ML22038A435

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Transmittal of Revision 17 to PGE-J0691 Trojan- Independent Spent Fuel Storage Installation (ISFSI) Safety Analysis Report
ML22038A435
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 01/13/2022
From: Jenkins B
Portland General Electric Co
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Division of Fuel Management
References
CAC 001028, EPID L-2017-RNW-0-011, VPN-001-2022
Download: ML22038A435 (12)
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Text

Director, Office of NMSS USNRC CopyNo.01

/ ~ Portland Gener.it. Electric Company l'PGE_.1 Trojan ISFSI

'.,. - / , 71760 Columbia River Hwy

, Rainier, Oregon 97048 January 13, 2022 VPN-001-2022 Trojan-lSFSI Dockgt Nb. 72-17 License SNM-2509 CA!: No. 001028 EPID No. L-2017-RNW-0_011 ATTN: Document Contrpl Desi<

Director, Division of5pent Fuel Management Office of Nuclear Material Safety and Safeguards*

U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Transmittal of Revis.ion 17 to PGE-J0691 Trojan- Independent Spent Fuel Storage Installation fISFSI} Safety Af)alysis Report Pursuant to 10 CFR 72.70{c), this letter transmits the Trojan ISFSJ's updated PGE-1069, Trojan I_SFSI Saf$ty Analy$is Report (SAR), Revision 17 clian~ed p.ages, as a part ofTr~jan ISFSI license SNM-2509, Amendment 7.

  • This Revision 17 of the Trojan ISFSI SAR reVi$~ SAR Section 9.7.6, Str1-1ctural Inspection Program, and Section 9.7.7, Concrete Cask.Interior Inspection Program to compJywith the Trojan 15.FSI Renewed License Tech Spec 5.5.5.and SAR 9. 7.8.4 to officially implement the new Aging Management Program (AMP) effective January 1, 2022.

Trojan ISFSI Renewed License Technical Specification 5.5.5 states: "The Aging Manag~ment'Progr~m will establish the processes and proce.c;lures to manc1ge .the aging of ISFSI components. into ext.ende.d storage perioqs. This program will be implemented consistent with the l~FSI Safety Analysis Report. The Aging Management Program will be implemented on or before 20 years fr.on:rthe date of the first canister loading."

In addition, SAR 9.7.8.4.states.: "Consistent with Nl.)REG-1927,*Section 3.6.1.4, Timing.of lnsp.ections, and LRA Appendix D, Baseline Inspections, Tr1;Jjan wjfl S!';hedul(;l the first implementation.of the following four AMPs (SA.R Sections 9.7.8.4.1 through.9.7.8.4.4) to be cornP.leted in.calendar years 2022-thro1:1gh 2023 and these will be considered Baseline Inspections." Note: The Trojan AMP 01 document states: "The first canister loaded.at Trojan was plac_ed in service on the Trojan ISFSI storage pad on Janu.ary 17, 2003. The program will be implemented on ..

January 1, 2022 an~ will r:eplace the SA~, Section 9,7.6, Structural. Inspection Progr-am, and Section 9.7.7, Concrete Casie Interior Inspection Program."

PGE will continue to upc!ate the Trojc)n ISFSI SAR in accordance with*the requirements in 10 CFR 72.70{b) and (c) and make the*changes consistent with 1P CFR 72.48{c).

Please contact Mr. Tom Romay of my staff at 503-556-7001 if you have questions regarding this correspondence.

Sincerely,

~-.~*v-f,*~ l Pr~oJLc.l!o.

. -~ ~~ \t __..J O fd, Bradley Y. Jenkins /, '.[.,"1it:. ,~S Vice President, Utility Operations Enclosure c: C, T. Markley, NRC, NMSS, SFPD Director, DNMS, NRC Region IV T. R. Cornett, ODOE Ntvf S52L>

Nl-1:5 s 2tp JV/15-5

Revision 17 to PGE-1069 Trojan Independent Spent Fuel Storage Installation (ISFSI) Safety Analysis Report (SAR)

Revised pages are to be replaced as follows:

REMOVE INSERT Table of Contents Page xiii Page xiii Pages xxiv and xxv Pages xxiv and xxv Page xxix Page xxix Section 9 Pages 9-13 through 9-18 Pages 9-13 through 9-18

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9.0 CONDUCT OF OPERATIONS ........................................................................................ 9-1 9.1 ORGANIZATIONAL STRUCTURE ............................................................................. 9-2 9.1.1 ISFSI OPERATION ORGANIZATION .................................................. :....... 9-2 9.1.1.1 Corporate Organization ... --.. -- -- -- .--.... --........... --..... --.-- .... -- -- .--.... -- -- .-- 9-2 9.1.1.1.1 Support Staff................................................................ 9-2 9.1.1.1.2 ISFSI Safety Review Committee ................................ 9-2 9.1.1.2 Operating Organization ..... --.---- .. --.--* .... --......... ----.--* .. *------**--***------** 9-2 9 .1.1.3 Nuclear Oversight**--***--*--**----*----*--*****--**--******--*----*----*--*--******------** 9-3 9.1.1.4 Succession of Authority*------**--****-- .. *--**--*--* .... -- ... -- .. *-- -- ... **--*-- .. -- -- -- 9-3 9.1.2 PERSONNEL QUALIFICATION REQUIREMENTS ................................... 9-3 9.1.3 LIAISON WITH OUTSIDE ORGANIZATIONS ........................................... 9-3 9.2 PRE-OPERATIONAL AND STARTUP TESTING ....................................................... 9-4 9.3 TRAINING PROGRAMS ............................................................................................... 9-5 9.3.1 TRAINING PROGRAM DESCRIPTION ....................................................... 9-5 9.4 NORMAL OPERATIONS .............................................................................................. 9-6 9.4.1 PROCEDURES ................................................................................................. 9-6 9.4.2 RECORDS ........................................................................................................ 9-6

  • 9.5 9.6 EMERGENCY PLANNING ........................................................................................... 9-8 REVIEWS AND AUDITS .............................................................................................. 9-9 9.6.1 9.6.2 9.6.3 INDEPENDENT SAFETY REVIEWS ............................................................ 9-9 ISFSI SAFETY REVIEW COMMITTEE ............................................. ,.......... 9-9 RECORDS ...................................................................................................... 9-12 9.7 PROGRAMS .................................................................................................................. 9-13 9.7.1 FIRE PROTECTION PROGRAM ................................................................. 9-13 9.7.2 TRAINING PROGRAM ................................................................................ 9-13 9.7.3 TROJAN ISFSI EMERGENCY PLAN .......................................................... 9-13 9.7.4 TROJAN ISFSI SECURITY PLAN ............................................................... 9-13 9.7.5 TRANSFER CASK AND CONCRETE CASK HANDLING AND STORAGE PROGRAM ................................................................................. 9-13 9.7.6 STRUCTURAL INSPECTION PROGRAM ................................................. 9-13 9.7.7 CONCRETE CASK INTERIOR INSPECTION PROGRAM ....................... 9-14 9.7.8 AGING MANAGEMENT PROGRAM ......................................................... 9-14 9.7.8.1 Scoping Evaluation Results--*****--*----*--****--******--**--****--******--***--**** 9-14 9.7.8.2 Aging Management Review Results---- .. ----... --------**--*--**------***--**** 9-15 9.7.8.3 Time-Limited Aging Analysis Results*******----*------**----------******--*** 9-15 9.7.8.4 Aging Management Programs----***--*----***--*----***----**----*--*------******* 9-16
9. 7.8.4.1 MPC Aging Management Program ............................ 9-17 9.7.8.4.2 Transfer Cask Aging Management Program .............. 9-17
  • 9.7.8.5 9.7.8.4.3 Concrete Cask Aging Management Program ............. 9-17 9.7.8.4.4 Transfer Station Aging Management Program ........... 9-17 Tollgate Assessments .................................................................... 9-18 xm Revision 17

EfJ Troian Independent Spent Fuel Storage Installation Safety Analysis Report LIST OF EFFECTIVE PAGES Page Number Revision Table of Contents i 7 Table of Contents ii and iii 4 Table of Contents iv 12 Table of Contents v through vii 9 Table of Contents viii 4 Table of Contents ix and x 7 Table of Contents xi 4 Table of Contents xii 16 Table of Contents xiii 17 Table of Contents xiv through xvii 15 Table of Contents xviii 16 Table of Contents xix through xxiii 15 Table of Contents xxiv and xxv 17 Table of Contents xxvi and xxvii 15 Table of Contents xxviii 16 Table of Contents xxix 17

  • 1-1 through 1-6 1-7 Figure 1.1-1 Figure 1.3-1 Appendix l .A 4

6 4

2 4

Drawing 3969 2 Drawing 3970 5 PGE-002 2 Drawing 3971 2 2-1 7 2-2 6 2-3 13 2-4 7 2-5 and 2-6 2 2-7 through 2-11 16 2-12 through 2-15 8 2-16 2 2-17 7 2-18 8 2-19 7 2-20 5 2-21 8 2-22 through 2-27 2 2-28 5 XXIV Revision 17

Tro;an Independent Spent Fuel Storage Installation Safety Analysis Report

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LIST OF EFFECTIVE PAGES Page Number Revision 2-29 6 2-30 through 2-33 2 2-34 7 2-35 and 2-36 2 2-37 16 2-38 through 2-42 2 2-43 4 2-44 8 2-45 2 2-46 6 2-47 2 Table 2.1-1 0 Table 2.1-2 0 Table 2.2-1 2 Table 2.7-1 2 I

  • Figure 2.1-1 Figure 2.1-2 Figure 2.1-3 Figures 2.1-4 through 2.1-6 Figures 2.2-1 and 2.2-2 4

7 4

0 0

Figures 2.3-1 through 2.3-6 0 Figure 2.4-1 0 Figure 2.4-2 8 3-1 through 3-5 4 3-6 6 3-7 through 3-14 4 3-15 5 3-16 4 3-17 5 3-18 15 3-19 and 3-20 12 3-21 15 3-22 2 3-23 11 3-24 2 3-25 5

  • Table 3.1-1 Tables 3.1-2 and 3.1-3 Table 3.1-4 XXV 0

2 0

Revision 17

  • _u_o~ia_n_m_d~~~e_nd_e_nt~S~pe~n_tF_u_e_lS~to~r~~~e~m~s~ta~ll=at~io~n~Sa~fe~fy~A LIST OF EFFECTIVE PAGES

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Page Number Revision Table 8.2-5 2 Tables 8.2-6 and 8.2-7 16 Table 8.3 -1 8 Figures 8.1-1 and 8.1 -2 2 Figures 8.2-1 through 8.2-4 2 Figure 8.2-6 2 9-1 4 9-2 and 9-3 6 9-4 4 9-5 through 9-7 6 9-8 4 9-9 through 9-12 6 9-13 through 9-18 17

  • 9-1 9 through 9-23 Table 9.1-1 Tables 9.7-1 through 9.7-19 Figure 9.1-1 15 8

15 6

10-1 4 11-1 6

  • XX.lX Revision 17
  • Trojan independent Spent Fuel Storage Installation Safety Analysis Report 9.7 PROGRAMS The following programs will be established, implemented, and maintained in addition to the programs required by ISFSI Technical Specifications, Section 5.5.

9.7.1 FIRE PROTECTION PROGRAM The Fire Protection Program provides controls to prevent and protect the facility from fues and explosions which could impact the safe storage of spent nuclear fuel or cause the release of radioactive material.

9.7.2 TRAINING PROGRAM The Training Program contains the training and certification requirements for the ISFSI Specialists.

9.7.3 TROJAN ISFSI EMERGENCY PLAN The Trojan ISFSI Emergency Plan contains actions and responsibilities to be performed in response to a radiological emergency. This plan complies with the requirements of 10 CFR 72.32(a).

9.7.4 TROJAN ISFSI SECURITY PLAN The Trojan ISFSI Security Plan (PGE-1073) contains a detailed plan for security measures for physical protection of the ISFSI. In addition, this plan contains contingencies for responding to threats and potential radiological sabotage. This plan complies with the requirements of 10 CFR 72, Subpart H, "Physical Protection."

9.7.5 TRANSFER CASK AND CONCRETE CASK HANDLING AND STORAGE PROGRAM The Transfer Cask and Concrete Cask Handling and Storage Program places controls on the handling and storage of the Concrete Cask, Transfer Cask, and MPC. This program will consist of elements that will control: the heights at which the loaded Concrete Casks can be lifted, use of the Transfer Cask, and arrangement of Concrete Casks on the ISFSI Storage Pad. The program also provides requirements for use of a mobile crane for lifting MPCs in the Transfer Station and provides controls for movement and loading of Transport Casks.

9. 7.6 STRUCTURAL INSPECTION PROGRAM Concurrent with implementation of the Aging Management Program on January 1, 2022, as
  • specified in Section 9.7.8, the Structural Inspection Program inspections for the Concrete Cask 9-13 Revision 17
  • Trojan Independent Spent Fuel Storage Installation Safety Analysis Report Exterior and Transfer Station are replaced by the long-term aging management programs described in Subsections 9.7. 8.4.3 and 9.7.8.4.4.

9.7.7 CONCRETE CASK INTERIOR INSPECTION PROGRAM Concurrent with implementation of the Aging Management Program on January 1, 2022, as specified in Section 9.7.8, the Concrete Cask Interior Inspection Program is replaced by the long-term aging management programs described in Subsections 9.7.8.4.1 and 9.7.8.4.3.

9.7.8 AGING MANAGEMENT PROGRAM Pursuant to Technical Specification 5.5.5, this Aging Management Program (AMP) establishes the processes and procedures to manage the aging of ISFSI components into extended storage periods. As part of the license renewal process detailed in License Change Application 72-07 (Reference 9), an aging management assessment of the Concrete Cask, MPC, Transfer Cask, Transfer Station, Spent Fuel Assembly, and ISFSI Pad was performed to identify inspection and monitoring activities that are necessary to provide reasonable assurance that ISFSI Concrete Cask, MPC, Transfer Cask, and Transfer Station components within the scope of license renewal continue to perform their intended functions consistent with the current licensing basis for the renewed operating period. This section describes the following aging management program activities: scoping evaluation results, aging management review results, and time-limited aging analysis results. In addition, this section describes the Aging Management Programs for inspection and monitoring of the selected MPC and associated Concrete Cask, the Transfer Cask, Concrete Casks, and Transfer Station and the Tollgate Assessments of the overall aging management program.

9.7.8.1 Scoping Evaluation Results This section provides a summary of the Trojan ISFSI renewal scoping evaluation and results.

The scoping evaluation was performed based on the process described in NUREG-1927 (Reference 10). The first step in the process was a screening evaluation to dete1mine which components and structures are within the scope of the license renewal. The second step in the process was identifying the function(s) each in-scope component and structure is required to perform during the period of extended operations.

The components and structures determined to be within the scope of renewal are the MPC, Transfer Cask, Concrete Cask, Fuel Assemblies, Transfer Station (including the Transfer Station Pad and Impact Limiter), and ISFSI Pad. SAR Table 9.7-1 summarizes the results of the scoping evaluation, listing the above in-scope components and structures and the criteria upon which they were determined to be within the scope of renewal. In addition, the scoping evaluation reviewed the subcomponents of the above in-scope components and structures and results for these subcomponents and their intended function(s) are identified in SAR Table 9.7-2 through

  • Table 9.7-7 .

9-14 Revision 17

  • Troian Independent Spent Fuel Storage Installation Safety Analysis Report 9.7.8.2 Aging Management Review Results This section provides a summary of the Trojan ISFSI renewal Aging Management Review (AMR) results. The AMR was performed in accordance with the processes described in NUREG-1927.

A summary of the results of the AMR for the MPCs, Transfer Cask, Concrete Casks, Fuel Assemblies, Transfer Station, and ISFSI Pad is contained in SAR Tables 9.7-8 through 9.7-13, respectively. These tables provide the following information related to each subcomponent determined to require aging management review: the intended function, the material group, the environment, the aging effects requiring management, the aging mechanisms, and the specific aging management activities that manage those aging effects. The tables also identify subcomponents that did not support, or whose failure would not compromise, the SSC intended safety function(s) and were, therefore, not subjected to further aging management review.

9.7.8.3 Time-Limited Aging Analysis Results This section discusses the results for each of the Time-Limited Aging Analyses (TLAAs) evaluated for license renewal. The evaluations have demonstrated that the analyses have been projected to the end of the renewed license period.

MPC Fatigue Evaluation Section 4.2.5.3.6 already indicates that the fow stress, high-cycle conditions during normal dry storage conditions cannot lead to a fatigue failure of the MPC. However, it is possible that repeated lifting of the MPC might cause increased stresses and therefore lower the fatigue life of the MPC. Based on an evaluation (Reference 12) oflifting stresses, the allowable number of

_MPC lifting cycles greatly exceeds the number of MPC lifts necessary during the 60-year storage life.

Neutron Absorber Depletion Evaluation Section 4.8 describes boron depletion of the fixed neutron absorber within the MPC, and demonstrates that it is negligible over 50 years. The same analysis (Reference 13) was updated in support of the license renewal request and concludes that the total depletion of B-10 in Boral over a 500-year period is negligible, and therefore, the neutron absorber will perform its intended function beyond the extended storage period.

  • Transfer Cask Fatigue Evaluation Section 4.8 summarizes a cyclic loading fatigue evaluation of the Transfer Cask which concludes that stresses are well below the endurance limit of the trunnion material. Following placement of
  • MPCs into Concrete Casks, the Transfer Cask is no longer used to lift loaded MPCs. Thus, trunnion fatigue is not an issue during the extended license period. Potential fatigue issues are 9-15 Revision 17
  • Tro;an Independent Spent Fuel Storage Installation Safety Analysis Report limited to Transfer Cask components in the load path when the Transfer Cask supports a loaded MPC in the Transfer Station. As a conservative measure, an evaluation (Reference 14) was performed to determine the allowable number of Transfer Cask lifting cycles involving a loaded MPC. Stresses in this scenario exceed those when supporting a loaded MPC in the Transfer Station. Based on this evaluation, the allowable number of cycles supporting a loaded MPC in the Transfer Station greatly exceeds the number needed during the extended license period.

Fuel Cladding Integrity Evaluation Section 4.2.6.1 describes a calculation for the fuel cladding temperature limit, which is a function of temperature versus time as well as internal rod pressurization. The original fuel cladding temperature limit was established to keep the probability of cladding breach less than 0.5% per fuel rod. This calculation (Reference 15) was revised to ensure that the probability of cladding breach is less than 0.5% over the 60-year storage life at the Trojan ISFSI. Based on the results of the calculation, the life usage fraction of the fuel cladding demonstrates that cladding integrity is assured for the 60-year storage life.

9.7.8.4 Aging Management Programs This section describes the Aging Management Programs for inspection and monitoring of the selected MPC and associated Concrete Cask, the Transfer Cask, Concrete Casks, and Transfer Station as detailed in Tables 9.7-14 through 9.7-17.

Consistent with NUREG-1927 (Reference 10), Section 3.6.1.4, Timing of Inspections, and LRA Appendix D, Baseline Inspections, Trojan will schedule the first implementation of the following four AMPs (SAR Sections 9.7.8.4.1 through 9.7.8.4.4) to be completed in calendar years 2022 through 2023 and these will be considered Baseline Inspections. As described in LRA Appendix D, the Transfer Cask was placed in long-term storage in 2003 and won't be removed from storage until it is needed for fuel transfer; therefore, the Transfer Cask AMP baseline inspection planned to be performed in 2022 or 2023 will be a partial inspection as described in LRA Appendix D.

The Transfer Cask and Transfer Station AMPs are required to be completed prior to their first use for fuel transfer and this is not expected to occur before 2022-2023. If Trojan ISFSI fuel transfer would be scheduled before 2022-2023, the Transfer Cask AMP and Transfer Station AMP would be performed prior to their first use as required by ISFSI License Condition No. 13 (Reference 11) that states:

"However, for the Transfer Cask AMP and Transfer Station AMP, consistent with the timing stated in the LRA, the first inspection will occur prior to the first use of the Transfer Cask and Transfer Station, respectively, as required by Trojan ISFSI License Condition 13."

  • 9-16 Revision 17
  • Trojan Independent Spent Fuel Storage Installation Safety Analysis Report 9.7.8.4.1 MPC Aging Management Program

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This program involves monitoring the exterior surface of a representative MPC, including visual inspection of accessible MPC surfaces for signs of degradation. This inspection shall be performed on MPC-28 at a frequency of 5 years +/-25%. The detailed 10-element MPC Aging Management Program is contained in Table 9:7-14.

9.7.8.4.2 Transfer Cask Aging Management Program The Transfer Cask Aging Management Program utilizes inspections to ensure that the Transfer Cask maintains its intended :function through the extended storage period, by performing a visual inspection for degradation of the external surfaces of the Transfer Cask. This inspection is performed prior to use of the Transfer Cask and once per year (+/-25%) while in use. The detailed 10-element Transfer Cask Aging Management Program is contained in Table 9. 7-15.

9.7.8.4.3 Concrete Cask Aging Management Program The Concrete Cask Aging Management Program utilizes condition monitoring to manage aging effects of the Concrete Casks, both internally and externally. The external Concrete Cask AMP is performed annually (+/-25%) on all Concrete Casks on the pad as a visual inspection to identify any surface deterioration. The internal portion of the Concrete Casks AMP is performed in conj1J11ction with the MPC AMP, and involves a visual inspection of the interior Concrete Cask annular space of cask PCC-03 every 5 years (+/-25%). The detailed 10-element Concrete Cask Aging Management Program is contained in Table 9.7-16.

9.7.8.4.4 Transfer Station Aging Management Program The Transfer Station Aging Management Program utilizes inspections to ensure that the Transfer Station maintains its intended :function through the extended storage period, by performing a visual inspection for degradation of the external surfaces of the Transfer Station and Transfer Station Pad. This inspection is performed prior to use of the Transfer Station and once per year

(+/-25%) while in use. The detailed 10-element Transfer Station Aging Management Program is contained in Table 9.7-17 .

  • 9-17 Revision 17
  • Trojan Independent Spent Fuel Storage Installation Safety Analysis J?.eport 9.7.8.5 Tollgate Assessments Tollgate Assessments are established as a requirement to evaluate aging management feedback and perform a safety assessment that confirms the safe storage of spent nuclear fuel. The impact of the aggregate feedback will be*assessed as it pertains to components at tp.e Trojan ISFSI and actions taken as necessary, such as:
  • Adjustment of aging-related degradation monitoring and inspection programs in AMPs described in Section 9.7.8.4
  • Modification ofTLAAs described in Section 9.7.8.3
  • Performance of mitigation activities Each tollgate assessment ~hould address the following elements:
  • Summary of research findings, operating experience, monitoring data, and inspection results made available since last assessment
  • Aggregate impact of findings, including any trends
  • Consistency of data with the assumptions and inputs in Trojan's TLAAs
  • Effectiveness of AMPs
  • Corrective actions, including any changes to AMPs
  • Summary and conclusions Trojan's tollgates are shown in Table 9.7-18 and performance criteria for tollgate assessments are shown in Table 9.7-19. Note that the implementation of these tollgates does not imply that Trojan will wait until one of these designated times to evaluate information. Trojan will continue to follow existing processes for addressing emergent issues, including the use of the corrective action program on site. These tollgates are specific times where an aggregate of information will be evaluated as a whole. .
  • 9-18 Revision 17
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