2793-1   A 533B   0.086      77          1.204        7.2(')             71.5       >50 Lower Shell Plate B4107-1                    C3121-1   A 533B    0.13     110          1.198         23            84"84.7        >50 Lower Shell Plate B4107-2                    C3131-2   A 533B    0.12     103          1.198         22            8".80.3        ?50 Lower Shell Plate B4107-3                    C3131-1   A 533B    0.12     116          1.198         22           4",690.5        &#x17d;50 Intermediate Shell Long. Welds 2-442A, B      27204  Linde 1092 0.203      91      0 ,J00,888        34           6"-60.1         >50
-. Using surveillance data                    27204  Linde 1092 0.203      91          0.888        331"              61.0        ;50 Intermediate Shell Long. Weld 2-442C          27204  Linde 1092 0.203      91      0-4630458         29           64-"646         ?50
-. Using surveillance data                    27204  Linde 1092 0.203      91          0.458       28.51"'            65,1        a50 Lower Shell Long. Welds 3-442A, B             27204  Linde 1092 0.203      91      0Q7450,709        32           64461.9         ?50
-. Using surveillance data                    27204  Linde 1092 0.203      91          0.709        31('"             62,8        >50 Lower Shell Long. Weld 3-442C                 27204  Linde 1092 0.203      91          1.198         36       1      &458.2       >50
-- Using surveillance data                    27204  Linde 1092 0,203      91          1.198        351"             59.2   1      50

Enclosure 2                                                                                                                                      Section 4 PG&E Letter DCL-11-136                                                                                                    TIME-LIMITED AGING ANALYSES Page 89 of 98 Table 4.2-6 DCPPUnit 1 Reactor Vessel Material Cv USE at EOLEJi)                                                                             EOLLC'/US Material Description                                           Unirradiated     EOL %/DT                Projected  EOLcC, USE
_______________________Cu                                                    UE        Fluence   % Drop in Cv,~        S  Acceptance Reactor Vessel Beltline Region                    Heat                        wt%           Cv USE       1019 n/cm 2     USE        C, USE     Criterion Location                                       Number           Type                          ft-lbf     (E>1 MeV)                    ft-lbf     ft-lbf Intermediate Shell to Lower Shell                21935       Linde 1092       0.183            109          1.198         34        7-471.9       a50 Circumferential Weld 9-442 Upper Shell Plate B4105-1                        C2624         A 533B         0.120             80        Q-0170.020      8.6       7-3.673.1     >50 Upper Shell Plate B4105-2                       C2624-2        A 533B         0.120             74       0 04-70.020     8.6         &9467.6      a50 Upper Shell Plate B4105-3                      C2608-2B        A 533B         0.140             81       004-70.020      9.4        74973.4       >50 Upper Shell Long. Weld 1-442A                 27204/12008    Linde 1092       0.190             86       0.fA-0.015     4-274       T4474.0       250 Upper Shell Long. Weld 1-442B                 27204/12008    Linde 1092       0.190             86       0-00-70.009    4414        -7674.0       ?50 Upper Shell Long. Weld 1-442C                 27204/12008    Linde 1092       0.190            86      1 Q-0460.018     414 17-674.0           >50 Upper Shell to Intermediate Shell Weld 8-        13253       Linde 1092       0.250            111       0-4-7-0.020 442                                                                                                                     41-17       44492.1       a50 Notes:
(i) Per the guidance of 10 CFR 50.61 and Position 1.2 unless otherwise noted.
(ii)PercentageUSE decrease is based on Position 2.2 of Regulatory Guide 1.99, Revision 2.
Section 4 PG&E Letter DCL-1 1-136                                                                                 TIME-LIMITED AGING ANALYSES Page 90 of 98 Table 4.2-7 DCPP Unit 2 Reactor Vessel Material C,, UISP at P01 L".i EOL 1/4T                  Projected  EOL C, USE Material Description                   Cu   Unirradiated   Fluence   % Drop in Cv               Acceptance Reactor Vessel Beltline Region               Heat               wt%     Cv USE     1019 n/cm 2     USE          Cv USE     Criterion Location                   Number       Type             ft-lbf    (E>1 MeV)                      ft-lbf     ft-lbf Intermediate Shell Plate B5454-1            C5161-1     A 533B    0.14      91       4451.341        25          68"68.3       >50
--Using surveillancedata                    C5161-1     A 533B    O 14      91          1.341       22"'1           71.0       >50 Intermediate Shell Plate B5454-2            C5168-2     A 533B    0.14      99       4451.341        25          7*4-674.3     &#x17d;50 Intermediate Shell Plate B5454-3            C5161-2     A 533B    0.15      90       41-.31.341      26          6"166.6       >50 Lower Shell Plate B5455-1                   C5175-1     A 533B    0.14     112       4-*341.323      25           "4=484.0     >50 Lower Shell Plate B5455-2                   C5175-2     A 533B    0.14     122       4-441,323       25          92-091.5      >50 Lower Shell Plate B5455-3                   C5176-1     A 533B    0.1      100       4-341.323     2021          7-"79.0       >50 Intermediate Shell Long. Weld 2-          21935/12008 Linde 1092  0.22     118      0-_7680.739    3834          7-3477.9      &#x17d;50
-- using surveillance data                21935/12008 Linde 1092  0.22     118         0.739       37.5""           73.8       &#x17d;50 Intermediate Shell Long. Weld 2-          21935/12008 Linde 1092  0.22     118      0,9250.912     3036          7-1-675.5     >50 U--,sing surveillance data             21935/12008 Linde 1092  0.22     118          0.912      39.5""           71.4       250 Intermediate Shell Long. Weld 2-         21935/12008  Linde 1092 0.22      118      0-.7-80.775 201 C                                                                                              3835          7-4376.7      &#x17d;50
-- Using surveillance data                21935/12008 Linde 1092  0.22     118         0.775        3e'             73.2       >50 Lower Shell Long. Weld 3-201A               33A277    Linde 124  0.258      88      0-7-740,763      38           6"054.6      >50 Lower Shell Long. Weld 3-201B               33A277    Linde 124  0.258      88      0.7-620.733    3738          56.454.6      &#x17d;50 Lower Shell Long. Weld 3-201C               33A277    Linde 124  0.258      88      0Q9430900        39            53.7        &#x17d;50 Intermediate Shell to Lower Shell            10120    Linde 0091 0.046     125       4-441.323     2021         400498.8       >50 Circumferential Weld 9-201 Section 4 PG&E Letter DCL-11-136                                                                                                   TIME-LIMITED AGING ANALYSES Page 91 of 98 Table 4.2-7 DCPPUnit 2 Reactor Vessel Material Cv USE at EOLE(_)
EOL 1/4T                   Projected EOL C, USE Material Description                                  Cu        Unirradiated  Fluence   % Drop in Cv    Cv USE   Acceptance Reactor Vessel Beltline Region            Heat                               wt%          Cv USE     1019 n/cm2    USE          Ct USE    Criterion Location                    Number             Type                           ft-lbf    (E>1 MeV)                              ft-lbf Upper Shell Plate B5453-1                 C5162-1           A 533B            0.110           82      00300.040      9.4         7-4474.3     a50 Upper Shell Plate B5453-3                 C5162-2           A 533B            0.110          86.5     0.0300.040     9.4         7-"78.4      &#x17d;50 Upper Shell Plate B5011-1R                C4377-1           A 533B            0.110           72      094300.040     9.4         6&8-65.2     ?50 Upper Shell Long. Weld 1-201A           21935/12008       Linde 1092          0.220          118      0-0300.038      18         96,96,8      250
-- using surveillance data              21935/12008       Linde 1092          0.220          118         0.038       20PI          94.4       >50 Upper Shell Long. Weld 1-201B           21935/12008       Linde 1092          0.220          118      00280.037       18         97496.8      >50
-4Using surveillance data               21935/12008       Linde 1092          0.220          118         0.037       20"01         94.4       -50 Upper Shell Long. Weld 1-201C           21935/12008       Linde 1092         0.220           118      0.0230.031      17         0-497.9      ?50
-Using surveillance data                21935/12008       Linde 1092         0.220           118         0.031       1901)         95.6       -50 Upper Shell to Intermediate Shell          21935          Linde 1092         0.183           109      0-0300.040    4416          24391.6     a50 Weld 8-201 Notes:
(i) Per the guidance of 10 CFR 50.61 and Position 1.2 unless otherwise noted.
(ii) PercentageUSE decrease is based on Position 2.2 of Regulatory Guide 1.99, Revision 2.
Section 4 PG&E Letter DCL-11-136                                                                 TIME-LIMITED AGING ANALYSES Page 92 of 98

==4.9   REFERENCES==
: 39. Westinghouse Report WCAP-17315-NP. Diablo Canyon Units 1 and 2 Pressurized Thermal Shock and Upper-Shelf Energy Evaluations.Rev. 0. July 2011. Westinghouse Non-ProprietaryClass 3.
: 40. Westinghouse Report WCAP-17299-NP. Fast Neutron Fluence Update for Diablo Canyon Unit I and Unit 2 Pressure Vessels. Rev. 0. February2011. Westinghouse Non-ProprietaryClass 3.
Appendix A PG&E Letter DCL-1 1-136                                Final Safety Analysis Report Supplement Page 93 of 98 A1.15         Reactor Vessel Surveillance The Reactor Vessel Surveillance program manages loss of fracture toughness due to 1 7 neutron embrittlement in reactor materials exposed to neutron fluence exceeding 1.0E n/cm2 (E>1.0 MeV). The program is consistent with ASTM E 185-70 and ASTM E 185-73 for Units 1 and 2, respectively. Capsules are periodically removed during the course of plant operating life. Neutron embrittlement is evaluated through surveillance capsule testing and evaluation, ex-vessel neutron fluence calculations, and monitoring of reactor vessel neutron fluence. The testing program and reporting conform to requirements of 10 CFR 50 Appendix H, Reactor Vessel Material Surveillance ProgramRequirements.
Data resulting from the program is used to:
Determine pressure-temperature limits, minimum temperature requirements, and end-of-life Charpy upper-shelf energy (Cv USE) in accordance with the requirements of 10 CFR 50 Appendix G, Fracture Toughness Requirements; and, Determine end-of-life RTPTS values in accordance with 10 CFR 50.61, Fracture Toughness Requirements for ProtectionAgainst Pressurized Thermal Shock.
The Reactor Vessel Surveillance program provides guidance for removal and testing or storage of material specimen capsules. All capsules that have been withdrawn and tested were stored.
For Unit 1, the last capsule is expected to be withdrawn during the currcnt opFraFing term1R17 refueling outage after it has accumulated a fluence equivalent to 660 years of operation. The remaining four standby capsules have low lead factors, will remain inside the vessel throughout the vessel lifetime, and will be available for future testing.
There are no capsules remaining in the Unit 2 vessel. All capsules were removed because high lead factors produced exposures comparable to the fluences expected at the end of the period of extended operation.
DCPP Units 1 and 2 currently use ex-vessel monitoring dosimetry, which consists of four gradient chains with activation foils outside the reactor vessel, which will be used to monitor the neutron fluence environment within the beltline region.
Appendix A PG&E Letter DCL-1 1-136                               Final Safety Analysis Report Supplement Page 94 of 98 A3.1.2             Pressurized Thermal Shock The most recent coupon examination results for both units show that the increase in RTNDT in plate and weld materials are bounded by that predicted by Regulatory Guide 1.99, Radiation Embrittlement of Reactor Vessel Materials, Revision 2 for Units 1 and 2.
The results demonstrate that the DCPP reactor vessel material ages consistently with Regulatory Guide 1.99 predictions, and provides a conservative means to satisfy the requirement of 10 CFR 50.61; thus providing assurance of the reactor vessel integrity.
Unit 1 Using Regulatory Guide 1.99 Position 2.1 and 1.1 methods, RTPTS values were generated for beltline and extended beltline region materials, the upper shell plates and associated welds, of the Unit 1 reactor vessel for EOLE fluence values. The projected RTpms values for EOLE did nRt meet the 10 CFR 50.61 screening criteria for beltline and extended beltline materials. The Unit I RTpTs was projected to the end of the period of extended operation in accordance with 10 CFR 54.21(c)(1)(ii). RTpTs remains within acceptable values through the period of extended operation.
The Un~it 1 reactor Vessel fluence Will continue to be monitored as pa~t of the IDCPP1 Reactor Vessel Surwe;iance program, deScrFibed in Section A!.16 and therefore will be managed to the end of the period of extended operation in accordance with 10 CFR 54.21 (G)(4)(4~i.
Unit 2 The RTPTS values generated for beltline and extended beltline region materials, the upper shell plates and associated welds, of the Unit 2 reactor vessel for fluence values at EOLE meet the 10 CFR 50.61 screening criteria. The Unit 2 RTPTS was projected to the end of the period of extended operation in accordance with 10 CFR 54.21(c)(1)(ii).
RTPTs remains within acceptable values for the period of extended operation.
Appendix A PG&E Letter DCL-1 1-136                                                                                        Final Safety Analysis Report Supplement Page 95 of 98 Table A4-1 License Renewal Commitments Item #                                                   Commitment                                                     LRA           Implementation Section             Schedule 23    DCD 11l replac         he      rnt ca;rbo&#xf7;n steel with stai8nles steel cl'aRd     P 2 2 pump casing in      3-3-2-2-1-4  Prier to the period of the G"\/CS* with a completely stainless  . teel PmUP casing*.Completed                                                 edeided epefatkmCompleted 24    PG&E will implement the revised PTS rule (10 CF-R 50.61 a). in the event that the prvss                        472-2     At least 3 yearsprier of 10 CFR -50.61(a)cannot be mnet, PG&E will implement alternate               eptions, such as lu             A3.1.2     te eXceeding the PTS edUctiona          *prvided in 0CFR=D50.1 Deleted                                                                        c       ing criterioA *f 10 CFR 50.U6 Delete d
31   The Unit 2 gap repair work will be completed prior to the period of extended                                   2.,27      PDrier to the period epCat9         omCompleted                                                                                               of-e-xtepded-epeatiGR.Complet ed 35   DGPP will revise the test procedure acceptance criteria to specifically preclude repositioning a             B2.4.21      Prior to the period tub...e mo.re than oce without capping or replacing. This will preclude repositioning a tube                              Of.            oeded having chrom~e plated 6U~fi9es fromA the chrome being moved out of the a;reas of known                                    ope~ation-.Complet wear-.Completed                                                                                                           ed 62   Implementation upgrades is plannedfor allforUnit 2 Diesel April,       Generator Stating Air and Turbocharger Air Compressr 2011.Completed                                                                      Pror of e to the period
                                                                                                                                                   ".....
epwafieR Complete d
71   The intake Structure will bereturned to (a)(2) status pior tothe period of exended operatin.                  92..32     Prio to the pered of The Inta;;ke Structure is currently scheduled to be returned to (a)(2) status by the end of                              AkteRdt4-2-044Completed                                                                                                           GpewatjenComp/eted Appendix B PG&E Letter DCL-1 1-136                                    AGING MANAGEMENT PROGRAMS Page 96 of 98 B2.1.15        Reactor Vessel Surveillance Program Description The Reactor Vessel Surveillance program manages loss of fracture toughness due to neutron embrittlement in reactor materials exposed to neutron fluence exceeding 1.0E 17 n/cm 2 (E>1.0 MeV). The program is consistent with ASTM E 185-70 and ASTM E 185-73 for Units 1 and 2, respectively. Capsules are periodically removed during the course of plant operating life. Neutron embrittlement is evaluated through surveillance capsule testing and evaluation, ex-vessel neutron fluence calculations, and monitoring of reactor vessel neutron fluence. The testing program and reporting conform to requirements of 10 CFR 50 Appendix H, Reactor Vessel Material Surveillance Program Requirements. Data resulting from the program is used to:
* Determine pressure-temperature limits, minimum temperature requirements, and end-of-life Charpy upper-shelf energy (Cv USE) in accordance with the requirements of 10 CFR 50 Appendix G, Fracture Toughness Requirements; and,
* Determine end-of-life RTPTS values in accordance with 10 CFR 50.61, Fracture Toughness Requirements for ProtectionAgainst PressurizedThermal Shock.
The Reactor Vessel Surveillance program provides guidance for removal and testing or storage of material specimen capsules. All capsules that have been withdrawn and tested were stored.
For Unit 1, the last capsule is expected to be withdrawn during the current Opeatng te-mlR17 refueling outage after it has accumulated a fluence equivalent to 660 years of operation. The remaining four standby capsules have low lead factors, will remain inside the vessel throughout the vessel lifetime, and will be available for future testing.
There are no capsules remaining in the Unit 2 vessel. All capsules were removed because high lead factors produced exposures comparable to the fluence expected at the end of the period of extended operation.
DCPP Units 1 and 2 currently use ex-vessel monitoring dosimetry, which consists of four gradient chains with activation foils outside the reactor vessel, which will be used to monitor the neutron fluence environment within the beltline region.
NUREG-1801 Consistency The Reactor Vessel Surveillance program is an existing program that is consistent with NUREG-1801, Section XI.M31, Reactor Vessel Surveillance.
Appendix B PG&E Letter DCL-11-136                                    AGING MANAGEMENT PROGRAMS Page 97 of 98 Exceptions to NUREG-1801 None Enhancements None Operating Experience Reactor Vessel Surveillance program experience at DCPP is evaluated and monitored to maintain an effective program. This is accomplished by promptly identifying and documenting (using the Corrective Action Program) any conditions or events that could compromise the program. In addition, industry operating experience provides input to ensure that the program is maintained. The DCPP operating experience findings for this program identified no unique plant specific operating experience; therefore DCPP operating experience is consistent with NUREG-1801.
The Reactor Vessel Surveillance program has provided materials data and dosimetry for the monitoring of irradiation embrittlement since plant startup. The use of this program has been reviewed and approved by the NRC during the period of current operation. Surveillance capsules have been withdrawn during the period of current operation, and the data from these surveillance capsules have been used to verify and predict the performance of DCPP reactor vessel beltline materials with respect to neutron embrittlement. Calculations have been performed as required to project the reference temperature for pressurized thermal shock (RTPTs) and Charpy upper-shelf energy (Cv USE) values to the end-of-license-extended (EOLE). DCPP pressure-temperature limit curves are valid up to a stated vessel fluence limit, and must be revised prior to operating beyond that limit.
Neutron Fluence The last capsule withdrawn and tested from Unit 1 was Capsule V at the end-of-cycle (EOC) 11, which yielded an exposure less than that expected at EOLE. Capsule B will be withdrawn at 23.2 EFPY in order to capture enough fluence data for EOLE. The last capsule withdrawn and tested from Unit 2 was Capsule V at EOC 9, which yielded an exposure comparable to that expected at EOLE. The EOLE fluence projections include the use of lower-leakage cores and the Unit 1 power uprate.
PressurizedThermal Shock All of the beltine and extended beitline materialsin the Diablo Canyon Units 1 and 2 reactorvessels are projected to remain below the PTS screening criteria values of 270&deg;F, for axially oriented welds and plates / forgings, and 300&deg;F, for circumferentially oriented welds (per10 CFR 50.61), through EOL (32 EFPY) and EOLE (54 EFPY). T-he-projected Unit 4 RTPTv.alUe      did not meAet thI   CFR 501 Ecrening Q1*0                    crGitria for beitline and extended bcftline m~aterials. The Unit 2 RTp~-was-p3+*eted to the end e-Appendix B PG&E Letter DCL-1 1-136                                    AGING MANAGEMENT PROGRAMS Page 98 of 98 the period of extended operation. The Unit 1 reactor vessel fluenrce will cntepinue to be moni~tored as part of the Reactor Vessel SurveiIlaRce program.
Charpy Upper-Shelf Energy The most recent coupon examination results for both units demonstrate that the DCPP reactor vessel material ages consistently with Regulatory Guide 1.99 predictions and provides a conservative means to satisfy the requirements of 10 CFR 50, Appendix G.
The Cv USE values were revised with projections to the end of the period of extended operation.
The Reactor Vessel Surveillance program operating experience information provides objective evidence to support the conclusion that the effects of aging will be adequately managed so that the component intended functions will be maintained during the period of extended operation.
Conclusion Continued implementation of the Reactor Vessel Surveillance program provides reasonable assurance that the aging effects will be managed so that the systems and components within the scope of this program will continue to perform their intended functions consistent with the current licensing basis for the period of extended operation.}}