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San Onofre, Units 1, 2 & 3 and ISFSI - Response to Request for Additional Information Regarding Emergency Planning Exemption Request
	ML14258A003
Person / Time
Site:	San Onofre
Issue date:	09/09/2014
From:	Palmisano T J; Southern California Edison Co
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	TAC 3835, TAC 3836, TAC 3837
	Download: ML14258A003 (100)
	v • d • e

I SOUTHERN CALIFORNIA EDISONAn EI)ISON INTERNATONAl

" Cmpa nThomas I. Palmisano Vice President

& Chief Nuclear OfficerSeptember 9, 201410 CFR 50.12U. S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, D.C. 20555

Subject:

Docket No. 50-206, 50-361, 50-362, and 72-041Response to Request for Additional Information Regarding Emergency Planning Exemption RequestSan Onofre Nuclear Generating

Station, Units 1, 2, 3 and ISFSI(1) Letter from T. J. Palmisano (SCE) to the U.S. Nuclear Regulatory Commission (NRC) dated March 31, 2014;

Subject:

Docket Nos. 50-206, 50-361, 50-362, and 72-041, Emergency Planning Exemption

Request, San Onofre Nuclear Generating

Station, Units 1, 2, 3, andIndependent Spent Fuel Storage Installation

Reference:

(2) Letter from T. J. Wengert (NRC) to T. J. Palmisano (SCE) datedAugust 27, 2014;

Subject:

San Onofre Nuclear Generating StationUnits 1, 2 and 3, Request for Additional Information Re: Emergency Planning Exemption Request (TAC NOS 3835, 3836 and 3837)

Dear Sir or Madam:

By letter dated March 31, 2014 (Reference 1), Southern California Edison (SCE)submitted an exemption request from certain requirements of 10 CFR 50.47,"Emergency Plans," and 10 CFR Part 50, Appendix E, "Emergency Planning andPreparedness for Production and Utilization Facilities,"

for San Onofre NuclearGenerating Station (SONGS) Units 1, 2, and 3, and the Independent Spent FuelStorage Installation (ISFSI).

Granting the exemptions requested is necessary tosupport review and approval of a Permanently Defueled Emergency Plan andassociated Emergency Action Levels both of which are being addressed separately.

By letter dated August 27, 2014 (Reference 2), the NRC requested additional information related to the proposed exemption request.

The response to the NRCrequest for additional information is contained in Enclosure 1 to this letter. Theresponse results in changes to the proposed exemptions of Reference

1. A revisedexemption table is provided as Enclosure 2 to this letter. The conclusions of the nosignificant hazards consideration and environmental considerations contained inReference 1 are not affected by, and remain applicable to, this revised request.P.O. Box 12~8San Clemente, CA 92672(949) 368-6575 PAX 86575Fax: (949) 368-6183Tom. Palmisano@sce.com Document Control Desk-2-September 9, 2014There is one new regulatory commitment in this submittal.

See Enclosure 3 for details.Should you have any questions, or require additional information, please contactMs. Andrea Sterdis at (949) 368-9985.

I declare under penalty of perjury that the foregoing is true and correct.Executed on 2-6 / 4-Sincerely, Enclosure 1: Response to NRC Request for Additional Information Attachment A: SONGS Units 2 and 3 Fuel Management RecordsAttachment B: ORIGEN-ARP/ORIGEN-S input filesEnclosure 2: Modified Exemption Table, Emergency Planning Exemption RequestEnclosure 3: Regulatory Commitments cc: M. L. Dapas, Regional Administrator, NRC Region IVT. J. Wengert, NRC Project Manager, SONGS Units 2 and 3R. E. Lantz, NRC Region IV, San Onofre Units 2 and 3G. G. Warnick, NRC Senior Resident Inspector, SONGS Units 2 and 3S. Y. Hsu, California Department of Public Health, Radiologic Health Branch ENCLOSURE 1Response to NRC Request for Additional Information Regarding Emergency Planning Exemption Request NRC Request for Additional Information By letter dated August 27, 2014, the NRC provided Requests for Additional Information (RAIs) regarding SouthernCalifornia Edison's (SCE's) Emergency Planning exemption request dated March 31, 2014. The following are the NRCRAIs and the SCE responses.

NRC RAI:By letter dated March 31, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No.ML1 4092A332),

Southern California Edison (SCE) requested exemptions from portions of Part 50 of Title 10 of the Codeof Federal Regulations (10 CFR 50) for the San Onofre Nuclear Generating Station (SONGS) Units 1, 2 and 3Radiological Emergency Response Plan. Specifically, SCE requested and [sic] exemption from certain emergency planrequirements of 10 CFR 50.47(b),

10 CFR 50.47(c)(2),

and Section IV to Appendix E of 10 CFR 50. The requested exemptions would allow SCE to reduce emergency plan requirements and subsequently revise the SONGS Radiological Emergency Response Plan consistent with the permanently defueled condition of the reactors.

SONGS Unit 1 was permanently shutdown in 1992 and completed permanent defueling in March 1993. SCE activelydecommissioned the facility, and most of the structures and equipment have been removed and disposed.

By letter dated September 12, 2013 (ADAMS Accession No. ML131640201),

SCE submitted certification to the U.S.Nuclear Regulatory Commission (NRC) indicating its intention to permanently cease power operations at SONGS Units 2and 3 as of June 7, 2013, pursuant to 10 CFR 50.82(a)(1)(i).

By letters dated June 28, 2013 and July 22, 2013 (ADAMSAccession Nos. ML13183A391 and ML13204A304, respectively),

SCE submitted certifications to the NRC for thepermanent removal of fuel from the Unit 2 and Unit 3 reactor vessels, pursuant to 10 CFR 50.82(a)(1)(ii).

Upon docketing of certifications of the permanent cessation of power operations and for the permanent removal of fuel from the reactorvessels pursuant to 10 CFR 50.82(a)(1)(ii),

the 10 CFR Part 50 licenses for SONGS Units 2 and 3 no longer authorize operation of the reactors, or emplacement or retention of fuel into the reactor vessels, as specified in 10 CFR 50.82(a)(2).

In reviewing the request for exemption, the NRC staff used precedent from past emergency preparedness (EP)-related decommissioning exemption

reviews, including the reviews submitted for the EP rule changes effective November 23,2011. The staff also informed our review with guidance and regulations applicable to an Independent Spent Fuel StorageInstallation.

The staff also considered the analysis described in NUREG-1 738, "Technical Study of Spent Fuel PoolAccident Risk at Decommissioning Nuclear Power Plants,"

February 2001 (ADAMS Accession No. ML010430066).

Page 1 Based on the NRC staffs initial review of SCE's March 31, 2014, EP exemption

request, the following draft requests foradditional information (RAIs) are required to facilitate completion of the staffs technical review:Note: In the following RAIs, bold strikc out text indicates the requested exemption from rule language.

Itemnumbers are the numbers in the left hand column in Table 1 of Enclosure 2 of the application.

(MF3835)

RAI-001The basis for exemption of Item 1 in Table 1 (Enclosure

2) is generic and does not state specifically why SONGS shouldbe considered for exemption.

Similarly, the following item numbers also contain only generic information in the basis forexemption:

3, 4, 5, 9, 11, 17, 18, 20, 23, 25, 26, 32, 43, 48 and 49. Please provide justifications specific to SONGS forgranting the exemptions listed above.SCE Response:

SONGS exemption request dated March 31, 2014 (Reference

1) provided a table of proposed exemptions and associated justifications (Reference 1, Enclosure 2, Table 1), hereafter referred to as the proposed exemption table. Enclosure 2 ofthis submittal contains a modified version of SONGS proposed exemption table, hereafter referred to as the modifiedexemption table. The first column of the modified exemption table shows the requested exemptions as modified by thisRAI response.

The second column shows the modified bases for requesting exemption.

Note that the modifiedexemption table includes only those elements affected by RAIs but does not withdraw SCE's request for the remaining elements of the proposed exemption table.The modified exemption table provides a revised basis for exemption, including information specific to SONGS, for Item 1of the proposed exemption table. As noted in the response to RAI-002, the site-specific bases for most of the proposedexemptions is the same. That is, no currently applicable Design Basis Accident (DBA) has dose consequences in excessof requirements and the heat-up rate for beyond design basis event meets noted regulatory guidance.

In addition, the modified exemption table provides information specific to SONGS, including a revised basis for exemption for items 3, 4, 5, 9, 11, 17, 18, 20, 23, 25, 26, 32, 43, 48 and 49 of the proposed exemption table.Page 2 (MF3835)

RAI-002The basis for exemption of Item 1 in Table 1 (Enclosure

2) does not address design-basis accidents (DBAs). Pleaseprovide a discussion justifying that no currently applicable DBA will exceed U.S. Environmental Protection Agency (EPA)Protective Action Guides.SCE Response:

Reference 1, Enclosure 1, Section 3 addresses Design Basis Accidents at SONGS by providing a summary of the limitingcurrently applicable DBA and the resulting dose consequences.

That discussion demonstrates that the doseconsequences at the Exclusion Area Boundary from the remaining applicable DBAs, calculated as of August 2013, arewithin the applicable regulatory limits, including the U.S. Environmental Protection Agency (EPA) Protective ActionGuides. All applicable DBAs (listed below) were updated.

The DBAs can be effectively grouped as Radioactive WasteGas Releases, Fuel Handling Accidents, Load Handling Events and Spent Fuel Pool Boiling Events. The limiting DBAresults from a dose perspective are summarized in Reference 1, Enclosure 1 Section 3 as previously noted. Further,results from beyond design basis events are also addressed.

The site-specific justification in Item 1 of the Exemption Table was clarified to better reflect SONGS treatment of both DBA and Beyond DBA events. It is worth noting that theDBA doses and adiabatic heat-up timing are the key plant-specific results upon which most of the proposed exemptions are based. This will be noted as appropriate in the modified Table.CURRENTLY APPLICABLE DESIGN BASIS ACCIDENTS 15.7.3.115.7.3.215.7.3.315.7.3.415.7.3.515.7.3.715.7.3.815.7.3.10 15.7.3.11 Radioactive Waste Gas System Leak or FailureRadioactive Waste System Leak or Failure (Release to Atmosphere)

Postulated Radioactive Releases Due to Liquid Tank FailuresDesign Basis Fuel Handling Accident Inside Fuel BuildingSpent Fuel Cask Drop Accidents Test Equipment DropSpent Fuel Pool Boiling AccidentSpent Fuel Assembly DropUse of Miscellaneous Equipment Under 2000 lbs.Page 3 (MF3835)

RAI-003Item 29 in Table 1 (Enclosure

2) states the following:

"Appendix E.IV.D.3:

A licensee shall have the capability to notifyresponsible State and local governmental agencies within 15 minutes promptly (within 60 minutes) after declaring anemergency."

The NRC staff cannot approve the addition of rule language via an exemption, only by issuing rulemaking.

Please providethe site-specific justification for extending the notification time beyond 15 minutes, including the notification time to whichSONGS will be committed to.SCE Response:

SCE has revised Item 29 of the proposed exemption table. The changes provided in the modified exemption table, Item29, remove the previously proposed text in the left-hand column referring to a 60-minute notification requirement, providea site-specific justification for the exemption is provided, and reference a proposal for a 60 minute limit for notifications inthe Permanently Defueled Emergency Plan.(MF3835)

RAI-004Item 40 in Table 1 (Enclosure

2) contains no justification for deletion of "Civil Defense" and "local news media persons".

Please provide site-specific justification for exempting these requirements.

SCE Response:

The modified exemption table, Item 40, provides a site-specific justification for the deletion of "Civil Defense" and "localnews media persons."

(MF3835)

RAI-005Justifications for Items 46 and 47 in Table 1 (Enclosure

2) state: "see basis for section IV.2." The basis for section IV.2states "see basis for 50.47(b)(10)."

Please provide specific justification for these two items or reference the correctsection.Page 4 SCE Response:

Items 46 and 47 of the proposed exemption table address State and local participation in ingestion pathway Emergency Planning Zone (EPZ) and plume exposure pathway EPZ exercises.

The plume exposure pathway EPZ and the ingestion pathway EPZ would be eliminated by the proposed exemption to 10 CFR 50.47(c)(2),

described in Item 10 of theproposed exemption table.The modified exemption table provides justifications for Items 46 and 47 that refer to the basis for exemption from Item 1,10 CFR 50.47(b),

as modified in response to RAIs 1 and 2, above. The modified basis for Item 1 provides design basisand beyond-design-basis accident analysis results justifying that the offsite emergency planning requirements are nolonger necessary.

(MF3835)

RAI-00610 CFR SONGS Request Wording Past Precedent Wording50.47(b)(10)

A range of protective actions has A range of protective actions has beendeeloped for the plume exposure pathway EPZ developed for the plume exposure pathway EPZfor emergency workers and the public. in for emergency workers and the public. Indeveloping thus range- of acotions, consideration developing this range of actions, consideration has been given to evacuation, sheltering, and as has been given to evacuation, sheltering, and asa supplement to these,the prolphelactic.

use of a supplement to thesc,the prOphelactic use ofpotssumiieid (I),asapf~piae.petassiumed4Ke(K),as apffwprate.

by applicants and licensees.

Licensees sha by applicants and licensees.

Licensees shlupdate the evacuation time estimates on-a update the evacuation time estimates on-aperiodic basis. Guidelines for the choice of periodic.

basis. Guidelines for the choice ofprotec~tive actions durn an emergency, protective actions during an emergency, conslistent with Federal guidance, are developed consistent with Federal guidance, are developed and in place, and protective actions forVthe and in place, and protective acItions for thingstion exposure pathway E PZ appropriate to i ngestion exposure pathw~ay EPZ appropriate tothe lcale have been developed, the locale have been developed.

Page 5 Although formal offsite radiological EP plans have typically been exempted for decommissioning sites, offsiteorganizations continue to be relied upon for firefighting, law enforcement, ambulance and medical services in support ofthe licensee's (onsite) emergency plan. Additionally, the licensee is responsible for control of activities in the Exclusion Area, including public access. Please provide further justification as to why this requirement would not be applicable based on the context described above.SCE Response:

The intent of the originally requested exemption was to continue to rely on State and local organizations for firefighting, law enforcement, ambulance, and medical services as needed for events at the site without the need for theseorganizations to provide formal offsite radiological emergency response.

Agreements have been executed with offsiteorganizations, and will be modified as necessary to reflect the proposed Permanently Defueled Emergency Plan, toprovide for support of the SONGS Emergency Plan in the form of Letters of Agreement (LOA). The LOAs will continue tobe required per 10 CFR 50.47(b)(3) and applicable details are provided as Appendix 3 of the SONGS proposedPermanently Defueled Emergency Plan, provided as Enclosure 2 of Reference

2. Additionally, SCE will continue tocontrol activities, including public access, within the Exclusion Area Boundary in accordance with applicable regulations and the current SONGS licensing basis.SCE agrees with the revised 'past precedent' wording the NRC provided in its RAI. Therefore, SCE has revised theoriginally requested exemption for portions of 10 CFR 50.47(b)(10) as shown in the modified exemption table, Item 9.Page 6 (MF3835)

RAI-00710 CFR SONGS Request Wording Wording Based on Recent EP Rule SOCAppendix By June 23,2014 Identification of, and a By June 23,2014 Identification of, and-aE.IV.A.7 the assistance expected from desriptin-"of the assistance expected fromappropriate State, local, and Federal agencies appropriate State, local, and Federal agencieswith responsibilities for coping with emergencies, with responsibilities for coping withincluding hostile action at the site. Foe emergencies, including hostile action at thepurposes of this appendix, "hostille action"i site. For purposes of this appendix, "hostldefined as an act directed toward a nucler action" is defined as an act directed toward apower plant or its personnel that includes the nuclear power plant or its personnel thatviolent,

-f .. ,to destr q u,. ..nt. , ,-,take includes the violent force to destroyhostages, and.... r intimi.-

dat-,e t.h, e ensee to equipment, take hostages, and/or intimidate

.,.n.- an.... ..., Thi n.,..',,.u, a,,k by air-, the licensee to achieve an end. This includesland, Or water us.ing guns, explosie attack by air, land, or water using guns,projectiles, vehicles or other de.ices u 4 to explosives, projectiles, vehicles or otherdeliver destructive f.rce. devices used to deliver destructive force.Although the NRC has previously exempted decommissioning reactors from "hostile action" enhancements based on theapplicability of the new EP Rule (as stated in the Statement of Considerations),

some EP requirements for events aremaintained, such as the classification of security-based events, notification of offsite authorities, and coordination for theresponse of offsite response organizations (i.e., firefighting, medical assistance) onsite. Please revise the requested exemption accordingly or provide further justification for exemption.

SCE Response:

SCE is revising the requested exemption from Appendix E to 10 CFR Part 50, IV.A.7, consistent with the NRC RAI('Wording Based on Recent EP Rule SOC'). The modified exemption table, Item 21, provides the revised markup andprovides additional justification.

Page 7 (MF3835)

RAI-00810 CFR 50 SONGS Request Wording Wording Based on Recent EP Rule SOCAppendix By June 20, 2012, nuclear.

power reactor By June 20, 2012, nuclear power reactoE.IV.C.2 Licensees shall establish and maintain the Licensees shall establish and maintain thecapability to assess, classify, and declare an capability to assess, classify, and declare anemergency condition within 15 minutes after emergency condition within 15 minutes afterthe availability of indications to plant operators the availability of indications to plant operators that an emergency action level has been that an emergency action level has beenexceeded and shall promptly declare the exceeded and shall promptly declare theemergency condition as soon as possible emergency condition as soon as possiblefollowing identification of the appropriate following identification of the appropriate emergency classification level. Licensees shall emergency classification level. Licensees shallnot construe these criteria as a grace period to not construe these criteria as a grace period toattempt to restore plant conditions to avoid attempt to restore plant conditions to avoiddeclaring an emergency action due to an declaring an emergency action due to anemergency action level that has been exceeded.

emergency action level that has been exceeded.

Licensees shall not construe these criteria as Licensees shall not construe these criteria aspreventing implementation of response actions preventing implementation of response actionsdeemed by the licensee to be necessary tW deemed by the licensee to be necessary toprotect public health and safety provided th.t protect public health and safety provided thatany delay, .-,n d a,.,. , ,e ..... deny .... ,any delay in declaration does not deny theState and local authorities the opportunity" t State and local authorities the opportunity toi.mplement measres necessar.

y to protect implement measures necessary to protect the,_, the public health and safety. public health and safety.State and local jurisdictions may take actions as part of their comprehensive emergency response (all-hazard) planning.

Licensee actions shall not impede State and local authorities to respond to emergencies as they determine the need.Please provide specific justification for exempting this requirement or restore language consistent with revised wordingproposed.

Page 8 SCE Response:

SCE agrees that State and local jurisdictions may take actions as part of their comprehensive emergency response (all-hazards) planning.

SONGS actions will facilitate and certainly not impede State and local authorities from responding toemergencies.

The modified exemption table, Item 26, provides a revised markup of the regulation consistent with the RAI('Wording Based on Recent EP Rule SOC'), and provides additional justification.

(MF3835)

RAI-009SCE requested exemptions from the requirements in 10 CFR 50 Appendix E.IV.E.9.a and 10 CFR 50 Appendix E.IV.E.9.c as indicated below:10 CFR 50 Appendix E.IV.E.9.a Provision for the communications with contiguous State/local governments within the plume .xpos.. pathwayEPZ. Such communications shall be tested monthly.10 CFR 50 Appendix E.IV.9.E.c Provision for the communications among the nuclear power contro. l room, the onsite technical suppor center,and the emergency

.esponse facility:

and among the nuclear facility, the principle state and local emergency operations

centers, and the field assessment teams. Such communication shall be tested annually.

It appears to the NRC staff that 10 CFR 50 Appendix E.IV.E.9.c as exempted would be redundant to 10 CFR 50 AppendixE.IV.E.9.a.

Please explain what different organizations would be contacted and what different communication systemswould be tested for compliance with 10 CFR 50 Appendix E.IVE.9.c, as exempted, as opposed to the ones in 10 CFR 50,Appendix E.IV.E.9.a, as exempted.

Page 9 SCE Response:

SONGS agrees that the remaining portions of 10 CFR 50, Appendix E, Sections E.IV.E.9.c are redundant to provisions remaining in 10 CFR 50, Appendix E, Section IV.E.9.a, b, and d and therefore propose an exemption from SectionE.IV.E.9.c in its entirety.

The modified exemption table, Item 38, provides a revised markup of the regulation and providesadditional justification.

(MF3835)

RAI-Ol0Exemption of requirements to emergency planning requirements, as requested, partially depends on the ability of thelicensee to mitigate the consequences of design basis and beyond DBAs.Please describe the actions SONGS could take to mitigate the consequences of an event involving the spent fuel pool(SFP). Include in the description:

" Permanently installed equipment available to fill or spray the SFP* On-site portable equipment available to fill or spray the SFP* Off-site equipment available to fill or spray the SFP" Available water sources" Written procedures to perform the mitigation strategies and how they are maintained

" The personnel who would perform these mitigation strategies and how they are trained" How the equipment used in the mitigating strategies are stored, maintained and tested" Approximate times it would take to deliver, setup, and start delivering makeup/spray to the SFP using portableequipment

How makeup/spray could be delivered to the SFP in the event that radiation levels at the SFP prohibited entry tothe areaSCE Response:

Mitigation strategies associated with storage of irradiated fuel in spent fuel pools have been addressed through a numberof regulatory actions.

In addition to Emergency Planning guidance (NSIR/DPR-ISG-02, "Interim Staff Guidance, Page 10 Emergency Planning Exemption Requests for Decommissioning Nuclear Power Plants")

it was addressed as part of theresponse to the Security Orders following the Attacks on the World Trade Center (EA-02-026, B.5.b) which evolved into10 CFR 50.54(hh) and License Condition 2.C(26) and was readdressed as part of the response to the Fukushima Order(EA-12-049, Mitigating Strategies Order). Although the underlying rule (10 CFR 50.54 (hh)) is not applicable topermanently defueled plants and the Fukushima Orders were (for SONGS) appropriately rescinded, the current LicenseCondition 2,C(26) continues to apply and requires SONGS to maintain mitigation strategies associated with storage ofirradiated fuel in spent fuel pools.As discussed with the NRC staff during a teleconference on July 23, 2014, SCE has proposed, via the Permanently Defueled Technical Specification (PDTS) LAR (Reference 3), retention of a modified form of the current Mitigation Strategy License Condition specifically retaining the Spent Fuel Pool aspects.

The NRC Staff has not approved the PDTSor concurrent changes to the Operating License including the proposed revision to the Mitigation Strategy LicenseCondition.

Whether the current License Condition text is retained or the change to more focused text is approved, it willremain an obligation to retain appropriate capabilities and keep the NRC well-informed with regard to the associated details as required by the SONGS Commitment Management process.On January 2, 2014 (Reference 4), SCE submitted modified commitments based on the most recent changes to theSONGS detailed strategies.

The information provided in Reference 4 addresses any changes made to our commitments relating to the first 4 bullets in this RAI. In particular, they focus the commitments on technical aspects associated withmitigation of spent fuel pool related events. There were no proposed changes to our commitments relating to thefollowing 3 bullets (procedures, training or testing).

These aspects continue to be addressed as described in SCE'sMitigating Strategies License Amendment (Reference 5).The number of permanently installed flow-paths and sources will be reduced as systems are abandoned to support anappropriate plant configuration leading into active demolition.

As such changes are considered, protection of stored spentfuel remains the nuclear safety priority.

Significant plant configuration changes will continue to be docketed in accordance with the commitment management process.Bullets 8 and 9 are not explicitly addressed in the current program or Reference

4. If an excessive drain down event wasto occur and no installed equipment was available, portable equipment is housed on-site and can be set-up within 3hours. SONGS can also use fire equipment from adjacent off-site support (Camp Pendleton) in a similar time frame. AsPage 11 described in Reference 4, the SONGS strategies include options that do not require access to the spent fuel building(s) orthe refueling floors.(MF3835)

RAI-011The Executive Summary in NUREG-1 738 states, in part,... the staff's analyses and conclusions apply to decommissioning facilities with SFPs that meet the design andoperational characteristics assumed in the risk analysis.

These characteristics are identified in the study asindustry decommissioning commitments (IDCs) and staff decommissioning assumptions (SDAs). Provisions forconfirmation of these characteristics would need to be an integral part of rulemaking.

The IDCs and SDAs are listed in NUREG-1 738, Tables 4.1-1 and 4.1-2, respectively.

Please explain the extent each ofthese IDCs and SDAs will be satisfied at SONGS during the decommissioning phase, considering proposed exemptions from portions of the emergency planning requirements of 10 CFR 50.47(b),

10 CFR 50.47(c)(2) and 10 CFR Part 50,Appendix E. With respect to the seismic checklist discussed in SDA No. 6, the explanation may focus on the reducedpotential for a zirconium fire due to the delay in seeking emergency plan changes (i.e., a demonstration that the fuel hasdecayed such that it can be indefinitely cooled by natural circulation of air in its design storage configuration),

asdescribed in Item 10 of the checklist.

SCE Response:

SCE has reviewed SONGS compliance with each of the IDCs and SDAs and confirmed that the intent of each is met.The review results are documented in the UFSAR (Appendix 9A). A summary of the review is provided in the table below:Page 12 Item # DESCRIPTION SONGS ALIGNMENT IndustryDecommissioning Commitments Cask drop analyses will be performed or Single-failure proof crane will be in use to handlesingle failure-proof cranes will be in use heavy loads.1 for handling of heavy loads (i.e., phase IIof NUREG-0612 will be implemented).

Procedures and training of personnel will Emergency Plan Implementing Procedures (EPIPs)be in place to ensure that onsite and and other Mitigating Strategies procedures are in2 offsite resources can be brought to bear place and include provisions for access to onsite andduring an event. offsite resources.

Appropriate personnel are trainedon these procedures.

Procedures will be in place to establish Emergency Plan Implementing Procedures providecommunication between onsite and communication protocols and practices.

3 offsite organizations during severeweather and seismic events.An offsite resource plan will be Mitigation Strategy Procedures address portabledeveloped which will include access to equipment available on-site and off-site.

Theportable pumps and emergency power Emergency Plan Implementing Procedures addressto supplement onsite resources.

The other off-site sources.4 plan would principally identifyorganizations or suppliers where offsiteresources could be obtained in a timelymanner.Page 13 Item # DESCRIPTION SONGS ALIGNMENT SFP instrumentation will include Spent Fuel Pool Level Alarms, as well asreadouts and alarms in the control room Temperature and Radiation Level indication, are(or where personnel are stationed) for available in the Main Control Room and will be5 SFP temperature, water level, and area maintained available in the new Command Center.radiation levels. Additionally, while there is no SFP level indication inthe Main Control Room, SFP level indication is will beavailable in the new Command Center.SFP seals that could cause leakage Seals are located on gates which are at least two (2)leading to fuel uncovery in the event of feet above fuel stored in rack modules.

The design ofseal failure shall be self-limiting to the seals provides further assurance of their reliability leakage or otherwise engineered so that through redundant pressurization systems and otherdrainage could not occur. means. Local alarms would indicate less than normaloperating pressure.

Procedures or administrative controls to Such procedures or administrative controls are inreduce the likelihood of rapid drain-down place. The installed SFP cooling pumps include anti-events will include (1) prohibitions on the siphon devices which are regularly verified.

Similaruse of pumps that lack adequate siphon design features are planned for the new spent-fuel 7 protection (2) controls for pump suction pool islanding equipment (spent fuel pool cooling andand discharge points. The functionality filtration units not relying on permanent plant supportof anti-siphon devices will be periodically systems).

verified.

An onsite restoration plan will be in place SONGS Mitigation Strategies include means toto provide repair of the SFP cooling provide makeup water to the Spent Fuel Pool with orsystems or to provide access for without requiring entry to the refueling floor.8 makeup water to the SFP. The plan willprovide for remote alignment of themakeup source to the SFP withoutrequiring entry to the refuel floor.Page 14 Item # DESCRIPTION SONGS ALIGNMENT Procedures will be in place to control SFP operations that have the potential to rapidlySFP operations that have the potential to decrease SFP inventory are governed by therapidly decrease SFP inventory.

These administrative controls described in procedures administrative controls may require S023-3-2.11, "Spent Fuel Pool Operations,"

andadditional operations or management S023-3-2.11.1 "SFP Level Change and Purification review, management physical presence Cross-Tie Operations."

for designated operations oradministrative limitations such asrestrictions on heavy load movements.

Routine testing of the alternative fuel Normal makeup to the spent fuel pools is from thepool makeup system components will be Plant Makeup Water Storage Tank through a primaryperformed and administrative controls makeup water pump at a rate of 150 gal/min.for equipment out of service will be Makeup may also be provided by two electric-driven implemented to provide added fire pumps and one diesel-driven fire pump that canassurance that the components would supply makeup water to the SFP via the Fire Waterbe available, if needed. system. Administrative controls for thesecomponents, including surveillance requirements, 10 limits on out-of-service time, and compensatory measures for out-of-service components, arecontained in the SONGS Decommissioning FireProtection Program.Page 15 Item # DESCRIPTION SONGS ALIGNMENT StaffDecommissioning Assumptions Licensee's SFP cooling design will be at SONGS Mitigation Strategies do not rely solely on fireleast as capable as that assumed in the pumps. Sufficient redundancy and diversity are andrisk assessment, including will be provided through multiple sources asinstrumentation.

Licensees will have at described in a letter to the NRC dated 1/2/20141 least one motor-driven and one diesel- (ADAMS Accession

ML14007A164).

From a risk-driven fire pump capable of delivering informed perspective it is important to note that poolinventory to the SFP. cooling is not required and even loss of inventory does not have significant consequences based on thecurrent level of decay heat production.

Walk-downs of SFP systems will be Procedures will be revised to ensure that walk-downs performed at least once per shift by the and patrols are periodically (no less than once a shift)operators.

Procedures will be developed performed.

for and employed by the operators to2 provide guidance on the capability and Mitigating strategy procedures provide the necessary availability of onsite and offsite inventory guidance.

makeup sources and time available toinitiate these sources for various loss ofcooling or inventory events.Page 16 Item #DESCRIPTION SONGS ALIGNMENT Item # DESCRIPTION SONGS ALIGNMENT Control room instrumentation thatmonitors SFP temperature and waterlevel will directly measure theparameters involved.

Levelinstrumentation will provide alarms atlevels associated with calling in offsiteresources and with declaring anemergency.

3Level (alarm only) and temperature instrumentation that is based on direct measurement of the relevantparameters is currently provided in the Main ControlRoom and will be available in the Command Center.While SFP level is not associated with an Emergency Action Level in the SONGS proposed Permanently Defueled EALs (currently under NRC review),

aSpent Fuel Pool High Temperature alarm is currently available in the Main Control Room to alert personnel if temperature approaches the proposed EAL PD-SU1 limit of 1400F.Licensee determines that there are no There are no such drain paths in the SONGS Units 2drain paths in the SFP that could lower or 3 Spent Fuel Pools. Level recovery is the focus ofthe pool level (by draining, suctioning, or the Spent Fuel Pool Mitigating Strategies and4 pumping) more than 15 feet below the includes on-site and off-site options.normal pool operating level and thatlicensee must initiate recovery usingoffsite sources.Load drop consequence analysis will be SONGS utilizes single-failure proof cranes for suchperformed for facilities with non-single loads.failure-proof systems.

The analyses andany mitigative actions necessary topreclude catastrophic damage to theSFP that would lead to a rapid pooldraining would be sufficient todemonstrate that there is high enoughconfidence in the facilities ability towithstand a heavy load drop.Page 17 ltem# DESCRI PTION SONGS ALIGNMENT Item #DESCRIPTION SONGS ALIGNMENT Each decommissioning plant willsuccessfully complete the seismicchecklist provided in Appendix 2B to thisstudy. If the checklist cannot besuccessfully completed, thedecommissioning plant will perform aplant specific seismic risk assessment ofthe SFP and demonstrate that SFPseismically induced structural failure andrapid loss of inventory is less than thegeneric bounding estimates provided inthis study (lx1 0-5 per year including non-seismic events).6SONGS thermal hydraulic analyses demonstrate thateven under the conditions described in the InterimStaff Guidance for Emergency Planning Exemption Requests (rapid drain and adiabatic heat-up) thehottest fuel assembly pins will not exceed 900C forover 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . Further, the maximum temperature isless than 565C when air-cooling is credited.

Seeinformation following this table for a summary of theair-cooled calculations.

Based on this demonstration that the fuel hasdecayed such that it can be indefinitely cooled bynatural circulation of air, SCE has not performed theseismic checklist.

Licensees will maintain a program to Soluble boron concentration, not Boraflex, is creditedprovide surveillance and monitoring of for reactivity control in the SONGS Units 2 or 3 spent7 Boraflex in high-density spent fuel racks fuel pools.until such time as spent fuel is no longerstored in these high-density racks.Air-cooled calculation summary:Subsequent to the SONGS exemption request submittal (Reference 1), an air-cooled calculation was completed.

Thiscalculation was performed as outlined below:The purpose of the spent fuel pool air cooled calculation is to determine the date by which the spent fuel has decayedto the point that its internal heat generation rate is low enough to preclude the zirconium cladding from reaching atarget temperature following a complete loss of water inventory from the Unit 2 or Unit 3 spent fuel pool. PerNUREG/CR-6451, 5650C (1 0490F) is the lowest temperature for incipient cladding failure and thus was selected as thePage 18 appropriate target. Selection of such a low target temperature not only precludes self-sustaining zirc fire but limits anyrelease of radioactive materials.

The analysis was performed in two major steps. First, maximum quasi steady-state air temperatures throughout theUnit 2 Fuel Handling Building (FHB), including the down-comers, were determined using the GOTHIC (Version 8)computer program.

The Unit 2 FHB was modeled in this case because its pool has a greater total spent fuel heatgeneration rate. The spent fuel pool heat generation rate was calculated using the guidance provided in NUREG-0800 ASB 9-2. The maximum down-comer air temperature was then used in the second step-the calculation of themaximum temperature of the zirconium cladding using the COBRA-SFS computer program.

The COBRA-SFS modelcontains the maximum heat load (Cycle 16) assembly placed face-adjacent to two earlier discharged assemblies attheir limiting heat load. With adiabatic boundary condition applied to this three-assembly model, the configuration isequivalent to modeling the other two adjacent assemblies as also being bounding Cycle 16 assemblies.

Thisconfiguration is conservative based on the inspection of SONGS 2 and 3 spent fuel pool configurations.

Results of this analysis show that the surface temperature of the cladding in the spent fuel pools will not exceed thetarget temperature (5650C) following a total loss of water from the SFP on or after August 31, 2014, which is 31months after shutdown.

Fuel cladding remains below the critical temperature due to adequate heat rejection from thebounding assembly to the surrounding assemblies, and from the SFP to the outside, primarily via the FHB ventilation system. For comparison, NUREG/CR-6451 estimates that a decay time of about 17 months is required for arepresented PWR spent fuel pool to reach this state.Key inputs for the analysis are the same as the adiabatic case with the following additional inputs needed to supportthe GOTHIC model for the calculation of maximum down-comer temperature and input to support COBRA-SFS:

1. Spent Fuel Pool total heat generation rate for August 31, 2014 is 2.765 x 106 BTU/hr2. Plant specific parameters of the FHB, including dimensions, floor elevations, wall thicknesses, and air volume areused in the GOTHIC model.Page 19

3. FHB normal ventilation supply and exhaust subsystem, such as junction elevations, flow rates, duct lengths andsizes, and fitting dimensions are considered in the GOTHIC model.4. Thermal radiation between heat sinks and the surrounding vapor is included in the GOTHIC model. Conservative values of emissivity (0.88 for concrete and 0.22 for stainless steel) are used.5. GOTHIC model includes energy input from FHB lighting and solar radiation absorbed by the FHB walls and roof.Input to solar radiation calculation is based on ASHRAE 2009.6. Climate data (design dry-bulb temperature, mean coincident wet-bulb temperature, mean coincident dry-bulbtemperature range, and mean coincident wet-bulb temperature range) are based on ASHRAE 2009 for the vicinityof SONGS area. All values are based on 5% occurrence for the month of September (hottest month in the year)meaning that the outside temperatures predicted using these values bound 95% of the available data.7. Detailed spent fuel rack and fuel assembly

geometry, material composition, and thermal properties are included inthe GOTHIC/COBRA-SFS models. A conservative form resistance coefficient of 100 is used in the COBRA-SFS calculation.

8. In the COBRA-SFS model, the heat generation rate for the limiting Cycle 16 fuel assembly and the two identical adjacent assemblies for August 31, 2014 are 8,293 BTU/hr and 3,476 BTU/hr, respectively.

Key results are:1. Peak cladding temperature as of August 31, 2014 is 1027 OF (553 'C). This is less than the maximum allowable temperature of 1049°F (565°C).2. Maximum down-comer temperature from GOTHIC is 230 °F. A more conservative value of 235 OF is used inCOBRA-SFS calculation.

3. Down-comer temperature rise is 21 OF.Page 20 The COBRA model shows that the limiting Cycle 16 assembly outlet average air temperature is 1005 OF and the adjacentassemblies are 759 OF.(MF3835)

RAI-012The NRC staff determined that the description of the analysis of the adiabatic heatup of the hottest fuel assembly wasincomplete as presented in Section 4.1 of Enclosure 1 to the exemption request letter dated March 31, 2014. Pleaseprovide the following additional information regarding this analysis:

the information in the fuel management records (mentioned in Section 4.1.2)" the process used to determine the limiting assembly from these records, including how assembly axial and coreradial power distributions were considered

" the decay heat model used to determine the decay heat rate as a function of decay time" the source and value used for the specific heat of the uranium dioxide in the limiting assembly" since two different values of uranium dioxide density are provided (by fuel vendor),

specify which value was usedfor the hottest fuel assembly and why that application is limitingSCE Response:

1. The information in the fuel management records includes:

individual fuel assembly uranium loading; enrichment; burn-up; and, final discharge date. These data were considered in the spent fuel pool adiabatic heat-up calculation and subsequently in the air-cooled heat up calculation cases. The data are provided in Attachment A.2. The process used to determine the limiting assembly can be outlined as follows:* SONGS fuel assemblies have been discharged for at least thirty-one (31) months. For fuel assemblies with longcooling times the decay heat is primarily affected by the discharge burn-up and cooling time." Fuel assembly discharge burn-up and cooling time from the fuel management records (Attachment A) werereviewed to identify the fuel assembly with the highest fuel assembly burn-up in the cycle which has the shortestcooling time. The discharged fuel assembly with the highest fuel assembly burn-up in the cycle which has thePage 21 shortest cooling time (i.e., Unit 2, Cycle 16) is fuel assembly S2RO1 3. Unit 3 spent fuel pool heat load isbounded by Unit 2 because of the shorter length of the last operating cycle." Core radial power distribution is implicitly considered via the selection of the highest burn-up assembly.

" The assembly axial power distribution is not explicitly modeled.

It is reasonable to model the entire assembly asheating together at the assembly average decay heat because the heat generation rate is very low and thetarget heat up time is high (> 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months ). Conduction and radiative heat transfer will result in axial uniformity ofcladding temperature.

3. The decay heat generation rates for the limiting fuel assembly in the SFP are determined using the ORIGEN-ARP/ORIGEN-S modules within the SCALE 6 computer code package.

Input parameters to ORIGEN-ARP/ORIGEN-S include:

fuel type, initial uranium mass, initial U-235 enrichment, fuel assembly burn-up, specificpower, light element weights, and cooling time. Decay heat generation rates for the limiting fuel assembly in theSFP are determined for a target date of 6/12/13 and at four month increments until 6/12/15 and at subsequent sixmonth increments until 12/12/16.

Therefore, using the aforementioned fuel assembly parameters, one ORIGEN-ARP/ORIGEN-S run is made for this fuel assembly.

The ORIGEN-ARP/ORIGEN-S input files for the limiting fuelassembly model are provided in Attachment B.4. The source and value used for the specific heat of the uranium dioxide in the limiting assembly was developed asfollows.

The specific heat of uranium dioxide (U02) is calculated using Equation 2.2-1 in NUREG/CR-7024, "Material Property Correlations:

Comparisons between FRAPCOM-3.4, FRAPTRAN 1.4, and MATPRO,"

March2011. The equation is shown below.SK102 exp(O/T)

KT YK3ED exp(-ED/RT)

Tp =2[exp(O/T)_

1]2 -2RT2Page 22 Where:Cp is the specific heat in J/kg-KK1, K2, K3, are constants for U02 of 296.7 J/kg-K, 2.43x1 0-2 J/kg-K2, and 8.745x1 07 J/kge is the Einstein temperature and is 535.285 K for U02T is the temperature of the U02Y is the oxygen to metal ratioED is the activation energy for Frenkel Defects and is 1.577x1 05 J/molR is the universal gas constant 8.3143 J/mol-KThe third term in this summation is negligible at temperatures below 900 K and is ignored.

Ignoring the term isconservative because it very slightly reduces the specific heat, which reduces the heat-up time. Per Figure 2.2-1 inNUREG/CR-7024, the heat capacity of uranium is concave over the range of temperatures of this analysis (140°F/333 K and 1049 °F/838 K). A conservatively low value for specific heat for the range of temperatures considered is selected as the average of the specific heats at those two temperatures.

The specific heat for U02 iscalculated for 333K and 838 K and the average of the two values is used in the adiabatic heat-up calculation.

5. A density for uranium dioxide of 94.5% TD (Theoretical Density) is used in this analysis.

This is appropriate because use of a lower uranium density percentage results in a lower thermal mass and thus a shorter heat-uptime. The value of 94.5% TD is the lowest stack density shown in the vendor manufacturing specifications.

References

1. Letter from Thomas J. Palmisano (SCE) to Document Control Desk (NRC) dated March 31, 2014;

Subject:

DocketNos. 50-206, 50-361, 50-362, and 72-041, Emergency Planning Exemption

Request, San Onofre NuclearGenerating

Station, Units 1, 2, 3, and Independent Spent Fuel Storage Installation (ADAMS Accession

ML1 4092A332)

Page 23

2. Letter from Thomas J. Palmisano (SCE) to Document Control Desk (NRC) dated March 31, 2014;

Subject:

DocketNos. 50-206, 50-361, 50-362, and 72-041, Amendment Application Numbers 223, 267, and 252, Permanently Defueled Emergency Plan, San Onofre Nuclear Generating

Station, Units 1, 2, and 3, respectively, andIndependent Spent Fuel Storage Installation (ADAMS Accession

ML14092A314)

3. Letter from Thomas J. Palmisano, (SCE) to Document Control Desk (NRC) dated March 21, 2014;

Subject:

DocketNos. 50-361 and 50-362, Amendment Application Numbers 266 and 251, Permanently Defueled Technical Specifications, San Onofre Nuclear Generating

Station, Units 2 and 3 (ADAMS Accession

ML1 4085A1 41)4. Letter from R. St Onge (SCE) to Document Control Desk (NRC) dated January 2, 2014;

Subject:

Docket Nos. 50-361 and 50-362, Commitment Change Report, San Onofre Nuclear Generating Station (ADAMS Accession

ML14007A164)

5. Letter from N. Kalyanam (NRC) to Richard M. Rosenblum (SCE) dated July 26, 2007;

Subject:

San OnofreNuclear Generating

Station, Units 2 and 3 -Conforming License Amendments to Incorporate the Mitigation Strategies Required by Section B.5.b of Commission Order EA-02-026 (TAC Nos. MD4564 and MD4565)Page 24 Attachment ASONGS Units 2 and 3Fuel Management Records(Pages 11 through 60 of the original document) 5.0 SPENT FUEL POOL ]INVENTORY DISCHAGE AND BURNUPThe following pages list the assemblies in each spent fuel pool, along with their last irradiation date, and burnup in units of MWD/MTU.

All data in this section is from Reference 7.3.1.The Unit 2 spent fuel pool contains 1426 assemblies.

The Unit 3 spent fuel pool contains 1350 assemblies.

5.1 UNIT 2S2A001S2A002S2A004S2A011S2A016S2A017S2A021$2A022S2A024S2A025S2A033$2A034S2A035S2A037S2A038S2A043S2A044$2A050$2A055S2A059S2A066S2AT02S2AT04S28001$2B002S2B003S2B004S2B005S2B006S2B008S2B009S2B010S2B011S2B012S2B013S2B014S2B015S2B016S2BO17$2B018S2B019S2B020S2B021S2B02203/15/8608/17/9110/21/8410/21/8409/02/8909/02/8909/02/8909/02/8910/21/8410/21/8410/21/8410/21/8410/21/8410/21/8410/21/8409/02/8910/21/8410/21/8408/29/8710/21/8406/05/9310/21/8410/21/8403/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8619305.625536.915031.713876.530530.230733.230919.630890.415232.615475.015039.915285.215196.115284.515245.823935.313710.615276.421163.915207.525461.015706.714826.925712.624572.725799.824578.624466.425768.123804.324584.323587.023602.023851.924524.224578.026057.425016.425624.124990.624389.524890.124534.125693.3S28023$2B024S28025325026S2B027S2B02832BO30S2B031S28032S2B033$2B034S2B035S2B036S25037S2B038S2B039S2B04032B042S2B043S2B044S2B04532B046S2B047S25048S28049S2B051S2B054S2B05532B05632B057S25058S2B059328061$2B062S2b063825064S2B065$2B066$2B069S2807032B071S25072S2B073$2B07403/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8603/15/8624581.124993.825320.125877.625938.725934.825848.925939.425611.625074.425744.426606.625979.925313.025827.226065.925156.625340.826166.724970.026111.324937.325751.424574.524977.525032.323693.925772.324576.7.24900.724264.724259.725080.424374.1235613.925772.226169.626687.325286.224341.025945.626154.426057.524708.2S25075 03/15/86 25075.5S2B076 03/15/86 23819.6S2B077 03/15/86 24942.9S2B078 03/15/86 25372.1S25079 03/15/86 24655.7S2B080 03/15/86 26682.7S2C003 08/29/87 34566.6S2C004 08/29/87 35991.7S2C005 08/29/87 36214.2S2C006 08/29/87 32444.0S2C008 08/29/87 32490.632C009 08/29/87 33951.1$2C010 08/29/87 33646.8$2C011 08/29/87 33946.632C014 08/29/87 34316.8$2C016 08/29/87 34108.4$2C018 08/29/87 33677.4S2C021 08/29/87 33936.732C022 08/29/87 34732.632C024 08/29/87 34623.0S2C026 08/29/87 32467.132C027 08/29/87 34150.2S2C028 08/29/87 33975.1$2C030 08/29/87 33742.9S2C034 08/29/87 33712.0S2C035 08/29/87 32641.532C038 08/29/87 34401.032C101 08/29/87 36852.8S2C102 08/29/87 36896.8S2C103 08/29/87 36841.332C105 08/29/87 36880.2$2C106 08/29/87 36762.832C108 08/29/87 36779.032C201 08/29/87 35462.082C203 08/29/87 37960.932C205 08/29/87 38327.3$2C207 03/15/86 26230.832C210 08/29/87 35899.8S2C211 08/29/87 37968.232C212 08/29/87 35757.432D031 09/02/89 30178.932D043 09/02/89 30670.132D054 09/02/89 32587.9S2D101 08/29/87 27189.6Page I Iof 131RAI-012 Responge, Attachment APage Al ofA50SCE Input to Sargent & Lundy SFP Analyses S2D102S2D103S2D104S2D105S2D106$2D107S2D108$2DI09S2D110S2D111S2D112$2D113S2D114S2D115S2D116$2E007S2EO1OS2E021S2E030$2E101S2E106S2E107S2E108S2E202S2E203S2E204S2E207S2E210S2E211$2E214S2E215S2E216S2E217$2E218$2E219S2E220$2E221S2E222S2E223$2E227$2E228S2E301S2E302S2E303S2E304$2E305S2E306$2E307S2E308S2E309S2E310S2E311$2E312S2F101S2F102S2F103S2Fl04S2F10508/29/8708/29/8708/29/8708/29/8708/29/8708/29/8708/29/8708/29/8708/29/8708/29/8708/29/8708/29/8708/29/8708/29/8708/29/8709/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8909/02/8908/17/9108/17/9108/17/9108/17/9108/17/9126906.126770.526547.726757.926558.728354.928568.527233.228470.027212.628238.127228.626989.427125.326980.134728.534967.437341.037473.539215.739226.438929.938912.236755.538807.635024.735102.935487.737079.938819.434506.034455.338890.338535.838712.536794.239047 .239319.635056.138793.136735.338869.138767.138568.338412.738769.740024 .239023.939187.438845.539871.940091.139918. 941332.737115.241056.541236.841539.6S2F106S2F107S2F108S2Fill$2F207S2F20852F209S2F210S2F212S2F214S2F215S2F219S2F220$2F224S2F225$2F226S2F22752F228S2F229S2F230$2F23152F23252F23352F23552F236S2F23852F239S2F24352F244S2F248S2F25052F252S2F25352F25452F256S2F301$2F302S2F303S2F304S2F305S2F307S2F308$2F309$2F31052F311$2F31252F313$2F314S2F315S2F31652F401S2F402S2F403S2F40452F405.S2F406S2F407$2F40808/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9108/17/9141343.141243.341411.441268.744350.144394.644531.144579.541629.344373.944560.044596.841307.843450.646326.143289.746840.943412.043582.546796.847238.646710.447053.746874.943584.746137.343439.546235.646080.547186.941903.743513.643236.146866.644656.646373.945622.745770.446042.245301.745207.945338.646228.045680.546489.046408.942404.642050.842392.242276.141351.441094.741348.441391.140923.341302.841276.541242.7S2G006S2G013S2G015S2G016$2G10152G102S2G103S2G104S2G105S2G106$2G107S2G108$2G10952G110S2G111S2G112S2G202S2G204S2G20552G20652G207S2G208S2G21152G212$2G214S2G21652G21752G218S2G221$2G22752G229.$2G233$2G234S2G235$2G236S2G239S2G24052G24152G24252G24352G24452G24552G24782G24952G25152G25452G255S2G25652G301S2G302S2G30352G304$2G305S2G306S2G307$2G308S2G309S2G31006/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9302/11/9506/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9336453.037092.036455.036467.041794.041651.042176.042084.037516.037439.041981.042066.037265.041889.037682.042468.042866.042014.043597.043742.042566.046950.044138.043902.043616.042157.045733.044414.043925.0A42342. 045654 .043106.046813.046561.046531.042777.046331.043428.043985.045985.045504.045396.043289.046465.046715.043471.044222.045257.046292.046102.044703.042656.046134.044824.046636.042743.044813.043197.0SCE Input to Sargent & Lundy SFP AnalysesPage 12 of 131RAI-012 Respon"e, Attachment APage A2 of A50 S2G311S2G312S2G313S2G314S2G315S2G316S2G401S2G402$2G403S2G404S2G405S2G406$2G407S2G408S2H004S2H005S2H008S2H009S2H010S2H012S2H013S2H014S211015S2H101S2H102S2H103S2H104S2H105S2H106$2H107S2H108S2H109$2H110S2H111$2H112S2H201S2H203S2H208S2H209S2H210S2H214S2H215S2H216$2H218S2H219S2H220$2H222S2H223$2H224$2H225S2H226S2H227S2H228S2H229S2H231S2H232S2H233S2H23406/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9306/05/9302/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9511/30/9602/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9502/11/9546116.045961.042564 .046131.045133.046112.041615.041574.041189.041341.041961.040943.041094 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Input to Sargent & Lundy SFP AnalysesPage 14 of 131RAI-012 Respon'e, Attachment APage A4 of A50 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Input to Sargent & Lundy SFP AnalysesPaze 15 of 131RAI-012 Responsie, Attachment APage A5 of A50 S2P40332P404S2P40532P406S2P407S2P40832P409S2F410S2241132P41232P41332P414S2P41532P41632P417S2P41832P41932P42032P42132P422S2P42332P42432P42532P42632P42732P42832P429S2P43032P431S2P43232P43332P43432P43532P436S2P50132P50232P50332P50432P50532P50632P507S2P50832P509S2P51032P51132P51232P51332P51432P51532P51632P51732P51832P519S2P52032P52132P522S2P523S2P52401/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0611/26/0701/03/0601/03/0601/03/0601/03/0611/26/0711/26/0701/03/0601/03/0601/03/0611/26/0711/26/0701/03/0611/26/0701/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0611/26/0701/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0640438.049656.049327.048015.047954.049710.046600.049276.043136.046432.049801.040341.049198.042893.043000.040586.049032.049097.042831.042572.048859.042792.046488.049129.049328.040501.049791.047804.049828.049601.042584.049326.046501.047935.046903.048333.048320.046991.048240.048618.049067.048525.046404.047063.048333.036338.049186.048374.046612.048713.048772.049154.046635.049078.048718.049154.047120.049209.032P52532P52632P52732P52832P52932P53032P53132P532S2P533S2P53432P53532P53632P53732P53832P53932P54032P54132P54232P54332P54432QO01S2QO02S2QO03S2QO0432Q005S2Q006S2QO07S2Q008S2Q009S2QO10S2QO11S2Q01232Q01332Q014S2QO15S2QO16S2Q101S2Q102S2Q103$2Q104S2Q105S2Q10632Q107S2Q10832Q401S2Q402S2Q40332Q404S2Q405$2Q406S2Q40732Q408S2Q409S2Q410S2Q411S2Q41232Q413S2Q41401/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0601/03/0611/26/0709/27/0909/27/0911/26/0711/26/0709/27/0911/26/0709/27/0911/26/0711/26/0711/26/0711/26/0711/26/0711/26/0709/27/0911/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0709/27/0909/27/0911/26/0709/27/0911/26/0711/26/0709/27/0909/27/0909/27/0911/26/0709/27/0909/27/0911/26/0711/26/0748389.048262.049213.035785.049077.036003.049124.036226.049128.049464.049207.036391.049301.036173.035991.049211.049370.046694.036030.049229.033348.050258.050552.035107.035164.048623.035165.049994.035115.038553.033321.033521.038507.038702.050336.038479.040656.041126.040972.041004.041163.041202.041081.040832.049634.050117.048387.049353.048424.048370.049323.050065.050188.048287.049554.050257.048390.048300.0S2Q415S2Q41632Q417S2Q418S2Q419S2Q42032Q501S2Q50232Q503$2Q504S2Q50532Q50632Q507S2Q508S2Q509S2Q510$2Q511S2Q512S2Q513S2Q514S2Q515S2Q516S2Q517S2Q518S2Q519S2Q520S2Q52.1S2Q52232Q523S2Q524$2Q525S2Q526S2Q52732Q528S2Q52932Q530S2Q531S2Q532S2Q53332Q534S2Q535S2Q536S2Q53732Q538S2Q539S2Q540S2Q541S2Q542S2Q54332Q544S2Q545S2Q546S2Q547S2Q548S2Q549S2Q550S2Q551S2Q55211/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0711/26/0748453.048336.048468.048562.048477.048536.048601.046643.048549.046701.046796.046508.048424.048410.048449.046696.048491.047238.046681.048356.047138.048616.044779.044652.047271.044748.036458.048517.036117.036145.046598.048580.048255.046628.048506.048605.046663.036355.048579.046838.044679.046822.036368.048516.036637.046896.048599.046817.048634.046656.048259.048678.036208.036226.046683.047210.048649.048666.0SCE Input to Sargent & Lundy SFP AnalysesPage 16 of 131RAI-012 Respon"e, Attachment APage A6 of A50 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Input to Sargent & Lundy SFP AnalysesPage 17 of 131RAI-012 Respong"e, Attachment APage A7 of A50 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Input to Sargent & Lundy SFP AnalysesPage 18 of 131RAI-012 Response, Attachment APage A8 of A50

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Input to Sargent & Lundy SFP AnalysesPage 19 of 131RAI-012 Respongle, Attachment APage A9 of A50 5.2 UNIT 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Input to Sargent & Lundy SFP AnalysesPage 20 of 131RAI-012 Response, Attachment APage A10 of A50 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Input to Sargent & Lundy SFP AnalysesPage 21 of 131RAI-012 Response, Attachment APage All of A50 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Input to Sargent & Lundy SFP AnalysesPa-e 23 of 131RAI-012 Respond'e, Attachment APage A13 of A50 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Input to Sargent & Lundy SFP AnalysesPage 24 of 131RAI-012 Response, Attachment APage A14 of A50 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Input to Sargent & Lundy SFP AnalysesPage 25 of 131RAI-012 Response, Attachment APage A15 of A50 S3Q551S3Q552S3RO01S3R002S3R003S3RO04$3R005$3R006S3R007S3R008S3R101S3RI02$3R103S3R104$3R105S3R106S3R107S3RI08S3R301S3R302S3R303S3R304S3R305M3R306S3R307S3R308S3R309S3R310S3R311$3R312S3R401S3R402S3R403S3R404S3R405S3R406S3R407S3R408S3R409M3R410S3R411S3R412S3R501S3R502S3R503S3R504S3R505S3R506S3R507S3R508S3R509S3R510S3R511S3R512S3R513S3R514S3R515S3R51610/12/0810/12/0810/10/1010/10/1010/10/1010/10/1010/10/1010/10/1010/10/1010/10/10-10/10/10 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034731.035548.035546.035224.039466.039530.039762.039632.039782.039781.039821.039728.038634.038391.038687.038473.033773.033491.033963.034183.039047.039112.033482.038991.034348.033362.039017.035622.033664.033753.034010.033482.035184.033831.033700.032793.0SCE Input to Sargent & Lundy SFP AnalysesPage 26 of 131RAI-012 Response, Attachment APage A16 of A50 S3S521S3S522S3S523$33524S3S525$33526S3S527S3S528S3S529S3S530$33531S33532$33533$33534$33535S3S536S3S53733S538$33539$33540$33541$33542S3S543S3S544$3S545$33546S3S547S38548$33549$33550S33551S3S552S3S553$3S554$33555S3S556S3TO01$3T002S3T003S3T004S3TI01S3TI02$3TI03S3T104S3T201S3T202S3T203S3T20401/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/ 1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1239071.033801.034018.033974.037617.033035.041254.035090.041289.034099.039255.038995.035271.041142.041209.032859.033224.034223.035440.035221.035582.038954.034491.040526.035574.033336.037772.040663.040703.040677.037725.040371.040621.040355.040614.037692.09503.09439.09655.09730.012458.012369.012467.012390.011823.012009.011956.011865.0S3T205S3T206S3T207S3T208$3T301S3T302$3T303S3T304S3T305S3T306$3T307S3T308S3T309S3T310$3T311S3T312S3T401S3T402S3T403$3T404$3T405S3T406$3T407S3T408$3T409S3T410S3T411S3T412$3T501S3T502S3T503S3T504$3T505S3T50683T507S3T508S3T509$3T510$3T511S3T512S3T513$3T514$3T515$3T516S3T517S3T518S3T519$3T52001/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1211888.011900.011902.011910.015912.011410.011277.011083.011464.011414.011736.011913.016000.015899.015886.011412.015089.015010.015044.015980.015093.015108.014987.014999.015879.016047.015989.015021.016358.015692.016319.014565.016097.013280.014574.016234.014574.016173.016134 .016232.013526.016227. 016299.016264.013181.013599.014448.014365.0S3T521S3T522S3T523$3T524S3T525S3T526S3T527S3T528S3T52983T530S3T531S3T532S3T533$3T534S3T535S3T536S3T537S3T538S3T539S3T540S3T541$3T542S3T543S3T544S3T545$3T546S3T547S3T548S3T549S3T550S3T551S3T552$3T553$3T554S3T555$3T556$3T55733T558S3T559S3T560S3T601S3T602S3T603S3T604S3T701S3T702S3T703S3T70401/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1201/31/1214591.016232.016123.014651.016203.016606.015742.016248.014468 016528.016386.014445.015591.014639.015523.015751.015972.016103.015990.013606.015682.013684 .016080.016022.015608.016000.015888.016195.015761.015681.016416.016165.015425.016357.013427.015504.015789.013644.014734.014513.09329.09331.09568.09666.013461.013490.013504.013512.0SCE Input to Sargent & Lundy SFP AnalysesPage 27 of 131RAI-012 Response, Attachment APage A17 of A50 6.0 SPENT FUEL POOL INVENTORY URANIUM LOADINGThe following pages list the assemblies in each spent fuel pool with their initial total Uraniumloading in grams, and initial U-235 loading in grams. All data in this section was obtained byrunning an 'initial weight report' in Tracworks (Reference 7.3.2).6.1 UNIT 2Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g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nput to Sargent & Lundy SFP AnalysesPage 28 of 131RAI-012 Response, Attachment APage A18 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S2B054S2B05552B056S2B057S2B058S2B059S2B061S2B062S2B06352B064S2B065S2B066S2B069S2B070S21B071S2B072S2B073S2B074S21075S2B076S2B077S2B078S21B07952B080S2C003S2C00452C005S2C006S2C008S2C009S2C010S2CO11$2C014$2C01652CO18$2C021S2C022S2C024$2C026S2C027S2C02852C030$2C034S2C0353998593987223987313987303988733993033985863994283995543980063976683977563982533997263984323982463970613977743983053991993972873978453973563978824259514269604280374280084282794281994278914279034275674285174288244279964283764277954283064274054267144271464273354275759574951495199533954095709524956595559514949394589538958694999490944095259481955795109499951494741228912318123451235112362123581234812351123381236212364123521235212339123491231912301123231229212299S2C038S2C101$2C102S2C103S2C10552C106S2C108S2C201S2C203S2C205$2C207S2C210$2C211S2C212$2D031S2D043S2D054S2D1O1S2D102S2D103S2D104S2D105S2D106S2D107S2D108S2D109S2D11O52D111$2D112S2D113S2D114$2D115S2D116S2E007S2EO1O52E021S2E030S2E101S2E106S2E107S2E108S2E202S2E203$2E2044280074064484058204054274058154053934055803986173991373987713972253989123976193975994263084254774269094259384265054270064268214275214269784261874257134259824255904259424264694260484270714277704279644250714255464263974261944189834187724186764179934114864113414128361237011711116921168311700116841169311487115141149311500115071146711462147541479214774116691172311750117391177811730116771166411672116611167111685116741170011717117231660316606166571665116342163591633416317138591384713901SCE Input to Sargent & Lundy SFP AnalysesPage 29 of 131RAI-01 2 Response, Attachment APage A19 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S2E20752E21052E211S2E214S2E21552E216S2E217S2E218S2E219S2E220S2E221S2E222S2E223S2E227$2E228S2E30152E302S2E303S2E304S2E305S2E306S2E307S2E308S2E309S2E310S2E311S2E312$2F101S2F102S2F103S2F104S2F105S2F106S2F107S2F108S2FillS2F207S2F208S2F20952F210S2F212521F214S2F215S2F2194126784104084114764108264102564102844109954111764110234123134110684111734127254104364112273979663984783974903977753980973961873974503978663972983964873959003967474147774134274143734141794145994171994146294160974145364007624006694014384005864000244003674001344007081390113821138521383513814138141384213844138391387913842138441389213825138531339113415133771338813402133311337713389133691334013323133581643316365164281642116438165281643916484164301583215835158901584115801158331583115846S2F220S2F224S2F225S2F226S2F227S2F228S2F22952F230S2F231S2F232S2F233S2F235S2F236S2F23852F239S2F243S2F244S2F248$2F25052F252S2F253S2F254S2F256S2F301S2F302S2F303S2F304$2F305S2F307$2F308S2F309S2F310S2F311S2F312S2F313S2F314521F315S2F31652F401S2F402S2F403S2F404$2F405S2F4063992583968933990813985513986663984893985303991743991453990293987023988573983993993193984133992663992043989033995723982733983513984234009803975283982563974123973313989913983083987563979043983303975783979563968603982803979033979963996374003353994733977563978613979841580315701157901574815752157411574315769157671576415754157561574415786157471579015790157711580015747157511575515853160191605016018160121610016068160901604316068160361604515275153381531615315158141584515799157211572515730SCE Input to Sargent & Lundy SFP AnalysesPage 30 of 131RAI-012 Response, Attachment APage A20 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S2F407$2F408S2G006S2G013S2G015S2G016S2G101S2G102S2G103$2G10452G105$2G106$2G107S2G108$2G109S2G11OS2G111$2G112S2G202$2G204S2G205S2G206S2G207S2G208S2G211S2G212$2G214$2G216S2G217S2G21852G22152G227$2G22952G233S2G234S2G23552G236S2G239S2G240$2G24152G242S2G24352G244S2G245398188397587428365428146427584427941413685414567414192414274415381414377414438414092414780414275415042414865399432399088398442398445399614399874400654400510400085399409399067398617398977400083398457400610398639398675399329398636400233399961398707398650398957398987157501572716953169241692316910.1632216382163561637916404163991639516335164091638616404163941579515779157241574915783157881580715806157971578015757157511579115776157061579315725157131574015720157891578315745157421575815761$2G24752G249S2G251S2G254S2G255$2G25652G30152G30252G303S26304$2G305S2G306$2G30752G308S2G309$2G310S2G31152G31252G313$2G314$2G31552G316$2G40152G402S2G40352G40452G405$2G406S2G407S2G408S2H004S2H005S2H00852H009S2H010S2H012S2H013S2H014S2H015S2H1101S2H1102S21H10352H104S2H1054000433984663982233988114000423991424004533999913993724001384000064009154006564007414002683990803991323997404003104009814011424002913981153990123992353993653995123995163994194000124292454289464290844287854292344289514291284290504290144148224150004144734146174145301579515734157251574015792157621607116042160021603116029160631606016065160491601116013160361605316094161091607315726157521574015748157591575915755158181704417014170011699017029169961700816999170001645816465164461645116448SCE Input to Sargent & Lundy SFP AnalysesPage 31 of 131RAI-012 Response, Attachment APage A21 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)52H106S21H-107S21H-108521H-109S2H110S2H111S2H112S2H201S2H203S2H208S2H209S2H210S2H21452H215S2H216S2H218S2H219S2H220S2H222S2H223S2H224S2H225S2H226S2H22752H228S2H229S2H231$2H232S2H233S2H234S2H243S2H244S2H247S2H249S2H250521H251$2H253S2H254S2H255S2H256S2H301S2H302S2H303521H3044144334145284145304148234146004145654147393998303996833999773998933998434009024003094004504004754003604007564000924000823999744000483997883998623997604000093999433999643998253997543997993997333997494000413990403992833993873993293992843991863994783993693995433996081644416448164481646016451164501645715833158531586615865158621588915865158691587215867158831583215829158251583015820158211581815829158211584015836158221583615835158351585015821158311583915831158301583516108161041611116114S2H305S2H306S2H307S2H308S2H309S2H310S2H311S2H312$2H313S2H314S2H315S2H316S2H401S2H402S2H403S2H404S2H501S2H502S2H503S2H50452JO01S2J002S2J003S2J004S2J00552J006S2J007S2J008S2J009S2J010S21011S2J012$2J013S2J014S2J01552J016S2J.101S2i102S2J103S2J104S2J105S2J106S2J.107S2.11083996143997754001694003933996114001794009134011644011024009254007444007753991063990663991263990134271514268324277654276374297434297194297154297674297674304004302234302874300294303094304364305944293704295914294074294604150084149434149544149644154364148294148844150341611416120161361614516115161371616716177161741616816160161621583315832158341582916732167241675716751169821698116980169841698817041170241704217033170421704617054170071701617007170111641016414164301641116456163991640116417SCE Input to Sargent & Lundy SFP AnalysesPage 32 of 131RAI-012 Response, Attachment APage A22 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S2J109 414976 16417 S2J308 400802 16103$2J110 414919 16416 S2J309 400750 16132S2JIll 414821 16411 S2J310 400903 16151S2J112 415076 16403 S2J311 401383 16166S2J202 400968 15814 $2J312 401270 16156S2J206 400987 15806 S2J313 401385 16154S2J208 401066 15813 S2J314 401410 16154S2J209 401056 15828 S2J315 401427 16155S2J211 400853 15825 S2J316 401076 16139S2J212 401047 15833 S2J401 400502 15832S2J217 400712 15825 S2J404 400589 1583552J220 399905 15804 S2J406 400489 15836S2J224 400532 15831 S2J407 400396 15842S2J225 400504 15828 S2K001 429529 16993S2J227 400389 15826 S2K002 430494 17082S2J228 400471 15828 S2K003 430686 1711052J230 400912 15853 S2KO04 430832 17095S2J231 400743 15848 S2K005 430021 17014S2J232 400668 15832 $2K006 430666 17107S2J233 400433 15817 S2K007 429692 17015S2J234 400266 15800 S2KO08, 429947 1701452J236 400464 15810 S2K011 430943 17206S2J238 400482 15816 S2K012 430353 17041S2J239 400962 15881 S2K013 429816 17050S2J241 400866 15841 $2K016 430250 17090S2J242 401044 15866 S2K102 415883 16497S2J246 401015 15847 S2K104 415629 16477S2J247 400690 15844 S2K110 416216 16480S2J248 400667 15848 S2K112 415998 16525S2J249 401261 15856 S2K201 401658 15977S2J250 400652 15851 S2K202 402149 15943S2J251 400724 15853 S2K203 401611 15956S2J252 400761 15863 S2K204 401251 15867S2J253 401196 15903 $2K205 400944 1588952J254 401307 15906 S2K206 401039 15872S2J255 401335 15909 S2K207 400962 1586552J256 401146 15897 S2K208 401090 15930S2J301 400523 16113 S2K209 401090 15923S2J302 400529 16089 S2K210 400925 15844S2J303 400742 16098 S2K211 401693 15942$2J304 400413 16090 S2K212 401238 15905S2J305 400558 16123 S2K213 401595 15948S2J306 400737 16118 $2K214 401657 1594352J307 401031 16158 S2K215 400895 15889SCE Input to Sargent & Lundy SFP Analyses Page 33 of 131RAI-012 Response, Attachment APage A23 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S2K216521K217S2K218S21K21952K220S2K22152K222S21<223S2K224S21<225S2K22652K227S21(228S21<229S21(230S2K231S21<232$2K233S2K234S21<235S2K236S2K237S21(238S21<239521(240521<241521<242S21<243S21<244S21<245S21(24652K247S21<248S21<249521<250521(251S21(252$2K253S21<254521(255S2K256521<307521<308521<309400933400676400996401003401092401145401475400835402190401938401489401452402012401055401244401756400983401046402131401812401872401261401887401897401298401056400611401780402374401944402019401641401285401765399634400819401955401591401535401769401845400969400720401594158071580415858158751588415906159271585916000159371582415890159501590115933159241586715867159571596215948159391593615962158911590615842160081599215988159741596415929159581581115882159461594515962160191600016068160901621052K312S2K31352K314S21<315$2K316521<401S21L006S2L007$2L008S2L015S2L201S2L202S2L203S2L204S2L205S2L206S2L207S2L20852L209S2L210S2L211S2L212S2L30152L302S2L303S2L304S2L305S2L306S2L307S2L308S2L309S2L310S2L311S2L312S2L313S2L314521L315S2L316S2L317S2L318S2L319S2L320S2L401S2L4024004694010864008824013984012514015374406464408334409964409924384544381194387454385364390054390784384524382844380924384464388204385984378624379954381934383384383874377404382664383634385994381444382704385334378734382644378874376834377754378874384274379714370314366181614916058161251618516081159401976819778197901980519537194991953719521195531953819487194431938219434195071949819439194931952019523195211944819452194531942019411194471947619443194491943019422194241942519439194571933619302SCE Input to Sargent & Lundy SFP AnalysesPage 34 of 131RAI-012 Response, Attachment APage A24 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S21L404S2L405S2L406521L407S2L408S21L409521L410521L411521L412S2L413S2L414S2L415S2L416521L417521L418S2L419S2L420521L421S2L422S2L423S2L424S21L425S21L426S21L427$2L429S2L430S2L432S2L433S2L434521L435521L436S2M001S2M002S2M003S2M004S2MOO5S2M006S2M007$2M008S2M009S2M010S2MO11S2M012S2M0134371624368784364864364824367664369024370064368154372654369054372544374594375064365324371624372344360724366344360964365904362104366324371574367104369694371674369764377414376054369614369084386294390524394224400024401874393824399764400684391794396874395444394004395911937919305192891930219356193691935619339193431931919343193681938519346193651938119326193981932719317192961939619334192951940219402193681933019351193651936919020190561907919075190781906419091190921906419076190681906419064S2M014S2M015S2M016$2M20152M20252M20352M20452M205$2M20652M207$2M208S2M301S2M302$2M303S2M304S2M305S2M306$2M307S2M31152M312$2M313S2M314$2M315$2M316$2M501S2M504S2M505S2M506S2M507$2M508$2M509S2M510$2M512S2M513S2M514S2M515S2M51652M51752M519S2M52052M521S2M522$2M523S2M5244399954397424400404381724381674379714377154374774378774372554373524368024365284373184361214366714370314364124364054368084373084370454368544369614346964355904364634368684373694366824364024360344355094357104352684346734352224361494362634348154349464363714362704359191912319104191051879818798187801876518809188301879818816188251880018813187061874418737187931872618771187951883018822188021863318668186981868718729187361872918665186201862818644186271864818689186921860118591187101874318668SCE Input to Sargent & Lundy SFP AnalysesPage 35 of 131RAI-01 2 Response, Attachment APage A25 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)$2M525$2M526S2M527S2M528S2M529S2M531S2M532S2M533S2M534S2M535S2M536S2M537S2M538S2M539S2M540S2M541S2M542S2M544S2M545$2M546S2M547S2M548S2M549$2M55052M551S2M552S2M553S2M554S2M556$2M557S2M558$2M560$2N002S2N004S2NO05S2N006S2N007S2N008S2N009$2N01052NO11S2N012M2NO13$2N0144358854350864355764363854365664355434350314367294370514368024362184364704367534363974359944360474361614358894365364369354366864361444352044363434369654370794370004368814358464376324375664354854396064402884404224389654385634378294383224385114377044371954371374384911865918601186681871818729186271859918725187391871218709186951870618705187011871218709187061870718717187081868618612186631871418724187641873918672187701877618638182921832018322182861825518213182301821918175181511814318210S2N015S2N016S2N201S2N202S2N203S2N204S2N205S2N206S21N\207S21N\208521N\209S2N210S2N211S2N212S2N213S21N214S2N21552N216S2N301S2N305S2N306S2N307$2N308S2N309S2N31052N312S2N313S2N315S2N401S2N402S2N403S2N404S2N405S2N406S2N407S2N408S2N501S2N502S2N503S2N504S2N505S2N506S2N507S2N5084389584387224371414368954360344363224363974367264363954358384358214361994362564361054364364367794366324369644358794363314364754372404367774363224367204371004368414363434358564358544349404350244354474360464366754366704346884347934349344349644353744357334354454350391825018245179521794617940179551794517982179531792917897179371793217925179481795017948179651792517931179371797017937179331794317942179431792517869178611785317847178601785517873178891779117811178071780117833178521782517800SCE Input to Sargent & Lundy SFP AnalysesPage 36 of 131RAI-012 Response, Attachment APage A26 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S2N509521N510S2N511S2N512S2N513S21N514S2N515S2N516S2N517S2N518S21N519S2N520S2N52152N522S2N523S2N524$2N525S2N526S2N527S2N528S2N529S2N530S2N531S2N532S2N533S2N534S2N535S2N536S2PO01$2P002S2P003S2P004S2P005$2P00652P007S2P008S2P00952P010R2POMIS2P012S2P013S2P014S2P01552P0164352144355884356384352504348024348884349854348294350524351534350824350624354744345264342754355884352354354654357464352694353804356804355274357264361354360244358074362464406514404814402464400484398804405324401534407374406974399634395434397974403694406004407274404261781317837178331783317808178121781417813178571784817822178031781917815177991783617823178431788017862178591784517844178551786217856178531786219833198301983419804197941984519823198671983519811197931980319847198631987319838S2P201$2P202S2P203S2P204$2P205$2P206S2P207$2P208S2P401$2P402$2P403S2P404S2P405$2P406$2P40752P408$2P409S2P410S2P411$2P412$2P413S2P414$2P415S2P41652P417S2P418$2P419S2P420S2P42152P42252P42352P424$2P425$2P426S2P427$2P42852P429$2P430S2P431$2P43252P433S2P434S2P435S2P4364373294374504375114376024379394377094376574377544375304371834371404370674372884361444363634368924365514370874371244364944367434370554374574376704380964375904378814379154375604380314376034379144366794374074371594373214363994362054367314368954376624370754369244360821949019491194761947619503194941948219488194561943819435194201944319378193721942619414194431945519419194201943419454194621946019438194471945219464194741944219462194051944419432194351942019400194291943019463194321940119372SCE Input to Sargent & Lundy SFP AnalysesPage 37 of 131RAI-012 Response, Attachment APage A27 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)$2P501S2P502S2P503S2P504S2P505$2P506$2P507$2P508S2P50952P510S2P51152P51252P51352P514$2P51552P516S2P517S2P51852P519S2P520$2P521S2P52252P523$2P52452P52552P526S2P52752P528S2P529S2P53052P531S2P532S2P533$2P534$2P535S2P536S2P537S2P538S2P539S2P540S2P541S2P542S2P543S2P5444360524358724358124363274372854371134366384370974372734366114362064369364367454372404373674375324375154373554379624373424374214371264363274371144359964370864368634370894369404371634365834368894366914372124366334372084359054366084363224367704362354366724364184364361938619377193651939119437194461940319437194461939519377194191940219438194461944019441194291945219428194411943619387194301938219436194101942019408194161940719414194101942319404194171942619423194131940519431194641941719434S2Q001S2Q00252Q003$2Q00452Q005S2QO06S2QO07S2Q008S2Q009S2QO1152(2011$2Q012S2Q013$2Q014$2Q01552Q016S2Q101S2Q10252Q10352Q104S2Q105$2Q106$2Q107$2Q108S2Q40152Q402S2Q403S2Q40452Q405$2Q40652Q40752Q40852Q40952Q41052Q411S2Q41252Q413$2Q414S2Q41552Q41652Q417S2Q418S2Q419S2Q4204413504415314413954405074406054409494405264405584407074403284414164405594403084398754408754402904383774382584385214381774383844381164381184385154369184372974366814366924368564366824371234373574372784372654375234375314372324372614373124375524373974369974368584368261973619744197391966219666197041970119705197041965719736197041967019643197111967319288192831929319283193221928719319193301923419245192271922919219192101923219241192371922719232192451920219204192001921319209192011920019195SCE Input to Sargent & Lundy SFP AnalysesPage 38 of 131RAI-012 Response, Attachment APage A28 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)$2Q501S2Q502$2Q503S2Q504S2Q505S2Q506$2Q507$2Q508520509$2Q510S2Q51152Q51252051352Q51452Q515$2Q51652Q51752Q51852Q519S2Q520S2Q521S2Q52252Q52352Q524S2Q52552Q526S2Q527$2Q528S2Q52952Q53052Q53152Q53252053352Q534$2Q535S2Q536$2Q53752Q53852Q53952054052Q541$2Q542$2Q543S2Q544436188436508436519436291436304436614436649436535436614436690436376436221436175436150436118436298435980436030435524435635436304435882436586436544436068436014436665436162436702436886436588436643436425436497436601436684436851436420436609436392436476436282436657436708192061921819209191951919619217191851918419203192181918119174191881918319169191821917519177191651917419235192041924119239191911920019183191901920119197192181922119203192151918119195192231919919225192161921519192192141921752Q545S2Q54652Q54752Q54852Q54952Q55052Q55152Q55252Q55352Q55452Q55552Q556$2R001S2R002S2RO03S2R004S2R005S2R006S2R007S2R008S2R009S2R010S2R011S2R012S2R013S2R014S2R015S2R016S2R101S2R102S2R103S2R10452R105$2R10652R107S2R108$2R401$2R402S2R403S2R40452R405S2R40652R407S2R4084359704359304373644372974360254355574365544366974367964368154364714362854404954404864403534407324406784401014408994408044403894402184398074403104403334400344400484404024393124399544400184396054386054385604391454385864371774369794371604376404372614374744371134373041918819183192601924919191191671920719213192151921519216192111983619823198351985119819198251985419845198341986619851198841987919861198721988619549195851958319562195071952419520195251943819427194251944019415194351941219430SCE Input to Sargent & Lundy SFP AnalysesPage 39 of 131RAI-O012

Response, Attachment APage A29 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S2R409$2R410S2R411S2R412521R501S2R502$2R503S2R504$2R505S2R50652R507S2R508$2R509S2R510S2R511S2R51252R513S2R514S2R51552R516S2R517S2R518S2R519S2R520S2R521$2R522S2R523S2R524S2R525$2R526S2R527$2R528S2R529$2R530S2R531S21R532S2R533S2R534S2R535$2R536S2R537S2R538S2R53952R5404373674372824372524371454376554377044375404376224373224370604370074365494363424362874361234363694368724363024365944363884366384365064368234364564365504363034371374375254373634371154369414372124370844371384368154361744362784365074367704367344370184371794365364365491941819414194211942519453194521943819445194401942919445194121939419390193811939519423194051941519409194221941019420194011941019400194561947319466194301942619468194491945119431193861939519412194231942319430194361940719408$2R541$2R542S2R543S2R544S2R545S2R546S2R547$2R548S2R549S2R550521R551S2R552$2R553$2R554S2R555S2R556S2R55752R558S2R559S2R560S2R561$2R562$2R563S2R564S2SO0152500252S003525004525005$25006525007M2S008S2SO1525102525103525104525105S2S10652510752S10852S30152S30252S303S253044375414372334374334376254371824362474376864370904372714381224375904366224363454363464361954366484369254377174368374365924369624366584367024368454412924409744411904409384411274411374415654407474388744391924392994393144389104390044388384388244373814376844376524377191943019421194271943519417193761942219392194051945219449194191939019397193991938219371194091936519377194271938919395193981993519954199631995119910199041992419902195591959119595196051958719598195891958919496194941950419514SCE Input to Sargent & Lundy SFP AnalysesPage 40 of 131RAI-012 Response, Attachment APage A30 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S25305S25306525307S25308525401S25402525403525404S25405S2S406S2S407S2S408S25409525410.525411525412525413525414525415525416525501525502525503525504525505525506525507$2550852550952S510S2S51152551252551352S514S25515525516S2S517S25518525519525520525521S255225255235255244376754378294376644373744370714371484370014371234371124372964373744374944377074376524373994371494373084373054373674370604374564372704372384372334372504373014376444379364379504377934374524376664374164375834374904376204372954371044376874382094382234376794377914377881950519509194931949519435194391943019432194141941419434194421946119448194291941919445194301944319440194681946119459194431944619450194711948019479194711944719472194571946619463194511943919429194761948619475194761947919477S2S525$25526525527525528525529S2553052553152S532S25533S25534525535525536525537S2S538S2S539525540S2S54152S542S2S543S25544S2S545S2S546S2S547S25548S2S549S2S550525551S2S552525553S25554S25555525556$25557525558S25559525560525561525562S25563525564S2TO0152T002$2T003S2TO044378734377454371294379294375854375834374614369584370244369404371164371654377264374194375874368214373294371464370604373404372844368484369074377614368144368674370564377214377994379684371084370674371184370384370914370444370734370844369484371584403314401114397114399411948019468194321946719450194511945519423194271942419444194451947419458194491939319419194221944619469194721943119440194641943419440194461944919450194611944819448194421943619446194371944719433194021943718564185361850918517SCE Input to Sargent & Lundy SFP AnalysesPage 41 of 131RAI-012 Response, Attachment APage A31 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S2T201$2T202S2T20352T20452T301S2T302S2T303S2T304S2T305S2T306S2T307S2T308S2T309S2T310S2T311S2T312$2T313S2T314S2T315S2T316S2T317S2T318S2T319S2T320S2T321S2T322S2T323S2T324S2T401S2T402S2T403S2T404S2T405S2T406S2T407S2T408S2T501S2T502$2T503S2T504S2T505$2T506S2T50752T5084382494381714380144381484379134375374376344376484377884379534377324383044381434376304381274383484379414382264384074384354380234379594378544379074374744376194375644379024365564367284371664371574373754373464372834373524366434364954365204362364362114362504362244360391824018243182421824318197181791817218170181931822018176182351823618206182281822718204182171823818230182091820718197182041819518198181911819818062181041815118140181161813718132181371807818067180461807718091180921807518052S2T509S2T510S2T511S2T51252T51352T514S2T515S2T516S2T517S2T51852T519S2T520S2T521S2T522S2T523S2T52452T525S2T526S2T527$2T528S2T529S2T530S2T531$2T532S2T533S2T534S2T535S2T536$2T537S2T538$2T539S2T54052T541S2T542S2T543$2T544$2T545S2T546S2T547S2T548S2T549S2T550S2T55152T5524360434367944364904367344368594363294359614368344365364366454373804371034365474375384374994372374368594367444367794367434369034368664371694366554368134372634369174367574373354368864366984366514364764365204367904368194366494365034365084366304372544373264374964372331808018114180711808818098180791807818111181071811518131181121807618147181271812918087180831809518088181041811318093180951812318138181461816518136181511816518153181131809018102180961809818098181011814318103181241813518104SCE Input to Sargent & Lundy SFP AnalysesPage 42 of 131RAI-012 Response, Attachment APage A32 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S2T553$2T554S2T555$2T556S2T557S2T558S2T559S2T560S2TA01S2TA02S2TA03S2TA04S2TA05S2TA0652TA07S2TA08S2U10152U102$2U103S2U104S2U10552U10652U107S2U108S2U301S2U302$2U303S2U304$2U305S2U306S2U307$2U308S2U309S2U310S2U311$2U312S2U313S2U314S2U315S2U316S2U401S2U402S2U403S2U4044372944372214369164367514365014370864372834371794428384429784430424431754419074425504421494423234381834374764375154374724379504378864383474380474366494374314364774368684359904363094364204366594365054371464374424362234371614370174373434370704369594374704376324369561810218105181301813918122181661817018160186411865418661186591831818350183301834120202201762017120157201592015620197201852012120196201202014220073200732007020091200842015820186200722016320166201652016820047200842009520071S2U405S2U406S2U407S2U408S2U50152U502$2U503$2U504S2U505S2U506$2U507$2U50852U509S2U510$2U511S2U512S2U513S2U514S2U515S2U516S2U517S2U518S2U519S2U520S2U521S2U522$2U523S2U524S2U525S2U526S2U527$2U52852U529S2U530K2U531$2U532S2U533S2U534S2U535$2U536$2U53752U538S2U539S2U5404367614368984370284370274365664364144367664371724371404370654376974374864373724369434368134370454367614369124368454370204372184375324374654375524374834374204369274366034370274371084375114369894369704370944372454371624375054370184362894360494355664370464360304361522008720097200992009920086200662007520079200832007720107200972008720078200642009420056200612007120120201182012320102201072010720120201112011820104201022011520097201192013320105201202010720115201082009620036200942004420064SCE Input to Sargent & Lundy SFP AnalysesPage 43 of 131RAI-012 Response, Attachment APage A33 of A50 Assembly Total U (g) U-235 (g)S2U541S2U542S2U543S2U544S2U54552U54652U547S2U548S2U549S2U550S2U551S2U552S2U553S2U554S2U555$2U556$2U557S2U558S2U559S2U560S2UA01S2UA02S2UA03S2UA04S2UA05S2UA06S2UA07S2UA08S2UW01S2UW02S2UW03S2UW04S2UW05S2UW06S2UW07S2UW08436790436853437203437631438252437882437318436472436427436582436301436489436569436460436901437382436286436468435451435955442090442019442054442101442135441989442112442053437928437830437471437570437474437872437963438045201012010320101201562017320153201082003220062200692005620077200942006220104201712005320074200062004420385203752038720354204122037620376203822020520204201792018720180201742017820182SCE Input to Sargent & Lundy SFP AnalysesPage 44 of 131RAI-012 Response, Attachment APage A34 of A50 6.2 UNIT 3Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S3A008S3A019S3A021S3A022S3A023S3A024S3A026S3A027S3A029S3A031S3A032S3A033S3A034$3A037S3A038S3A040S3A041S3A043S3A045S3A046S3A047S3A049S3A052S3A053$3A054S3A055S3A057S3A059S3A060S3A061S3A062S3A063S3A064S3A065$3A066S3A067S3A068S3A069S3A071S3B0014277364278714269794262074266344263174261714273434275294274614260154262484269404272394271624273974272494285724281424277954281994246314262654258524287284272934281424262254274674268864269634283824279184275794267474265784283924270834278213964478038802780208006801080098008800080278027799380157993803180218048802580578073804980397969799979908083804180768042807080578060808480628053804280128084801780229405S3B003S3B004S3B005S3B006S3B007S3B008S3B009S3B010S3B011S3B012S3B01353B01453B015S3B016S31018S3B019$3B0205313021S31B02253B023S3B024S3B025S3B026531027S3B028S3B029S38030S38031S3B032S3B033S3B034S3B03553B036S38037S38038S3B039S3B04053B041S310425310433958503958253960713954663967253971853975913970823974663976453976033975903977093970913987533978783977153970513971993968173975923971813974923979953973343966003979253970423967333968333975533975723980043975973959463965063967973963243958403961239389938993969380941094229431941994289433943294329434942694709439943594219434942794439433944194529436942094519429942094249437942894379434940094149422940993979403SCE Input to Sargent & Lundy SFP AnalysesPage 45 of 131RAI-012 Response, Attachment APage A35 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S3B045531046S3B047$3B048S3B049S3B050S38052S3B053S3B054S3B05553B056S3B057S38060S3B061S3B062S38063S3B067S3B068538069S3B070S3B071S3B072S3B074S3B076538077S3B078S3B079S3B080S3CO01$3C002S3C003S3C004S3C005S3C007S3C009S3CO10S3CO11S3C012$3C01353C014S3C015S3C016S3C0173965803964933968293976223953003968963963803965643972793978273969893968613969533972513975623976913985553981293980253979473982123979313998463960633994793992263963123967804255004253794255894258494259544256084254984258544262734267884262644257884287574299354293269415941394209433936694059391940794169435941494099408941494269426945294419439944194429436949793929487948293989413122761227212292123391229112301123371235512365123201233712353123661238112363S3C018S3C020S3C021S3C022S3C023S3C02453C025$3C026S3C027S3C028S3C029S3C030S3C032S3C033S3C034$3C03553C036S3C037S3C038S3C039S3C040S3C101S3C102S3C103S3C104S3C105S3C106S3C107S3C108S3C201S3C202S3C203S3C204S3C207S3C210$3C212S3C213S3C216$3D016$3D018S3D021$3D026S3D02842923642882242703242718742646142708742681242903342786642704042796142700642357742534542514842796542743242482542879042586542824740511840428640424640410440430440598940645040683339848539746039931639888439849539811939768239539639557842622242608642647642650542632612360123481234212335123431234412309123591235612347123421232412225122741229112324123221226012372123531235011694117241172211689117091168911706117221149211499114971150111489114801146811404114091473914734147491475214738SCE Input to Sargent & Lundy SFP AnalysesPage 46 of 131RAI-012 Response, Attachment APage A36 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S3D029S3D03053D031$3D032S31D034S3D036S3D04053D043S3D045$3D10453D105S3D106S3D108S3D10953D110S3D11353D114S3E001S3E003S3E004$3E005S3E007S3E008S3EO09S3E014$3E016S3E017S3E018S3E019S3E020S3E025S3E027S3E028S3E029S3E030$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$3E107S3E108$3E202S3E205S3E206S3E207$3E209S3E21153E212S3E213S3E21553E216S3E217$3E218S3E219S3E221S3E22253E22553E226S3E227S3E228S3E301S3E302S3E303S3E304S3E305S3E306S3E307$3E30853E30953E31053E31153E312S3FO02S3F00553F006S3F008S3FO10S3FO11S3F012S3F01341942141912242087441917841304741244541220741077841281841306441200741127341231941167841187341329541247541324941231041026841157341281841152939867339697039788939622239655439982539660939636239622539590439677139495042911742883942798342859842880542845642869542874116349163451642016359138761385713856138151388013879138411382313883138581386113917138621390213878138061384713902138581341313358133761330813321134411332413318133081331213347132751700016985169691697616976169721696116961SCE Input to Sargent & Lundy SFP AnalysesPage 47 of 131RAI-012 Respon"e, Attachment APage A37 of A50 Assembly Total U (g) U-235 (g)'Assembly Total U (g) U-235 (g)53FO15S3F016S3F101S3F10253F10353F10453F107S3F10853F109S3F11053FFll53F112S3F201$3F202S3F203$3F204S3F206$3F208S3F20953F21053F21153F212S3F21353F214S3F215S3F21653F218S3F219S3F220S3F221S3F222$3F224S3F225$3F226S3F227S3F228S3F231S3F23253F233S3F234S3F235$3F236$3F23942744842865541403941240641263641285941347841250641182141435941417541399439882739900839881839876039901439912039917439923639921439928339882339822739832939777139794039819839877439993540011540054939946439983239922839889139925039942639984939979739931539853139824216918169601637416316163241632916350163161627916387163831637015754157641575515753157621578015790157931579215796157741574515751157241573215750157581579415800158181577415810157911575115808158161583215830158111575615728S3F241S3F242$3F244S3F245$3F247S3F248$3F249S3F250S3F251S3F252$3F25553F256S3F301$3F302$3F303$3F304$3F305S3F306S3F307$3F308S3F30953F31053F311$3F312S3F313S3F31453F315S3F316$3F401S3F402S3F403$3F404$3F405$3F406S3F407$3F408S3GO01$3G003$3G006$3G10153G102S3G104$3G10639831839796239748639809739916339960239904439892939838839891239837039814340012440011540006140028140037540080639932039881840028339916239862439743739844439928139982539931939822539903739813939792339727939758739856239803842857242872142882141302841182541114941287315731157191570115720157571577415751157481572915746157251571616105161061610316112161201614116101160951611916097160901605416089161101608916099157201575615728157211569915721157581573016888168951689216327162531628116272SCE Input to Sargent & Lundy SFP AnalysesPage 48 of 131RAI-012 Response, Attachment APage A38 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)$3G107$3G10853G109S3G111S3G201S3G202S3G20553G206S3G209S3G210S3G211S3G214$3G215$3G216$3G217S3G220$3G221$3G224S3G225$3G226S3G227$3G228S3G229S3G230$3G232S3G233$3G234S3G235S3G236S3G239$3G241S3G244S3G245$3G248S3G251S3G252$3G254$3G301S3G302S3G303S3G304$3G305$3G30641330641226541183141196039955839971539863339895639875039874139876739873239899239901139846739797839792039796739775339749939802539864439789539799639952439844539890939811239845939893939884139802239863239911839764139797239793639694239810139876539761639860939720716296163111630716297157111571615756156921568215681156821568215692156931568815671156681567615664156531566715676156561566615719157111573115701157051573015728156991570215698156651568915670159831599615965159441603715990$3G307S3G308$3G30953G31053G311$3G312S3G313S3G314$3G31553G316S3G401$3G402$3G403$3G404$3G405$3G406$3G407$3G40853H001S3H002S3H003S3HO12S3H013S3H014$3H015$3H016S3H10353H105531H106$3H10753 H 108S3H110S3HillS3H112S3H201S3H202S3H203$3H20453H205S3H209$3H21053H211$3H21239870439724239753139788539799439821939720739772439896039823739801239840639902239754539797839797739736639855942842742862142846042715542798242805842679642704441388141381141402841385941416941401641431541426140013939926539935339992539945239897739898639941440010016052159971598016023159891602715977160081601615965157141574615766156901573515733157021571016915169231691716911169781694016910169181638316383163911638216394163891640716406158331577115829158181579915788157841581115844SCE Input to Sargent & Lundy SFP AnalysesPage 49 of 131RAI-012 Response, Attachment APage A39 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S3H213S3H214S3H216S3H217S3H218S3H220$3H221S3H222S3H223S3H226$3H230S3H232S3H237S3H239S3H244S3H248S3H249S3H250S3H251S3H252S3H253S3H254S3H255S3H256S3H301S3H302S3H303S3H30453H305S3H306S3H307S3H308S3H30953H310S3H311S3H312S3H313$3H315S3H316S3H401$3H402S3H403S3H40440020539964339922339926139900839972539898839918339893339851339924539902639937639927139921940006940025640018840020440029040006640000439977239933539886339867039961539938139887939899239891039896639916139912039938539913639852639842239834039965339962239877739816615849158241581915775157881582415789157961579515773157781577615792157801577315810158181581415813158181580815806157941577516065160821611316104160601607616073160701608416085161211610816014160481604615813158121579715700S3H405$3H406S3H407S3H40853J005S3J006S3J009S3J010S3.011S3J012$3J013S3J014S3J015S3J 106$3J201S3J202S3J203S3J204S3J212S3J215S3J216S3J217S3J219S3J221S3J223S3J225$3J227$3J228$3J230$3J233$3J234S3J236S3J238S3J239$3J247S3J248S3J249S3J251S3J253S3J25453J255S3J256S3J30139941839923639906939891743009042953342962342979742943742902542911842888142903141431440089640126240092440138040100740233740199940177440089340173439985740019340191640186740062640053740137240202040163840082940219640202140174640162740147840165140152639978340173915793157961578815782170151697916982169891697816968169711696916974163301586315880158631586315818158741587415873158771588115814157991588415883158151581815868158681587415888159041590215959158731589715866158691577116184SCE Input to Sargent & Lundy SFP AnalysesPage 50 of 131RAI-012 Response, Attachment APage A40 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S3J302S3J303S3J304S3J305S3J306S3J307S3J308S3J309S3J310S3J3.11S3J312S3J313S3J31453J315S3J316S3J401S3J402S3J403S3J404S3J405S3.406S3J407S3J408S3K105S3K106S3K107S3K108S3K109S3K110S3K111S3K112S3K201S3K202S3K204S3K205S3K207S3K208S3K209S3K211S3K212S3K213S3K217S3K21840040040046640142440180340155340133940089940068740095140121240120440108440096640025140054040016340136640123040107140171140225640174240126641658541711141707541686141648041640241611441661740129140197540209340179040243040022540148439958539953040122840280340131316101161161612816151161441612716133161231612116149161591614916138161161613015789158481586915860158871589515882159081653016562165671653016509164831646716486158941593715844158501593515807158861582315817159041593515910S3K219S3K220531K221S3K222S3K223S3K224S3K225S3K226S3K22753K228S3K229S3K230S3K231S3K232S3K233S3K23453K235S3K238S3K239S3K240S3K241S3K243S3K244S3K246S3K250S3K252S3K253S3K254S3K255S3K256S3K301S3K302S3K303S3K304S3K305S3K306S3K307S3K308S3K309531K310S3K311S3K312S3K313402411402183400238401321400783400821.40132740131840095940108340058240102340122040127140184240125140136640228340153140095740161840216640224940277940245940240240261840169840222839971840094340130840161340193540223140122840135840148939981740119740113040169840106515921159281584215890158491585115888158721585115883158381587815883159011594715902159041593315888158961589315942159051593115936159581596615881158961577916157161881620416224162421616016127161301609816150161381619816176SCE Input to Sargent & Lundy SFP AnalysesPage 51 of 131RAI-012 Response, Attachment APage A41 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S31K31453K315S3K316S3L105S3L115S3L116S3L201S3L20253L20353L204S3L205S3L206S3L207S3L208S3L301S3L30253L304$3L305$3L306S3L307S3L308S3L312S3L313S31L3143L301553L316531L401S31402S3L403S3L404S3L405S3L406$3L407S3L408S3L409S3L410531L411531L412531L413S3L414S3L415S3L416531L41740106740223640179543834143759544004143844843994243748243770543892443833543827643965143890343754643913143816943845343802143865143871943871943840043805443730543665443686143729643743443694543636443658743674343670343619343697443822143775943643643638543706543755716124162331621319929198962002119937199801990019921199501993319940200322000319966199371991819943199352000219980199861993719926199611988819898198911986619801197811980919812198211979919813198471985219828198181988519887S3L418531L419531L420S31L421531L422S3L423$3L424531L425S31L426S3L427531L428531L429S3L430531L431531L432S3L433S3L434S3L435S3L436S3L437531L438S3L439S3L440S3L441$3L442S3L443S3L444$3M001S3M005S3M007$3M008$3M009S3MO10S3MO11$3M014$3M101$3M102$3M103S3M105S3M106S3M107$3M401$3M40243827843843043744943718743882843865243779743735843801443845443788643809743758743736643763143726543829243807743639743737143708643864643852043820043671443626943661843976443933644031244063944042544069144080943966943957943927743913343901743807743883843699043697719896198951989619886199441993619898198811987419874198511986319840198571988019844198291982819773198201982319937199371990119775197221979719005189001891218923189111892918937189101863618628186311862318638186391848318484SCE Input to Sargent & Lundy SFP AnalysesPage 52 of 131RAI-012 Response, Attachment APage A42 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S3M403S3M404S3M405$3M406$3M407S3M408$3M50153M502S3M503S3M504S3M505S3M50653M50753M508S3M509$3M51053M51153M512S3M51353M51453M515S3M516S3M51753M519S3M520$3M521S3M522S3M52353M524S3M525S3M526S3M527S3M528S3M529S3M531S3M532S3M536S3M538S3M539S3M540S3M54153M542S3M5444369294374374371784371184371674372884367974366974365604364964365114367904367184372444373434371654370204373214371594358774361764374494376124366444374394365924371314376524367124365344361424359064367844369044366204362424367654361634358384368054368684353394365681848218504184781846918485184991848118481184781848518500184791848818519185351852618519185251850518456184701850518518184841850618489184981850718447184361842718407184331843418415184071845318414183911843518436183661843253M545S3M546S3M547S3M550S3M551$3M55253M553S3M556$3M557S3M55853M55953M561S3M562$3M563$3M564S3M565$3M566$3M567$3M568S3N001S3N002S3N00353N00453N005S3N006S3N007S3N008S3N009S3N010S3NO11S3N012$3N013S3N014S3N015S3N016531N\101S3N102S31N103531N\104S31N\105531N\106S3N108S3N30143657743669343700543626943730443628743572143617843615843610843546243610243652343643543631143739143694843754243775344010343984143929143998643932043943943921843921443993243986543982044026343934143942643964544017143837143841443856543890443805443875143813143714818497184931846818444184841843918420184141841818395183691842118413183941842218497184331850318519200021998819979199961998219986199821998019994199901999220006199831998219986200221970019722197341974519670197481968119648SCE Input to Sargent & Lundy SFP AnalysesPage 53 of 131RAI-012 Response, Attachment APage A43 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)53N302S3N303S3N304S3N401S3N402S3N403S3N404S3N405S3N406S3N407S3N408S3N409S3N410S3N41153N412S3N501S3N503S3N505S3N506S3N507S3N508S3N509S31N510S3N511S3N512S31N513531N514S3N516S3N517S3N518S3N519S3N520S3N521S3N522S3N523S3N524S3N525S3N526S3N527S3N528S3N52953N530S3N53143743343750243741043637043647343643043674843730043748843797843800443743643721143778043778943697143651443663443636843645343646043648543657143635743662743650843669543621943604443606643585943607643584943578243648443626043667443668543691943688243607543629743614419670196641966819539195431954219566196101962319649196311960919597196121961119603195911958819560195441955319549195581954219549195431955119557195311955419558195661955119551195771958019583195811959719595195441956119545S3N532531N533S3N534S3N535531N\536S3N53753N538S3N541S3N543S3N544S3N546S3N547S3N548S3N549S3N551S3N552S3N553$3N555S3N556S3N557S3N558S3N559S3N560S3POO1S3P002S3P00353P004S3P005S3P006$3P007S3P008S3P10153P102W3P103W3P104S3P105S3P106S3P107S3P108S3P201S3P202S3P203S3P20443593943559443591043627643620443594943545043698843530643555343563843609243548743601343519643512943501843506843466943430543461543492043529844092843997744014244088544110444112944078344014743750743753643748743765743792843770843787743759343816343767443794943810019534195181953519578195521955319520195791951619529195561958419545195751951019519195211952019538195251955419570195771943019358193781943419442194451942019377190801908219079190981912419114191211910819098190651908319089SCE Input to Sargent & Lundy SFP AnalysesPage 54 of 131RAI-012 Response, Attachment APage A44 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S3P205S3P206$3P207S3P208S3P209S3P210$3P21153P212S3P213$3P214S3P215$3P216S3P401S3P402S3P403S3P404S3P405S3P406$3P407S3P408S3P501$3P502S3P503S3P504S3P505S3P506S3P507S3P508S3P509S3P510S3P51153P512S3P513S3P514S3P51553P51653P517S3P51853P519S3P520S3P521$3P522S3P52343835043812343797543792143755643841543850543836343847943755743806943778643630243717843709943678843651643719043735543726043646943639443627643644643643943660343634243615943640743622143607043584643677943659943695343697843726843734143712143726443727343738343723119114191081909319087190681911619118191211913819053191021908618944189941900318957189471899919005190011895418949189471896318997190051898718954189791894418935189201898518979190031899719015190201902419023190451904819016S3P524$3P525$3P52653P527S3P528$3P529$3P530$3P531S3P532$3P533$3P534$3P535$3P536$3P537$3P538$3P539$3P540$3P54153P542$3P54353P544$3P545$3P546$3P547$3P548$3P54953P55053P55153P55253P553S3P55453P555$3P556S3P557$3P558S3P559$3P560S3QO01530002S3Q00353Q00453Q005$3Q00643611843711043685843700743737443695343687143584343678243688043654643569543559443574343556143541143561143581843624543599743596443599043557643570843603443581943600043582343583843583643588443604143623043629843578043633043629244033643997344008843987544010744004418923189801895419006190391897818968189561899818996189821891118923189161890818951189621895318939189711896718956189151892018960189281893518924189281893118944189681897818936189251892718953198341982319828198341983619829SCE Input to Sargent & Lundy SFP AnalysesPage 55 of 131RAI-012 Response, Attachment APage A45 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)53Q007S3Q008$3Q101S3Q10253Q10353Q104$3Q105$3Q106$3Q10753Q108$3Q20153Q202S3Q203S3Q204S3Q205S3Q20653Q20753Q208$3Q209S3Q21053Q211S3Q212$3Q213$3Q214S3Q215S3Q21653Q301$3Q30253Q30353Q30453Q305S3Q306$3Q307S3Q30853Q40153Q402S3Q403S3Q404S3Q405$3Q406530407S3Q408S3Q50144026344084843784243863043822843893043804643859643872943867243708643766243738443838343706943756043833443837343749343726443718543719243719743822043751143771243629043670343669343694943724743683443686243690043673143664543676543696543694443696443658843657343634819829198541951419532195271954019522195271953519532194791949919489195281949019512195261952819504194861948219493194951952619504195051945019471194671951819523195121950619490194121940519385194211939319382193791940019366S3Q50253Q503S3Q50453Q505S3Q506S3Q50753Q508$3Q50953Q510S3Q51153Q512$3Q51353Q51453Q515S3Q51653Q51753Q51853Q51953Q52053Q521S3Q522$3Q523$3Q524$3Q525S3Q526$3Q52753Q528$3Q52953Q53053Q53153Q53253Q53353Q53453Q535530536S3Q53753Q53853Q53953Q54053Q54153Q54253Q54353Q54443631943632743634443620843681543636043697743692643758943737143756943699243690543687343682043666243648343621343677243694843686143680743679343655743690243677243664343648343689543642643623543619643580043587743572343649343576243549443563743621743662243670743683019370193361933119321193761933119437194441946019449194601943819439194381943919450194001938719400194011939919379194221942919384194191938419384193941939919391193831936519368193711942619365193501935719413194031940519423SCE Input to Sargent & Lundy SFP AnalysesPage 56 of 131RAI-012 Response, Attachment APage A46 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S3Q545S3Q546S3Q547S3Q548S3Q549S3Q550S3Q551S3Q552S3R001S3R002S3R003$3R004S3R00553R006S3R007S3R008S3R101S3R102S31R103S3R104S3R105S3R106S3R107M3R108M3R301S3R302S3R303M3R304S3R305S3R306S3R307S3R308S3R309531R310S3R311S3R312S3R401M3R40253R403S3R404S3R405S3R406S3R40743710143690043662743668843667143674743745543715843993344007743955343852743910043880743961944047343834543871443889943848643850043861243884143875743768943807243844143822843833243854543822943717643714643698043742343654443667643693643676343681743726343754943752319428194571944519442194391940819460194462034220348203372033420366203512036220378200802010120087200562007320065200882009020015200352006120053200682007620073200372003620028200392000819932199411993519936199431995019956S3R408W3R409W3R410S3R411W3R412S3R501S3R502W3R503W3R504S3R505S3R506S3R507S3R508S3R509S3R510M3R511S3R512M3R513S3R51453R515S3R516S3R517S3R518S3R519S3R520531R521M3R522S3R523S3R524S3R525S3R526S3R527S3R528S3R529S3R530M3R531531R532S3R53353R534S3R535S3R536S31R537S31R53843717443717843708443708343732343695343704743709843713043668343714643646443658343642043672243687643646143630643624143556843542743545243626543607443626243645043675143649743664643672243650543579343647743629343515643498343565443530943477243467943539943747143569519942199531994219952199471994919934199161991819913199151990619914198961991419906199041989119899198541985019850198751986819888198881991219905199031990319890198371989319896198151983519831198181982119848198621996019889SCE Input to Sargent & Lundy SFP AnalysesPage 57 of 131RAI-012 Response, Attachment APage A47 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S3R53953R540S3R541M3R542S3R543S3R544S3R545M3R546M3R547S3R548S3R549S3R550531R551S3R552S3R553S3R554S3R555S3R556S3R55753R558S3R559S3R560S3S001535002535003$3S004S35005$3500653S007$3S00853510153510253510353510453S10553S106S35107535108535201535202$3S203535203S35204S3520543426643513343517743521843564343563143631643602743579143565643650843637343552943600743610743477743537843534443726143704743657843671644039043988544043144042143966044017344040543972543723843765543720543708643771843763943854743861543811543771543760643734743778419828198671986119850198851983119914198651989719883199071987919876198791988219835198661987719943199331991519915192291921219231192311920219222192411920618847188631885518849188691887718926189301889418873188611884918861535206S3S207S3S208$3S209535210$3521153S212535301S3S30253S30353S304535305S35306535307$3S308S3S309S35310S35311S3S312535401S3S402S35403535404535405535406S3540753S40853540953S41053S411535412S3S501S3S502S35503S3S504S3550553S506S3550753550853550953S510S3S51i$3S51243763343810943804443851043833443778143798043695443650143690843776943736243744343681043726643750543635543643243627143619243613243586743633143638443669843558243647643774643709443691643763243749943742743746543703543705143716343708543718243687943693943700143691218853188991889618919189111888318890188291880918827188681884918852188361885018858188191882318816187491874518720187551875718756187061874718818187891877718807188141880718806187751878818790187801878618775187771878318776SCE Input to Sargent & Lundy SFP AnalysesPage 58 of 131RAI-012 Response, Attachment APage A48 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S3S513S35514S3S515S3S516S3S517S3S51853551953S520S35521S3S522S3S523535524S35525535526535527$35528$3552953553053553153S532$35533$35534535535535536S3S537535538535539S3S540535541S35542$3554353554453554553554653554753554853S549535550S35551535552535553S3S554S3555543748143752843723043715643714943796143775843784543814143803243808043816643663943692343777743743243758943752043667343664243686543752343787243763343755143731343714443691243653743701243646543607243715643705643655343644043612143590043663443662343624943603243623818816188201880118781187921882418813188001878818814188241882218755187951885218798188281882618790187871879318838188571879918796187681877718800187801878518767187421877918777187511874018738187351874918745187331873718742535556S3TO0153T002S3T003S3T004S3T101S3T102S3T103S3TI04$3T201$3T202S3T203$3T204S3T205S3T206$3T20753T208S3T301S3T302S3T303S3T304S3T305S3T306S3T307S3T308S3T309S3T310S3T311S3T312S3T401S3T402$3T403S3T404$3T405$3T406S3T407S3T408$3T409S3T410S3T411$3T412$3T501S3T50243634144101044123944104544108243806243839543854243841043807643822543821243792843796943809043806143797843724043763843740043742243733843742643730443773643685843739043740443763143695543698343690843701143695543691143655943683243724843717943709543669343656343663318747198751988719878198791951919525195311952619553195451954619528195191953319535195491953219544195381954619540195471955019553195201952719518195371949119492194911949819489194791946919478194971950019495194721941819431SCE Input to Sargent & Lundy SFP AnalysesPage 59 of 131RAI-012 Response, Attachment APage A49 of A50 Assembly Total U (g) U-235 (g)Assembly Total U (g) U-235 (g)S3T503S3T50453T505S3T506S3T50753T508S3T509S3T510S3T511S3T512S3T513S3T514S3T515S3T516S3T517S3T518S3T519S3T520S3T521S3T522S3T523S3T524S3T525S3T526$3T527S3T528S3T529S3T530S3T531S3T532$3T533S3T534S3T535S3T536S3T5374363294366004368394365904358444358204358444370684373964379044372514364774360474365544371654372324372304372354363384366624364894360534360114362794366594362894365444365544366824365614362644364394367834366664368231941819437194611943919399194011940119477194741949119439194121940319424194391944119435194341939219415194121937719412194221943019418194311942219420194361942419435194541944619472S3T538S3T539S3T540S3T541S3T542S3T543S3T544S3T545S3T546S3T547S3T548S3T549S3T550S3T551S3T552S3T553S3T554S3T555S3T556S3T557S3T558S3T559S3T560S3T601S3T602S3T603$3T604S3T701S3T702S3T703S3T70443691043711743641143642843669743704443708443710643682243673243694143703943673443675743629043640243639543663443669443674843666843663243659543938743965743913043929143941043897343922443923319465194661944619428194451948119467194601947919472194841945019427194231941819424194181944419430194281944119435194311981019812197871979419543195231953119536SCE Input to Sargent & Lundy SFP AnalysesPage 60 of 131RAI-012 Response, Attachment APage A50 of A50 Attachment BORIGEN-ARP/ORIGEN-S input files(Pages B2 through B4 of the original document)

Attachment BCalculation No. 2013-13696 Revision 0Page No. B2 of B127'This SCALE input file was generated by'OrigenArp Version 6.0.13.12 January 12, 2010=arpcelE6xl6 LUse the cross section librarv Provided with the SCALE 6 package4.51 [Assembly average enrichment for the limiting assembly I2 Two cycles of irradiation 698. 5131 yFirst cycle irradiation time, =ys698.5131 ISecond cycle irradiation time, days I35.,98 First cycle specific power, MW/MTU35.98 1 Second cycle specific power, MW/MTU110.71 Moderator

density, g/ccft33fOOlend#origens0$$ a4 33 all 71 e tcel6xl63$$ 33 a3 1 27 a16 2 a33 18 e t35$$ 0 t56$$ 10 10 a6 3 alO 0 a13 13 a15 3 a18 1 e57** 0 a3 le-05 0.5 e95$$ 0 tCycle 1 Part 1 -Bounding IORIGEN-S input for first cycle, 10 time steps j0.440333 MTU Uranium loading, MTU 158** 15.84318 153 18 1W5.8fl431 15.84318 15.84318 15.84318 15.8431815.84318 15.84318 15.84318 XAssemblypower(MW)foreachtimestep 60** 69.85131 139.7026 209.5539 279.4052 349.2565 419.1078 488.9591558.8105 628.6618 698.5131 FCumulative irradiation time (days) at end ofeachtime step66$$ al 2 a5 2 a9 2 e73$$ 922340 922350 922360 922380 80000 240000 250000 260000 270000280000 400000 410000 500000 INuclideID(U-234.

U-235. U-236.U-238.O.Cr.

Mn. Fe.Co. Ni.Zr.Nb.Sn)I 74** 176.7453 19859.02 91.35148 420205.9 97.8 2301.8 106 4459.5 32.94371.5 100750.5 327.2 1646.4 FNuciide concentration (grams/assembly) for nuclide ID listed above75$$ 2 2 2 2 4 4 4 4 4 4 4 4 4 1 Library type for each nuclide lD listed above (2 -fuel, 4-lightelements) tcel6xl63$$ 33 a3 2 27 a33 18 e t35$$ 0 t56$$ 10 10 alO 10 a15 3 a18 1 e57** 698.5131 a3 le-05 0.5 e95$$ 0 tCycle 1 Part 2 -Bounding JORIGEN-S input for second cycle, 10 time steps.0.440333 MTU58** 15.84318 15.84318 15.84318 15.84318 15.84318 15.84318 15.8431815.84318 15.84318 15.84318 FAssembly power(MW) for each time step60** 768.3644 838.2157 908.067 977.9183 1047.77 1117.621 1187.4721257.324 1327.175 1397.026 FCumulativeirradiation time (days) at end of each time step66$$ al 2 a5 2 a9 2 e t54$$ a8 1 all 0 e56$$ a2 8 a6 1 alO 10 a14 5 a15 3 a17 2 e57** 0 a3 le-05 e95$$ 0 tCycle 1 Down -Bounding IORIGEN-S input forfirst decav case, from 0 days to 1.42 years0.440333 MTU60** 0.001 0.003 0.01 0.03 0.1 0.3 1 1.42 1Cumulative decay timeyears]

61** fO65$$'Gram-Atoms Grams Curies Watts-All Watts-Gamma 3z 3z 1 0 0 1 0 0 3z 6zRAI-012 Response, Attachment BPage BI of B3 Attachment BCalculation No. 2013-13696 Revision 0Page No. B2 of B1273z 3z 1 0 0 1 0 0 3z3z 3z 1 0 0 1 0 0 3z81$$ 2 0 26 1 a7 200 e82$$ 2 2 2 2 2 2 2 2 e83** 1Gamma energy group structure, in eV and descending order1.0000000e+07 8.0000000e+06 6.5000000E 3.0000000e+06 2.5000000e+06 2.OOOOOOOE 1.0000000e+06 8.0000000e+05 6.OOOOOOOE 2.0000000e+05 1.0000000e+05 5.OOOOOOOE 84** 1Neutron energy group structure, in eV and descending order2.0000000e+07 6.4340000e+06

3.0 000000O

1.4000000e+06 9.0000000e+05

4.0 000000O

3.0000000e+03 5.5000000e+02 1.0000000(

3.0499900e+00 1.7700000e+00 1.2999900E 8.00000OOe-01 4.0000000e-01 3.2500000E 5.00000OOe-02 3.00000OOe-02 9.9999980E t6z6zt+06~+06~+05t+04t+06~+05~+02~+00~-01~-035.0000000e+06 1.6600000e+06 4.0000000e+05 1.0000000e+04 1.8500000e+06 1.0000000e+05 3.0000000e+01 1.1299900e+00 2.2500000e-01 1.0000000e-05 4.0000000e+06 1.3300000e+06 3.0000000e+05 e1.7000000e+04 1.0000000e+01 1.0000000e+00 9.9999850e-02 e56$$ 0 0 alO 1 e t56$$ 0 0 alO 2 e t56$$ 0 0 alO 3 e t56$$ 0 0 alO 4 e t56$$ 0 0 alO 5 e t56$$ 0 0 alO 6 e t56$$ 0 0 alO 7 e t56$$ 0 0 alO 8 e t54$$ a8 1 all 0 e56$$ a2 9 a6 1 alO 8 a14 5 a15 3 a17 2 e57** 1.42 a3 le-05 e95$$ 0 tCase 4 JORIGEN-S input for the second decay case, continued from the first decay case, up to 4.93 years0.440333 MTU60** 1.76 2.09 2.42 2.76 3.09 3.42 3.92 4.42 4.93 ICumulative decaytime,years 61** fO65$$'Gram-Atoms Grams Curies Watts-All 3z 3z 1 0 0 1 0 0 3z 6z3z 3z 1 0 0 1 0 0 3z 6z3z 3z 1 0 0 1 0 0 3z 6z81$$ 2 0 26 1 a7 200 e82$$ 2 2 2 2 2 2 2 2 2 e8 3 ** Gamma energy group structure, in eV and descending order1.0000000e+07 8.0000000e+06 6.5000000e+06 3.0000000e+06 2.5000000e+06 2.0000000e+06 1.0000000e+06 8.0000000e+05 6.0000000e+05 2.0000000e+05 1.0000000e+05 5.0000000e+04 8 4 **

Neutron energy group structure, in eV and descending order2.0000000e+07 6.4340000e+06 3.0000000e+06 1.4000000e+06 9.0000000e+05 4.0000000e+05 3.0000000e+03 5.5000000e+02 1.0000000e+02 3.0499900e+00 1.7700000e+00 1.2999900e+00 8.00000OOe-01 4.00000OOe-01 3.2500000e-01 5.00000OOe-02 3.00000OOe-02 9.9999980e-03 Watts-Gamma 5.0000000e+06 1.6600000e+06 4.0000000e+05 1.0000000e+04 1.8500000e+06 1.0000000e+05 3.0000000e+01 1.1299900e+00 2.2500000e-01 1.0000000e-05 4.0000000e+06 1.3300000e+06 3.0000000e+05 e1.7000000e+04 1.0000000e+01 1.0000000e+00 9.9999850e-02 et56$$56$$56$$56$$56$$56$$56$$00000000 al0 1 e t0 alO 2 e t0 alO 3 e t0 alO 4 e t0 alO 5 e t0 alO 6 e t0 alO 7 e tRAI-012 Response, Attachment BPage B2 of B3 Attachment BCalculation No. 2013-13696 Revision 0Page No. B2 of B12756$$ 0 0 alO 8 e t56$$ 0 0 alO 9 e t56$$ fO tend#shellcopy ftT7lfOO1 "D:\San Onofre\Source Term\ORIGEN Runs\bounding.f71" del ft7lfO0endRAI-012 Response, Attachment BPage B3 of B3 ENCLOSURE 2Modified Exemption TableEmergency Planning Exemption RequestSan Onofre Nuclear Generating Station Requested Exemptions Table 1, Exemption RequestsRegulation Basis for Change1.0650.47(b):

The onsite a eXGept-as Generic Backoround Considerations

...... i i .. ...... ... .provided in nnF=OFAnm C3 gr thir, reG*!nRoff-ste emergency response plans fornuclear power reactors must meet thefollowing standards:

IIiIn the Statement of Considerations for the Final Rule forEP requirements for ISFSIs and for monitor retrievable storage installation (MRS) facilities (60 FR 32430; June22,1995),

the Commission responded to commentsconcerning offsite emergency planning for ISFSIs or anMRS and concluded that, "the offsite consequences ofpotential accidents at an ISFSl or a MRS {MOR40retrievable storage istallatiGR]

would not warrantestablishing Emergency Planning Zones." In a nuclearpower reactor's permanently defueled state, the accidentrisks are more similar to an ISFSI or MRS than anoperating nuclear power plant. The draft proposedrulemaking in SECY-00-01 45 suggested that after at leastone year of spent fuel decay time, the decommissioning licensee would be able to reduce its EP program to onesimilar to that required for an MRS under 10 CFR 72.32(b)and additional EP reductions would occur when: (1)approximately five years of spent fuel decay time haselapsed; or (2) a licensee has demonstrated that thedecay heat level of spent fuel in the pool is low enoughthat the fuel would not be susceptible to a zirconium firefor all spent fuel configurations.

The EP program would besimilar to that required for an ISFSI under 10 CFR72.32(a) when fuel stored in the SFP has more than fiveyears of decay time and would not change substantially when all the fuel is transferred from the SFP to an onsiteISFSI. Exemptions from offsite EP requirements havebeen approved when the specific site analyses show thatat least ten hours is available from a partial drain downevent where cooling of the spent fuel is not effective untilthe hottest fuel assembly reaches 9000C. Because tenhours allows sufficient time to initiate mitigative mitigating actions to prevent a zirconium fire in the SFP or to initiatead hoc offsite protective

actions, offsite EP plans are notnecessary for these permanently defueled nuclear powerplant licensees.

Site Specific BasisSouthern California Edison (SCE) has revised the accidentanalyses for those design basis accidents (DBA) thatremain applicable in the permanently defueled condition.

These revised accident analyses demonstrate that as ofAugust 2013. the radiological consequences of remaining applicable DBA will not exceed the limits of the U.S.Environmental Protection Agency's (EPA) Protective Action Guides (PAGs) at the Exclusion Area BoundaryPage 1 Requested Exemptions (EAB). These were summarized in Reference 1,Enclosure 1, Section 3.As shown in Enc!osure 1, SCE has demonstrated aminimum of 10 hou-rs is a-vailable for the c.nase of spent fuelpool adiabatic heatUp o 900oC In addition, SCE hasperformed analyses to show that after the fuel hasdecayed for 31 months, for beyond-design-basis eventswhere the SFP is drained, air cooling would prevent thefuel from reaching the lowest temperature where incipient cladding failure may occur (565°C).

This analysis case isalso addressed in RAI-01 1.In the event that air cooling is not possible, a minimum of10 hours is available to take mitigating actions or, ifneeded, offsite protective actions using an all-hazards approach to emergency planning from the time the fuel isuncovered until it reaches the auto-ignition temperature of9000C. This case is most often referred to as spent fuelpool adiabatic heatup and was also summarized inReference

1. Enclosure 1, Section 3 and is the subiect ofRAI-012.San Onofre Nuclear Generating Station (SONGS)maintains procedures and strategies for the movement ofor obtaining any necessary portable equipment that will berelied upon for mitigating the loss of spent fuel pool (SFP)water. These mitigating strategies were developed as aresult of the NRC Order on Mitigating Strategies (EA-02-026) and implement the reguirements of License Condition 2.C(26),

"Mitigation Strategy License Condition."

Thesediverse strategies provide defense-in-depth and ampletime to provide makeup water or spray to the SFP prior tosubstantial radioactive release or the onset of zirconium cladding ignition.

The details of these strategies aremanaged as commitments in response to the Mitigation Strategy License Condition.

The most recent update tothe commitments regarding mitigating strategies wassubmitted to the NRC on January 2, 2014 (ADAMSAccession

ML1 4007A1 64).The modified, site-specific basis is the fundamental technical basis for most of these exemptions.

Thus, thiswill be referred to freauentlv in the balance of this table.Page 2 Requested Exemptions

3. 450.47(b)(3):

Arrangements for De.ommissoning

...e. reactors SONGS presents a lowrequesting and effectively using likelihood of any credible accident resulting in radiological assistance resources have been made, releases requiring offsite protective measures because ofarrangement.

to acc.m...m.,o.date State and the permanently shut down and defueled status of theta,,ff a;t the 4.icn.ee's Emergency

.reactors.

An emergency operations facility would not beOperations Facility have been made, and required.

The "n, ucear iland" or "Main GControl fRoomnother organizations capable of or he Aoeafin-R an alternate command center can provideaugmenting the planned response have for the communication and coordination with offsitebeen identified.

organizations for the level of support required.

Also see the modified site-specific basis for Item 1(Section 50.47(b)).

4. §50.47(b)(4):

A standard emergency SCE has proposed EALs (ADAMS Accession classification and action level scheme, #ML14092A249) afe4--be consistent with Section 8 (4the basis of which include facility system aptIiGable and Appendix C of NEI 99-01 Revision 6and effluent parameters, is in use by the endorsed by the NRC in a letter dated March 28, 2013.nuclear facility

licensee, and State No offsite protective actions are anticipated to belocal response plans call fFr reliance on necessary, so classification above the Alert level is noinfo.rmation provided by facility I.ensees longer required.

for determinations of minimum initialo,,ite response m.easYFre.

Also see the modified site-specific basis for Item 1(Section 50.47(b)).

5. 050.47(b)(5):

Procedures have been Per SECY-00-0145, after approximately 1 year of spentestablished for notification, by the fuel decay time [and as supported by the licensee's SFPlicensee, of State and local response analysis],

the staff believes an exception to the offsite EPAorganizations and for notification of PAG standard is justified for a zirconium fire scenarioemergency personnel by all considering the low likelihood of this event together withorganizations; the content of initial and time available to take mitigative or protective actionsfollow up messages to response between the initiating event and before the onset of aorganizations andthe publ" has been postulated fire. The spent fuel scoping study provides thatestablished; and ,means to provide eady depending on the size of the pool liner leak, releases couldnotification and clear instruction to the start anywhere from eight hours to several days after thepopulace within the plume exposuFe leak starts, assuming that mitigation measures arepathway Em.ergency Planning Zone have unsuccessful.

If 10 CFR 50.54(hh)(2) type of mitigation beeAn estalished measures are successful, releases could only occur duringthe first several days after the fuel came out of the reactor.Therefore, offsite EP plans are not necessary for thesepermanently defueled nuclear power plant licensees.

.As; shnwn n Enco'sure 1, SCE s a-minimum of 10 ho-rs is available for the case of spent fuelpool adiabatic heatup to 9000C, Also see the modifiedsite-specific basis for Item 1 (Section 50.47(b)).

Page 3 Requested Exemptions

9. 450.47(b)(10):

A range of protective actions has been developed for theplume expsuwre pathway E lPZ foemergency workers and the public.-hi In the unlikely event of a SFP accident at SONGS, theiodine isotopes which contribute to an off-site dose are noloncier present, so potassium iodide (KI) distribution off-site would not serve as an effective or necessary supplemental protective action.r'nme i4RlAr.thanis

~ Fanan of nan GaRq11 ifBm ar,?o WrnanHt Wa rig,, tar , cnm ol~m.II"r~ of nnti~ittm jorluir (Kl'~ i" '. 1' -~usea~~n~

of gr, mtsum Oeihn 114-m1 asGr~-,ghave boon developed by applicants andlicnsees.

,icensees shall update thevacuationR time estimates 9n a poriedicbasis. Guidelines for: tthe cdhonive, ofnFEROGUYA

=G-1101216 GUAR0 nR EkMaMORG-11 r,- ....P, ir*t *eGamG itmiGh Car4ar.,I rim m ;Annna nraIdvlped and in place, and protective actiGR6 for the ingestion exnG6UF8nn!Rwn%1 rmKz- nnnFQt3F1n!9k 4CA !RCA !Qr-niohave been developed.

The Commission responded to comments in its Statement of Considerations for the Final Rule for emergency planning requirements for ISFSIs and MRS facilities (60FR 32435), and concluded that, "the offsite consequences of potential accidents at an ISFSI or a MRS would notwarrant establishing Emergency Planning Zones."Additionally, in the Statement of Considerations for theFinal Rule for EP requirements for ISFSIs and for MRSfacilities (60 FR 32430), the Commission responded tocomments concerning site-specific emergency planningthat includes evacuation of surrounding population for anISFSI not at a reactor site, and concluded that, "TheCommission does not agree that as a general matteremergency plans for an ISFSI must include evacuation planning."

[Relocate as Paragraph 1 and add Generic andBackground Considerations Subheading In the unlikely event Of a SFP2 accident, the iodine isotopesreacto accident are no logAer prnesent, so potassium iodide (KI) distibution off site would no iongern serve as aneffecntive, or necessary supplemental protec~tive action.Also see the modified site-specific basis for Item 1(Section 50.47(b))

and Item 11 (Appendix E,Section IV.1)for discussion on the similarity between a permanently defueled reactor and a non-Dower reactor.Page 4 Requested Exemptions

11. Appendix E.IV.1: The applicant's emergency plans shall contain, but notnecessarily be limited to, information needed to demonstrate compliance withthe elements set forth below, i.e.,organization for coping with radiological emergencies, assessment actions,activation of emergency organization, notification procedures, emergency facilities and equipment,

training, maintaining emergency preparedness,

recovery, and onsite protective actionsduring hostile action. In addition, theemergency response plans submitted byan applicant for a nuclear power reactoroperating license under this part, or foran early site permit (as applicable) orcombined license under 10 CFR part 52,shall contain information needed todemonstrate compliance with thestandards described in §50.47(b),

andthey will be evaluated against thosestandards.

The EP Final Rule published in the Federal Register (76FR 72560; November 23, 2011) amended certainrequirements in 10 CFR Part 50. Among the changes, thedefinition of "hostile action" was added as an act directedtoward an NPP or its personnel.

This definition is basedon the definition of "hostile action" provided in NRCBulletin 2005-02.

NRC Bulletin 2005-02 was notapplicable to nuclear power reactors that havepermanently ceased operations and have certified that fuelhas been removed from the reactor vessel.The NRC excluded non-power reactors (NPR) from thedefinition of "hostile action" at that time because an NPR isnot a nuclear power plant and a regulatory basis had notbeen developed to support the inclusion of non-power reactors in that definition.

Likewise, an SFP and an ISFSIare not nuclear power plants as defined in the NRC'sregulations.

The staff also considered the similarities between a decommissioning NPP and a non-power reactor to determine whether they should be includedwithin the definition of "hostile action."

NPRs pose lowerradiological risks to the public from accidents than dopower reactors because:

(1) the core radionuclide inventories are lower as a result of their lower power levelsand often shorter operating cycle lengths; and (2) NPRshave lower decay heat associated with a lower risk of coremelt and fission product release in a loss-of-coolant accident.

A decommissioning power reactor also has alow likelihood of a credible accident resulting inradiological releases requiring offsite protective measures.

For all of these reasons, the staff concludes that adecommissioning power reactor is not a facility that fallswithin the definition of "hostile action."Similarly, for security, risk insights can be used todetermine which targets are important to protect againstsabotage.

A level of security commensurate with theconsequences of a sabotage event is required.

TheSONGS proposed PDEP retains a level of planning forsuch events. The severity of the consequences declinesas fuel ages and, therefore, the underlying concern that asabotage attack could cause offsite radiological consequences decreases over time.Although the considerations discussed above provide aiustification for exemotino SONGS from "hostile action"related requirements, some EP requirements for security-based events will be maintained.

The classification ofsecurity-based events, notification of offsite authorities andcoordination with offsite agencies under a comprehensive emeraencv manaaement olan concept will still be reouired.

SONGS will maintain appropriate actions for the protection of onsite personnel in a security-based event.Page 5 Requested Exemptions

17. Appendix E.IV.A.1 A description of thenormal plant organization.

A --,4i- A +-. In rC'f D.,,+ r,(1 Mti-m- rr+iforF Nuclear Power Plants,"

states inpart: .there may be* .--P. ..... IA.J .... I----.-1waieF r-onled nUG1a=F 1AJWfdF URIPS +QF WHIGH 4-U!+!!!MaFit UfAnmop nf thp (Thnrnl~

Dosionn flritnrii mrna not hARequested Exemptions

+* In: ni. c + t ik 0, Gaedepartures fram the General Design Criteria must beidentified and justifid."

in Appendix A, a nuclear poGeunt i- defined as a p oWe .r actor and as6sociGequipment necessar-forF electric power generation aninldstho-rse structures,

systems, and compoenets required to proVide reasonable assurance that the facilitycan be operated without undue risk to the health andsafety of the public..

Based on the permanently shutdownR and- dofueled statue of the reactor,-a decommnrriAsionin reactor is not a facility that can beoperated to generate electrical power. Therefore, it denot have a "plant operating organization."

Based on the permanently shut down and defueled statusof the reactors, the SONGS reactors are not authorized tooperate under 10 CFR 50.82(a).

Because SCE cannotoperate the reactors, SCE does not have a "plantoperating organization."

18. Appendix E.IV.A.3.

AdeSG.itiGR,-bY The number of staff at decommissioning sites is generally position and funtion to be perfbomed, of small but is commensurate with the need to safely store

'6 headquaters spent fuel at the facility in a manner that is protective ofwho, V.4ill be sent to the plant site to public health and safety. Decommissioning sites augm.ent the .n..te em+er. ec have SONGS will maintain a level of emergency response.... that does not require response by headquarters personnel.

The on-shift and emergency responsepositions are defined in the Permanently DefueledEmer-gency Plan.20. Appendix E.IV.A.5.

WeitifiGatieih-by The number of staff at decommissioning sites SONGS isposition gentreFall relatively small but is commensurate with theother employees of the licensee with need to operate the facility in a manner that is protective special qualific,..ations fo..r .oping with of public health and safety.emhergency conditions that may ar.Other persons With special qualifications, such as consultants, who are netemployees of the licensee and who mnaybe called upor fod.rasistance frem~ergencies shall also be identified.

Thespca qualifications of these personsshal be de scrFi b ed.__________________________

Page 6 Requested Exemptions

21. Appendix E.IV.A.7.

By June 23, 2041,Identification of, and a description of theassistance expected from, appropriate State, local, and Federal agencies withresponsibilities for coping withemergencies, including hostile aGti0R atthe site. For purposes of this appendix, "hostile aGction" is defined as an actdirected toward a nuclear power plant orits personnel that includes the use ofviolent force to destroy equipment, takehostages, and/or intimidate the licenseeto achieve an end. This includes attackby air, land, or water using guns,explosives, projectiles,

vehicles, or otherdevices used to deliver destructive force.Requiring a decommissioni-

.ng site suc~h as SONGS toprovide a description of the assistan-e-expected from1appropriate State, local, and Federal agencies withresponribilities ford coping With emergencies wo ld be antinnecossarv hurden in liphi nf thA log r'ink nf ;;nonor~ar.,

arnee 4o f; ff~if 14 f 0~nRequested Exemptions UmUrgUnvy-Hububb d HS V V 000 0 CIM%7v.Requiring SONGS to identify and describhe the assistanc expected fromn appropriate State, local, and Feder-alagencies with responSibilities for coping With hoftile Action-at the s 4ite is unne r'ecause, as ea in sec~tion IVA1, a decommissioigpwe eco licensee isa. m~ + mnTnýn +tA m ,,. I'+ .4+m.oft......

"r" w%."hostile action.".Vt--. *~~"SONGS presents a low likelihood of any credible accidentresulting in radiological releases requiring offsiteprotective measures.

For this reason and those described in the basis for the proposed exemption from Appendix E,Section IV.1, the regulations specific to "hostile action"requirements are not applicable to a decommissioning power reactor such as SONGS.Similarly, for security, risk insiahts can be used todetermine which taroets are imoortant to Drotect aaainstsabotage.

A level of security commensurate with theconseauences of a sabotaae event is reeuired.

TheSONGS orooosed PDEP retains a level of olannina forsuch events. The severity of the conseauences declinesas fuel aaes and. therefore.

the underlvina concern that asabotaae attack could cause offsite radioloaical conseauences decreases over time.Although the considerations provided above and in thebasis the proposed exemption from Appendix E, SectionIV.1 provide a justification for exempting SONGS from"hostile action" related requirements, some EPrequirements for security-based events will bemaintained.

The classification of security-based events,notification of offsite authorities and coordination withoffsite agencies under a comprehensive emergency management plan concept will still be required.

SONGS will maintain appropriate actions for theprotection of onsite personnel in a security-based event.Page 7 Requested Exemptions

23. Appendix E.IV.A.9.

By December 21,ThA numFber of Staff ;# dt;AnmMksrinninn 6ites i6' Aenerall'i lice.sees.

a detailed analysi.s 311.I RSRut 'I_ Bel~l GAIM ...M. AAn 6u1rat with the need toRequested Exemptions

+~rne.~.tn

+; ., +k f .nnrkn n -. .-*operate the facility a.ma r tR that is protective of publicheIth and IAfetV ReenOnb!.iilitie; RA 'r1'.- defined in thefsignedA emergency erenesed emergency nlan intl nmcedureR intl wi'l he.,vassigned responsibilities that wfouldprevenit the timely perform~ance of theirassigne4d-funci4n apecified inthregularly tested through drlls and exercises.

that-will beaudited and inspected by SCE and the NRC. The duties etthe onshift pers~onnel At a: decomm -Issioni-ng reactor faciliyare not as complicated and diverse as those for ;Anoperating reactor.The NRC_ staff has con~sidoer-d-the similarity betweenth staffing Ievels at a permananltly shutdown and def, Wedr-eactor s9-taffing levels at NlPRs.O The minimal systemsand equipment neeedeed-to mainain the spent nuclear fue in'the pool or in a dr-y cask system in a safecnndition rFequire minimal PersonnAl anRd is byTe,.hnir.at Sn,, ifirit-li,,',-,

In t~he F'P RIde the, NR-, C'lTeGhniGal SneGifiratiORS IR the ER FiRal Rul the NRG.4 +1, + fk +.vnecessary for non power reactor licensees due to the smalstaffing lev-es required to operate the facility.

For all ofthese reasons, the staff has concluded thadecommissioning NP2P is exempt fromA the requiremento 10 CPR Part 50, Appendix E, Section WY.A.Responsibilities for on-shift and emergency responseDersonnel are defined in the Permanently DefueledEmergency Plan and implementing procedures.

The PDEPand implementing procedures will be regularly testedthrouah drills and exercises that will be audited bv SONGSand inspected by the NRC. The duties of the SONGS on-shift personnel are not as complicated and diverse as thosefor an operating power reactor.In the EP Final Rule (published in the Federal Register (76FR 72560: November

23. 2011). the NRC acknowledoed that the staffinq analysis requirement was not necessary fornon-Dower reactor licensees because staffina at non-Dower reactors is generally small, which is commensurate withoneratino the facility in a manner that is orotective of theoublic health and safety. The limited systems andequipment needed to safely maintain the spent nuclear fuelin the soent fuel Dool or in a dry cask storaee systemrequire minimal personnel and are governed by Technical Specifications.

Event scenarios postulated in the DBAs evolve at a slowrate. SONGS on-shift personnel duties are less complex.Therefore, significant time is available to complete actionsnecessary to mitigate an emergency without impedingtimely performance of emergency plan functions.

Theseiustifications support the conclusion that SONGS, as adecommissioning

reactor, can be exempt from therequirement of 10 CFR Part 50, Appendix E, SectionIV.A.9.Page 8 Requested Exemptions

25. Appendix E.IV.C.1:

The entire spectrumof emergency conditions that involve thealerting or activating of progressively larger segments of the total emergency organization shall be described.

Thecommunication steps to be taken to alertor activate emergency personnel undereach class of emergency shall bedescribed.

Emergency action levels(based not only on onsite andoffsite radiation monitoring information but alsoon readings from a number of sensorsthat indicate a potential emergency,

&uGha sthe pnreIure In GnnRunImnRu annd WereSPOnse of the EmnergencY Core CoolinguSystem) for notification of offsiteagencies shall be described.

Theexistence, but not the details, of amessage authentication scheme shall benoted for such agencies.

The emergency classes defined shall include:

(1)notification of unusual events, (2) alert,(3) site area emnergency, and (4) generaleone~geRGy Of 10 CFR Part 50, AppendixE, IV.C.1. These classes are furtherdiscussed in NUREG-0654/FEMA-REP-1.SCE has proposed adoption of Permanently DefueledEALs (ADAMS Accession

ML14092A249),

consistent with those described in Section 8 and Appendix C of NEI99-01, Revision

6. This scheme eliminates the Site AreaEmergency and General Emergency event classifications.

Additionally, the need to base EALs on containment pressure and the response of the Emergency CoreCooling System (ECCS) is no longer appropriate fornotification of offsite agencies.

The NEI 99-01, Revision 6,scheme was endorsed by the NRC in a letter dated March28, 2013 (ADAMS Accession No. ML12346A463).

Nooffsite protective actions are anticipated to be necessary, so classification above the Alert level is no longer required.

In the unlikely event of an accident at SONGS, there willbe available time for event mitigation, and if necessary, implementation of offsite protective actions using an all-hazards approach to emergency planning.

See themodified, site-specific basis for Item 1 (10 CFR 50.47(b))

detailing the low likelihood of a credible accident resulting in radiological releases requiring offsite protective measures.

Containment parameters do will not provide an indication of the conditions at a dofuel-dfclt SONGS andemergency core cooling systems are will no longer berequired.

Other indications such as SFP level oeandtemperature are used for the spent fuel in the SFPs.In the Statement of Considerations for the Final Rule forEP requirements for ISFSIs and for MRS facilities (60 FR32430), the Commission responded to commentsconcerning a general emergency at an ISFSI and MRS,and concluded that, "...an essential element of a GeneralEmergency is that a release can be reasonably expectedto exceed EPA Protective Action Guidelines exposurelevels off site for more than the immediate site area." Theprobability of a condition reaching the level above anemergency classification of alert is very low. In the eventof an accident at a permanently defueled facility thatmeets the conditions for relaxation of EP requirements, there will be time to take ad hoc measures to protect thepublic."As stated in NUREG-1 738, for instances of small SFPleaks or loss of cooling scenarios, these events evolvevery slowly and generally leave many days for recoveryefforts.

Offsite radiation monitoring will be performed asthe need arises. Due to the decreased risks associated with permanently defueled plants, offsite radiation monitoring systems are not required.

TI-, -A C~rnend~

A! elxpl ^nr .a,~nr4 iclh fk tha ~n ^ r..mV V VMArAruVIAP Iin ~ P11- uHW- i. rw':tISur rPage 9 Requested Exemptions

26. Appendix E.IV.C.2:

By June 20, 20-2,nuclear power reactor Licensees shallestablish and maintain the capability toassess, classify, and declare anemergency condition;-wthin 15 minutesafter the availability of indications to plantoperators that an emergency action levelhas been exceeded and shall promptlydeclare the emergency condition as soonas possible following identification of theappropriate emergency classification level. Licensees shall not construe thesecriteria as a grace period to attempt torestore plant conditions to avoiddeclaring an emergency action due to anemergency action level that has beenexceeded.

Licensees shall not construethese criteria as preventing implementation of response actionsdeemed by the licensee to be necessary to protect public health and safetyprovided that any delay in declaration does not deny the State and localauthorities the opportunity to implement measures necessary to protect the publichealth and safety.Generic Background Considerations In the Proposed Rule (74 FR 23254) to amend certainemergency planning requirements for 10 CFR Part 50, theNRC asked for public comment on whether the NRCshould add requirements for non-power reactor licensees to assess, classify, and declare an emergency condition within 15 minutes and promptly declare an emergency condition.

The NRC received several comments on theseissues. The NRC believes there may be a need for theNRC to be aware of security related events early on sothat an assessment can be made to consider thelikelihood that the event is part of a larger coordinated attack. However, the NRC determined that furtheranalysis and stakeholder interactions are needed prior tochanging the requirements for non-power reactorlicensees.

Therefore, the NRC did not includerequirements in the 2011 EP Final Rule for non-power reactor licensees to assess, classify, and declare anemergency condition within 15 minutes and promptlydeclare an emergency condition.

The staff considered thesimilarity between a permanently defueled reactor and anon-power reactor for the low likelihood of any credibleaccident resulting in radiological releases requiring offsiteprotective measures.

Site Specific BasisSONGS will maintain the capability to assess, classify, and declare an emergency condition.

For a site such asSONGS that is in the permanently defueled condition, therapidly developing scenarios associated with eventspostulated to occur durinq reactor power operation areno longer credible.

The consequences resulting from theonly remaining events (e.g., fuel handling accident) develop over a significantly longer period. As such, the15 minute requirement to classify and declare anemergency is unnecessarily restrictive.

Also see the modified site-specific basis for Item 1 (10CFR 50.47(b))

detailing the low likelihood of a credibleaccident resulting in radiological releases requiring offsiteprotective measures and see Item 11 (Appendix E,Section IV. 1) for discussion on the similarity between apermanently defueled reactor and a non-Dower reactor.29. Appendix E.IV.D.3:

A licensee shall Generic Background Considerations have the capability to notify responsible State and local governmental agencies While the capability needs to exist for the notification of5 after declaring an offsite government agencies within a specified timeemergency.

The licensee shall period, previous exemptions have allowed for extending d.emonstrate that the the State and local government agencies' notification governmental authorities have the time up to 60 minutes based on the site-specific capability to make a public alerting and justification provided.

Page 10 Requested Exemptions infnrmrr h"t tha Iir'naZOA oif nnI ...- I.--..---

_. -eME)r-geRGyGendii P i t i iti ltherma. Of the first rFeaGtr site, each nuclear power reactor licenseeshall demonstrate that administrati-e andnhmi.,I mreans' have. been ,ert.'lishrehd Site Specific BasisDue to the low probability of design-basis accidents orother credible events to exceed the EPA PAGs, thesignificantly reduced staff, and the minimal expectedoffsite response

required, the need to provideimmediate (within 15 minutes) notification has beenreduced.

to a 60 minute requirement.

The reduced on-shift ERO's priorities may be responding to anemergency event prior to making offsite notifications.

SCE proposes to comolete emeraencv notifications for iIr~rtino

~nd nro"~dinri ornmnt .~.inF aiirtion' and th'ni'cihntFn'me

...-1G~ * ~ .-I.exposure pathway EPZ. The des'gobjective of the prompt public alert andnotific~ation system shall be to have thecapability to essentially completeth initi-al alerting and initiate notificatio othe public- within the plume exposurpathway EPZ= within abhout 1 5 Minutes..vwithin 60 minutes after an emercencv declaration or achance in classification.

State and local aoencv staffedWarnina Points for the State of California.

OranaeCounty. San Dieao County. and the Marine Coros Base.Came Pendleton.

will be notified within 60 minutes.capability Will range from immediate v,,Information would then be disseminated to the publicand media in accordance with State and local clans.(witin '~ inito~tof ho tme hit tit(wi t hi R 15 m n e s e f I h e t 0 rA e t ha t Rta t e-sbituatioen exists requiring urgent action) tothe more likely events wAhere:L~

thereisubs__h6;tan tial t.iim e ailable1 A for th eappropriate governm~ental authorities toFAake a judg nt INIRt9thfBir OF ROt tOaGti t th bli ! t d A*f A;G,The 60-minute provision is consistent with the 10 CFR50.72(a)(3) notification to the NRC and is appropriate

because, for a site such as SONGS that is in thepermanently defueled condition, the rapidly developing scenarios associated with events postulated to occurduring reactor power operation are no longer credibleand there is no need for State or local responseorqanizations to implement any protective actions.Also see the modified site-specific basis for Item 1(50.47(b))

and Item 9 (50.47(b)(10))

for a discussion of thedose consequences from DBA as well as the lowprobability of beyond DBA events at SONGS to exceedthe EPA PAGs.Gapability shall additionally inRGIide* A. A39F ad l z fnotification capable of being used in theevent the primaray method of alerting andnotificOation isF unavailable duringaof the~ plumeu expoU~.et pathway EPpopulation.

The backup method shallf- f --A -Cf- +k-a, ~ ~ ~ ~ ~ ------ --u--i -- t aa*ae r ....']-0--~~a, CD7 P- '4 _-4aena an t naZh I .r'__n-.+a A-c,. sh- t~ f-, +hanr~~m.,rkl, nra-4s -4tu..lat.,n P- .. ...j -... i --- ------....

...notification system. When there is adecision to activate the alert andnotificmtion system tnnnormrntla hr,theao

,.,lI naternngv e t l th iti I *" dAWF iReiNhethew to a;;r_,f*v_;;tA thp eRtiFe aleFt aRdRGtffifiGatieR system simultaReously oF iR agraduated oF staged FnaRner.

TheFespon6ibility f9F a4vating suGh a publiG,e ar e .I ra, ,_wdh-4he-a ItA Aovernme~nt~al au4hoP~e~

Page 11 Requested Exemptions

32. Appendix E.IV.E.8.a.(ii):F nrm1Ie;;or.ite ope.a.ionz..

support center..vNUREG-0696, "Functional Criteria for Emergency Response Facilities,"

provides that the operational support center (OSC) is an onsite area separate fromthe control room Main Control Room and the TSCwhere licensee operations support personnel willassemble in an emergency.

For a permanently defueled power plant such as SONGS, the rapidlydeveloping scenarios associated with events postulated to occur during reactor power operation are no longercredible.

The number of operations support personnel necessary for response to the remaining credible eventsis accordingly much smaller.

As a result, an OSC is nolonger required to meet its original purpose of anassembly area for plant logistical support during anemergency.

The OSC function can be incorporated intoanother facility.

38. Appendix E.lV.E.9.c.Prc'iesIe fercomnnniclaGti9ons among tAe nuiGlearpower reactor control room, the ..sitctechnical SUPPOrt aRd the operation faGility; among the nUctear facility, the principal State and local emnergency operations Such communications systems shall betestedannually.

Because of theThe SONGS analysis confirmed the lowprobability of design-basis accidents or other credibleevents that would be expected to exceed the EPA PAGsand determined that there is sufficient the available timefor event mitigation and if needed, implementation ofoffsite protective actions using a comprehensive emergency management plan. Therefore, there is noneed for the TSC, EOF or field assessment teams.Also see justifi"eatiO the modified site-specific basis forItem 3 (50.47(b)(3)).

The provisions remaining inAppendix E to 10 CFR 50, Section IV.E.9.a, b, and dinclude the necessary requirements.

CommunicAtion With State and lonl EMts ismintane-d-to- cor__d~inateasssaneo site if required.

Page 12 Requested Exemptions

40. E.IV.F.1:

The program to provide for: (a)The training of employees andexercising, by periodic drills, ofemergency plans to ensure thatemployees of the licensee are familiarwith their specific emergency responseduties, and (b) The participation in thetraining and drills by other personswhose assistance may be needed in theevent of a radiological emergency shallbe described.

This shall include adescription of specialized initial trainingand periodic retraining programs to beprovided to each of the following categories of emergency personnel:

i. Directors and/or coordinators of theplant emergency organization; ii. Personnel responsible for accidentassessment, including control roomshift personnel; iii. Radiological monitoring teams;iv. Fire control teams (fire brigades);

v. Repair and damage control teams;vi. First aid and rescue teams;vii. Medical support personnel; viii. Licensee's headqua.ters supportix. Security personnel.

In addition, a radiological orientation training program shall be made available to local services personnel; e.g., localemergency services!Cvil

Defense, locallaw enforcement personnel, eGal-ReWS The number of staff at decommissioning sites is generally small but is commensurate with the need to safely storespent fuel at the facility in a manner that is protective ofpublic health and safety. Decommissioning sites typically have a level of emergency response that does not requireadditional response by headquarters personnel.

Therefore, the NRC staff has stated that it considers exempting licensee's headquarters personnel from trainingrequirements reasonable.

Also see the basis for Item 1(Section 50.47(b))

There will no loncer be any expected actions that must betaken by the public during an emergency, so it is no longernecessary to pre-plan the dissemination of this information to the public or to provide radioloqical orientation traininqto local news media persons.The phrase "Civil Defense" is no lonaer a commonly usedterm and is no longer applicable as an example in theregulation.

Page 13 Requested Exemptions

43. Appendix E.IV.F.2.a A full pa-ticipation a'varriea

,,,-hi--h

aet. ,eo mi ,r,,h nf '*ha.Sinco tho nr~ed for off ~ito emnrooncv nhnnino Ic mlaxodduo to the o need hili Off sitea hae~eRG paccidntc osre.w--licensee, State, and local emergenGcy plans als is- reasoenably achievable withoutman:;da-tory public participation s hale-conucedi fo;-r-eah site at wghic-h a powerreactor is located.

Nuclear power reac~torlicensees shall s-bmit exercise scenarios under § 50.4 at least 60 days before usein a4 full participation ercsrqured bythis paragraph.

2.a-.F.2.a.(i),

(ii), and (iii) are not applicable.

ether credible events that would be expeGted t0 exceodthp limifr; of E=PA PAGP. and the avaihlabl time for eventm;.;,.. ~ ;.,~ am nrr.nn,.1, at ane5pth mdIfd iPncii i frImI(O4ht v..On that basis, SCE has requested exemption from offsiteplans. With no offsite emerqency plan, there is no needfor full participation exercises that include offsite agencyparticipation.

The intent of submitting exercise scenarios at powerreactors is to check that licensees utilize different scenarios in order to prevent the preconditioning ofresponders at power reactors.

For permanently defueledsites such as SONGS, there are limited events that couldoccur and the previeusly rui potential progression toGeneral Emergency in power reactor site scenarios istherefore not applicable to a decommissioning site.SONGS should be exempt from F.2.a.(i)-(iii) becauseSONGS is-would be exempt from the umbrella provision ofF.2.a.46. Appendix E.IV.F.2.d:

Each State wFespnnn~'ihlitv for nuGloar mower roactorSee basis for section IV.2.See the modified site-specific basis for Item 1 (Section50.47(b))

emerYeru preprr~uiiue flb 5lulu tuupatcPate in the ingestion pathwaypotOnf ex(ercises at leaR-st oncne everyexercise cycle. in States wi th mRore than,one nuclear power reactor p.mexposure pathway EP;Z, the- State shouldrotate this participatio-n fromn site to site.Each State with responsibility for nuclearpower reactor emergency preparedness should fully participate in a hos~tile actiVonexecie at least once eveF' cycle andshould fUlly participate in one hostileacrt-ionexecis by December 31, 201 5.States With mor-e thRan one nul4Gear powerreactor plume exposure pathway EPZshould rotate this participation from siteto-S~e-.47. Appendix E.IV.F.2.e:

Licensees shall See basis for section IV.2.enable any State or local government lGoa-t-e with;in the plum"e exposur See the modified site-specific basis for Item 1 (Sectionpathway=P-Z to participate in the 50.47(b)).

licensee's drills when requested by suchState or local government Page 14 Requested Exemptions

48. Appendix E.IV.F.2.f:

Remedial exercises will be required if the emergency plan isnot satisfactorily tested during thebiennial

exercise, such that NRC.Tmcensultatien with FEMA, cannot (1) findreasonable assurance that adequateprotective measures can and will betaken in the event of a radiological emergency or (2) determine that theEmergency Response Organization (ERO) has maintained key skills specificto emergency response.

The extent eState and local participation in remediale Arcss Mu st ber suficient to show thatapproapriate corrective mneasures havebheen takenl regarding the elements of theI--m --# --1aI~ f-fAct ;_~ 0-~nrhruThe U.S. Federal Emergency Management Agency(FEMA) is responsible for the evaluation of an offsiteresponse exercise.

No action is expected from State orlocal government organizations in response to an event ata decommissionsng cite SONGS other than firefighting, lawenforcement and ambulance/medical services.

SCE hasLetters of Agreement in place for those services.

Offsiteresponse organizations will continue to take ad hocactions to protect the health and safety of the public asthey would at any other industrial site.exe~ses~49. Appendix E.IV.F.2.i:

Licensees shall usedrill and exercise scenarios that providereasonable assurance that anticipatory responses will not result frompreconditioning of participants.

Suehsc0nrio for nucearF power reactolicensees must inc-lude a wide spectrtum Of rad469l09ical releas-es

And cvent6,including' hostile action. Exercise and drillscenarios as appropriate mustemphasize coordination among onsiteand offsite response organizations.

For permanently defueled sites such as SONGS, there arelimited events with dose consequences potentially exceeding the EPA PAGs that could occur. and-theTherefore, the previously routine progression to GeneralEmergency in power reactor site scenarios is not-no longerapplicable to a decemmissiening site. Therefore andSONGS should not be expected to demonstrate responseto a wide spectrum of events.Also see the modified site-specific basis for Item 1(50.47(b))

detailing the low likelihood of a credible accidentresulting in radiological releases requiring offsite protective measures and the basis for Item 11 (Appendix E, SectionIV.1) regarding hostile action.Page 15 Enclosure 3Regulatory Commitments Regulatory Commitment Location One-time or Scheduled Completion recurring

[DateProcedures will be revised toensure that walk-downs andpatrols [of SFP systems]

areperiodically (no less thanonce a shift) performed.

Enclosure 1,RAI 11response, Table Itemfor SDA#2Recurring Prior to implementation of the proposedPermanently DefueledEmergency Plan

@@ Line 16: / Line 16: @@
 =Text=
-{{#Wiki_filter:I SOUTHERN CALIFORNIAEDISONAn EI)ISON INTERNATONAl " Cmpa nThomas I. PalmisanoVice President & Chief Nuclear OfficerSeptember 9, 201410 CFR 50.12U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555
+{{#Wiki_filter:I SOUTHERN CALIFORNIA EDISONAn EI)ISON INTERNATONAl
+" Cmpa nThomas I. Palmisano Vice President
+& Chief Nuclear OfficerSeptember 9, 201410 CFR 50.12U. S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, D.C. 20555
 ==Subject:==
-Docket No. 50-206, 50-361, 50-362, and 72-041Response to Request for Additional InformationRegarding Emergency Planning Exemption RequestSan Onofre Nuclear Generating Station, Units 1, 2, 3 and ISFSI(1) Letter from T. J. Palmisano (SCE) to the U.S. Nuclear RegulatoryCommission (NRC) dated March 31, 2014;
+Docket No. 50-206, 50-361, 50-362, and 72-041Response to Request for Additional Information Regarding Emergency Planning Exemption RequestSan Onofre Nuclear Generating
+: Station, Units 1, 2, 3 and ISFSI(1) Letter from T. J. Palmisano (SCE) to the U.S. Nuclear Regulatory Commission (NRC) dated March 31, 2014;
 ==Subject:==
-Docket Nos. 50-206, 50-361, 50-362, and 72-041, Emergency Planning ExemptionRequest, San Onofre Nuclear Generating Station, Units 1, 2, 3, andIndependent Spent Fuel Storage Installation
+Docket Nos. 50-206, 50-361, 50-362, and 72-041, Emergency Planning Exemption
+: Request, San Onofre Nuclear Generating
+: Station, Units 1, 2, 3, andIndependent Spent Fuel Storage Installation
 ==Reference:==
 (2) Letter from T. J. Wengert (NRC) to T. J. Palmisano (SCE) datedAugust 27, 2014;
 ==Subject:==
-San Onofre Nuclear Generating StationUnits 1, 2 and 3, Request for Additional Information Re: EmergencyPlanning Exemption Request (TAC NOS 3835, 3836 and 3837)
+San Onofre Nuclear Generating StationUnits 1, 2 and 3, Request for Additional Information Re: Emergency Planning Exemption Request (TAC NOS 3835, 3836 and 3837)
 ==Dear Sir or Madam:==
-By letter
+By letter dated March 31, 2014 (Reference 1), Southern California Edison (SCE)submitted an exemption request from certain requirements of 10 CFR 50.47,"Emergency Plans," and 10 CFR Part 50, Appendix E, "Emergency Planning andPreparedness for Production and Utilization Facilities,"
+for San Onofre NuclearGenerating Station (SONGS) Units 1, 2, and 3, and the Independent Spent FuelStorage Installation (ISFSI).
+Granting the exemptions requested is necessary tosupport review and approval of a Permanently Defueled Emergency Plan andassociated Emergency Action Levels both of which are being addressed separately.
+By letter dated August 27, 2014 (Reference 2), the NRC requested additional information related to the proposed exemption request.
+The response to the NRCrequest for additional information is contained in Enclosure 1 to this letter. Theresponse results in changes to the proposed exemptions of Reference
+: 1. A revisedexemption table is provided as Enclosure 2 to this letter. The conclusions of the nosignificant hazards consideration and environmental considerations contained
 ==Subject:==
-DocketNos. 50-206, 50-361, 50-362, and 72-041, Emergency Planning Exemption Request, San Onofre NuclearGenerating Station, Units 1, 2, 3, and Independent Spent Fuel Storage Installation (ADAMS Accession#ML1 4092A332)Page 23
+DocketNos. 50-206, 50-361, 50-362, and 72-041, Emergency Planning Exemption
+: Request, San Onofre NuclearGenerating
+: Station, Units 1, 2, 3, and Independent Spent Fuel Storage Installation (ADAMS Accession
+#ML1 4092A332)
+Page 23
 : 2. Letter from Thomas J. Palmisano (SCE) to Document Control Desk (NRC) dated March 31, 2014;
 ==Subject:==
-DocketNos. 50-206, 50-361, 50-362, and 72-041, Amendment Application Numbers 223, 267, and 252, PermanentlyDefueled Emergency Plan, San Onofre Nuclear Generating Station, Units 1, 2, and 3, respectively, andIndependent Spent Fuel Storage Installation (ADAMS Accession #ML14092A314)3. Letter from Thomas J. Palmisano, (SCE) to Document Control Desk (NRC) dated March 21, 2014;
+DocketNos. 50-206, 50-361, 50-362, and 72-041, Amendment Application Numbers 223, 267, and 252, Permanently Defueled Emergency Plan, San Onofre Nuclear Generating
+: Station, Units 1, 2, and 3, respectively, andIndependent Spent Fuel Storage Installation (ADAMS Accession
+#ML14092A314)
+: 3. Letter from Thomas J. Palmisano, (SCE) to Document Control Desk (NRC) dated March 21, 2014;
 ==Subject:==
-DocketNos. 50-361 and 50-362, Amendment Application Numbers 266 and 251, Permanently Defueled TechnicalSpecifications, San Onofre Nuclear Generating Station, Units 2 and 3 (ADAMS Accession #ML1 4085A1 41)4. Letter from R. St Onge (SCE) to Document Control Desk (NRC) dated January 2, 2014;
+DocketNos. 50-361 and 50-362, Amendment Application Numbers 266 and 251, Permanently Defueled Technical Specifications, San Onofre Nuclear Generating
+: Station, Units 2 and 3 (ADAMS Accession
+#ML1 4085A1 41)4. Letter from R. St Onge (SCE) to Document Control Desk (NRC) dated January 2, 2014;
 ==Subject:==
-Docket Nos. 50-361 and 50-362, Commitment Change Report, San Onofre Nuclear Generating Station (ADAMS Accession#ML14007A164)5. Letter from N. Kalyanam (NRC) to Richard M. Rosenblum (SCE) dated July 26, 2007;
+Docket Nos. 50-361 and 50-362, Commitment Change Report, San Onofre Nuclear Generating Station (ADAMS Accession
+#ML14007A164)
+: 5. Letter from N. Kalyanam (NRC) to Richard M. Rosenblum (SCE) dated July 26, 2007;
 ==Subject:==
-San OnofreNuclear Generating Station
+San OnofreNuclear Generating
+: Station, Units 2 and 3 -Conforming License Amendments to Incorporate the Mitigation Strategies Required by Section B.5.b of Commission Order EA-02-026 (TAC Nos. MD4564 and MD4565)Page 24 Attachment ASONGS Units 2 and 3Fuel Management Records(Pages 11 through 60 of the original document) 5.0 SPENT FUEL POOL ]INVENTORY DISCHAGE AND BURNUPThe following pages list the assemblies in each spent fuel pool, along with their last irradiation date, and burnup in units of MWD/MTU.
+All data in this section is from Reference 7.3.1.The Unit 2 spent fuel pool contains 1426 assemblies.
+The Unit 3 spent fuel pool contains 1350 assemblies.
+.1 UNIT 2S2A001S2A002S2A004S2A011S2A016S2A017S2A021$2A022S2A024S2A025S2A033$2A034S2A035S2A037S2A038S2A043S2A044$2A050$2A055S2A059S2A066S2AT02S2AT04S28001$2B002S2B003S2B004S2B005S2B006S2B008S2B009S2B010S2B011S2B012S2B013S2B014S2B015S2B016S2BO17$2B018S2B019S2B020S2B021S2B02203/15/8608/17/9110/21/8410/21/8409/02/8909/02/8909/02/8909/02/8910/21/8410/21/8410/21/8410/21/8410/21/8410/21/8410/21/8409/02/8910/21/8410/21/8408/29/

v t e Letter Sequence Response to RAI
TAC:MF3835, (Approved, Closed)
Initiation Request, Request, Request Acceptance... Administration Questions 10 September 2014 22 September 2014 27 August 2014 Answers 3 November 2014 Results Approval Other: ML14092A249, ML14303A257, ML15056A274, ML15056A277, ML15082A143, NRC-2015-0093, Independent Spent Fuel Storage Installation - Exemptions from Certain Emergency Planning Requirements (TAC Nos. MF3835, MF3836, and MF3837)
MONTHYEAR2014-08-27 [Table View]

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