Text

License Amendment Request - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme
	ML18295A384
Person / Time
Site:	Oyster Creek
Issue date:	10/22/2018
From:	Gallagher M; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	RA-18-092
	Download: ML18295A384 (54)
	v • d • e

Exelon Generation ~

Michael P. Gallagher Exelon Nuclear Vice President License Renewal and Decomm1ss1oning 200 Exelon Way Kennett Square, PA 19348 610 765 5958 Office 610 765 5658 Fax www.exeloncorp.com m1chaelp.gallagher@exeloncorp.com 10 CFR 50.90 RA-18-092 October 22, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket Nos. 50-219 and 72-15 License Amendment Request -

Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme

Reference:

1)

Electronic Mail Capture from John Lamb (U.S. Nuclear Regulatory Commission) to David Helker (Exelon Generation Company, LLC), "Oyster Creek Permanently Ceases Power Operations, "dated September 17, 2018 (ML18263A163)

2)

Letter from Michael P. Gallagher, Exelon Generation Company, LLC to U.S. Nuclear Regulatory Commission -

"Certification of Permanent Removal of Fuel from the Reactor Vessel for Oyster Creek Nuclear Generating Station," dated September 25, 2018 (ML18268A258)

3)

Letter from U.S. Nuclear Regulatory Commission to Bryan C. Hanson (Exelon Generation Company, LLC) - "Oyster Creek Nuclear Generating Station - Issuance of Amendment Re: Changes the Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme (GAG NO. MG0160; EPID L-2017-LLA-0307)," dated October 17, 2018 (ML18221A400)

4)

Letter from U.S. Nuclear Regulatory Commission to Bryan C. Hanson (Exelon Generation Company, LLC) - "Oyster Creek Nuclear Generating Station - Exemptions from Certain Emergency Planning Requirements and Related Safety Evaluation (GAG NO. MG0153; EPID L-2017-LLE-0020),"

dated October 16, 2018 (ML 182220A980)

5)

Letter from Michael P. Gallagher, (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission -

"Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E," dated August 22, 2017 (ML17234A082)

U.S. Nuclear Regulatory Commission License Amendment Request Docket Nos. 50-219 and 72-15 October 22, 2018 Page2

6)

Letter from Michael P. Gallagher, (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission - "Supplement to Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E," dated March 8, 2018 (ML18067A087)

7)

Letter from Michael P. Gallagher, Exelon Generation Company, LLC to U.S. Nuclear Regulatory Commission -

"Certification of Permanent Cessation of Power Operations for Oyster Creek Nuclear Generating Station," dated February 14, 2018 (ML18045A084)

Pursuant to 1 O CFR 50.90, "Application for amendment of license or construction permit,"

Exelon Generation Company, LLC (Exelon) requests an amendment to Renewed Facility Operating License Number DPR-16 for Oyster Creek Nuclear Generating Station (OCNGS).

The proposed amendment would revise the effective and implementation dates of License Amendment No. 294, Permanently Defueled Emergency Plan (PDEP) and Emergency Action Level (EAL) scheme for the permanently defueled condition. The proposed changes are being submitted to the U.S. Nuclear Regulatory Commission (NRC) for approval prior to implementation.

On September 17, 2018, OCNGS permanently ceased power operations (Reference 1). By letter dated September 25, 2018, (Reference 2), Exelon certified that all fuel had been permanently removed from the OCNGS reactor vessel and placed in the spent fuel pool (SFP).

On October 17, 2018, the NRC approved License Amendment No. 294, OCNGS PDEP and Permanently Defueled EAL Scheme (Reference 3). The PDEP and Permanently Defueled EAL scheme were predicated on approval of requests for Exemptions from portions of 1 O CFR 50.47(b), 1 O CFR 50.47(c)(2), and 1 O CFR Part 50, Appendix E,Section IV, which were approved on October 16, 2018 (Reference 4).

The PDEP and Permanently Defueled EAL scheme were predicated on approval of requests for exemptions from portions of 1 O CFR 50.47(b), 10 CFR 50.47(c)(2), and 10 CFR Part 50, Appendix E, Section IV, approved in Reference 4. The PDEP reduces the scope of offsite and onsite emergency planning commensurate with the permanently defueled condition.

The basis for the approval of the exemptions from offsite emergency preparedness (EP) requirements included a site-specific analysis that showed that the fuel stored in the SFP would not reach the zirconium ignition temperature in fewer than 1 O hours from the time at which it was assumed a loss of both water and air cooling of the spent fuel (zirc-fire window). Exelon's site-specific analyses for OCNGS, as provided in Exelon's exemption request (Reference 5),

showed that 12 months after permanent cessation of power operations, the spent fuel stored in the SFP will have decayed to the extent that the requested exemptions may be implemented at OCNGS.

Since the time of the submittal of the original adiabatic calculation in Reference 5, two key assumptions have been reconsidered based on actual conditions at the time of final shutdown.

First, the fuel in the reactor at the time of the final shutdown (Cycle 26) was considered instead of projected next cycle fuel (Cycle 27). As provided in Reference 6, the conditions through the end of Cycle 26 result in less decay heat in its limiting bundle than the limiting bundle used from Cycle 27. Second, the masses of fuel bundle assembly hardware pieces, such as the channel box and tie plates are credited, which reduces the required decay time.

U.S. Nuclear Regulatory Commission License Amendment Request Docket Nos. 50-219 and 72-15 October 22, 2018 Page 3 The revised adiabatic calculation provided in Attachment 2, factoring in these reconsidered assumptions, validates the response in Reference 6 and results in a reduced decay period of 9.38 months (285 days} for the zirc-fire window after the final reactor shut down. Significant conservatisms remain in the calculation.

Exelon is requesting that License Amendment No 294 (Reference 3} become effective 9.38 months (285 days} from the date of the permanent shut down of OCNGS on September 17, 2018 (Reference 1 }, as stated in the certification that OCNGS has been permanently shut down and defueled (Reference 2), which revises the amendment effective date to June 29, 2019.

License Amendment No. 294 is to become effective 12 months (365 days} following the permanent cessation of power operations and shall be implemented within 60 days of the effective date, but no later than March 28, 2021.

The description, technical and regulatory evaluation, significant hazards determination, and environmental considerations evaluation for the proposed amendment are contained in the. The revised bounding analysis is provided in Attachment 2.

The proposed change of the effective date for the PDEP and Permanently Defueled EAL scheme does not impact or change anything within the approved PDEP (Reference 3} other than the effective and implementation dates.

Exelon requests approval of the proposed license amendment by May 1, 2019, and an effective date of June 29, 2019. Exelon will implement this LAR within 30 days from the effective date; but no later than July 31, 2019. Approval by May 1, 2019, will provide Exelon the certainty in implementing change management for a significant reduction in site staffing.

The proposed change has been reviewed and approved by the station's Safety Review Committee in accordance with the requirements of the Exelon Decommissioning Quality Assurance Program.

In support of this license amendment request, Exelon has discussed the proposed change regarding the earlier implementation of the PDEP and Permanently Defueled EAL scheme with the New Jersey Bureau of Nuclear Engineering and local response organizations.

The proposed change has been evaluated in accordance with 10CFR50.91 (a}(1} using criteria in 1 O CFR 50.92(c}, and Exelon has determined that this change involves no significant hazards consideration. Exelon has also determined that the proposed change satisfies the criteria for categorical exclusion in accordance with 1 O CFR 51.22(c}(9} and does not require an environmental review. Therefore, pursuant to 1 O CFR 51.22(b}, no environmental impact statement or environmental assessment is required.

No commitments to the NRC are made in this letter.

U.S. Nuclear Regulatory Commission License Amendment Request Docket Nos. 50-219 and 72-15 October 22, 2018 Page4 If you have any questions concerning this submittal, please contact Paul Bonnett at (61 O) 765-5264.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 22nd day of October 2018.

Respectfully, lhtvrkf~~~

Michael P. Gallagher Vice President, License Renewal & Decommissioning Exelon Generation Company, LLC :

Description and Evaluation of Proposed Changes :

Oyster Creek Nuclear Generating Station Zirconium Fire Analysis for Drained Spent Fuel Pool, C-1302-226-E310-457, Revision 1 cc:

w/Attachment Regional Administrator - NRC Region I NRC Senior Resident Inspector - Oyster Creek Nuclear Generating Station NRC Project Manager, NRR - Oyster Creek Nuclear Generating Station Director, Bureau of Nuclear Engineering - New Jersey Department of Environmental Protection Mayor of Lacey Township, Forked River, NJ Oyster Creek Nuclear Generation Station Description and Evaluation of Proposed Changes License Amendment Request Oyster Creek Nuclear Generating Station Docket No. 50-219 EVALUATION OF PROPOSED CHANGES

Subject:

Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme 1.0

SUMMARY

DESCRIPTION

2.0 BACKGROUND

3.0 BASIS FOR PROPOSED CHANGES

4.0 TECHNICAL EVALUATION

5.0 REGULATORY EVALUATION

5.1 Applicable Regulatory Requirements and Guidance 5.2 Precedent 5.3 No Significant Hazards Consideration Determination 5.4 Conclusion

6.0 ENVIRONMENTAL CONSIDERATION

S

7.0 REFERENCES

License Amendment Request Permanently Defueled Emergency Plan Proposed Effective and Implementation Dates Change 1.0

SUMMARY

DESCRIPTION Page 1 of 6 Pursuant to 1 O CFR 50.90, "Application for amendment of license or construction permit, "Exelon Generation Company, LLC (Exelon) requests an amendment to Renewed Facility Operating License Number DPR-16 for Oyster Creek Nuclear Generating Station (OCNGS). The proposed amendment would revise the effective and implementation dates of License Amendment No. 294, Permanently Defueled Emergency Plan (PDEP), Emergency Action Level (EAL) scheme for the permanently defueled condition, and associated Exemption from portions of 1 O CFR 50.47(b),

1 O CFR 50.47(c)(2), and 1 O CFR Part 50, Appendix E,Section IV. The proposed changes are being submitted to the U.S. Nuclear Regulatory Commission (NRG) for approval prior to implementation.

The proposed change of the effective date for the PDEP, Permanently Defueled EAL scheme, and associated exemptions does not impact or change anything within the approved PDEP (Reference 5) or exemptions (Reference 6) other than the effective and implementation dates.

2.0 BACKGROUND

On January 7, 2011, Exelon informed the NRG that OCNGS will permanently cease power operations by December 31, 2019 (Reference 1 ). On February 2, 2018, Exelon announced that it planned to retire OCNGS no later than October 31, 2018 at the end of the current two-year operating cycle. Exelon informed the NRG of this change in Reference 2.

On September 17, 2018, OCNGS permanently ceased power operations (Reference 3). By letter dated September 25, 2018, (Reference 4), Exelon certified that all fuel had been permanently removed from the OCNGS reactor vessel and placed in the spent fuel pool (SFP).

On October 17, 2018, the NRG approved License Amendment No. 294, OCNGS PDEP and Permanently Defueled EAL Scheme (Reference 5). The PDEP and Permanently Defueled EAL scheme were predicated on approval of requests for Exemptions from portions of 10 CFR 50.47(b), 1 O CFR 50.47(c)(2), and 1 O CFR Part 50, Appendix E,Section IV, which were approved on October 16, 2018 (Reference 7).

License Amendment No. 294 becomes effective 12 months (365 days) following the permanent cessation of power operations and shall be implemented within 60 days of the effective date, but no later than March 28, 2021.

3.0 BASIS FOR PROPOSED CHANGES The basis for the approval of the exemptions from offsite emergency preparedness (EP) requirements included a site-specific analysis that showed that the fuel stored in the SFP would not reach the zirconium ignition temperature in fewer than 1 O hours from the time at which it was assumed a loss of both water and air cooling of the spent fuel. Exelon's site-specific analyses for OCNGS, as provided in Exelon's exemption request (Reference 7), showed that 12 months after permanent cessation of power operations, the spent fuel stored in the SFP will have decayed to the extent that the requested exemptions may be implemented at OCNGS.

Since the time of the submittal of the original adiabatic calculation in Reference 7, two key assumptions have been reconsidered based on actual conditions at the time of final shutdown.

First, the fuel in the reactor at the time of the final shutdown (Cycle 26) was considered instead of projected next cycle fuel (Cycle 27). When the original calculation was submitted, OCNGS was

License Amendment Request Permanently Defueled Emergency Plan Proposed Effective and Implementation Dates Change Page 2 of 6 scheduled to shut down no later than the end of December 2019 (Reference 1) and a refueling outage in October 2018 was scheduled to load fuel for Cycle 27. However, Exelon decided to reschedule the final shutdown to no later than October 31, 2018 (Reference 2), at the end of the current two-year operating cycle (Cycle 26). A revised adiabatic calculation (provided in ) was performed that calculates new decay heat values and the required decay time based on the revised final shutdown date at OCNGS, which no longer includes Cycle 27, such that, Cycle 26 becomes the final and bounding reload.

Second, the masses of fuel bundle assembly hardware pieces, such as the channel box and tie plates are credited, which reduces the required decay time. The revised adiabatic calculation (provided in Attachment 2) factors in the reconsidered assumptions and the results indicate that the 12-month decay period originally predicted in Reference 7 may be reduced to 9.38 months (285 days) after the final reactor shut down.

Significant conservatisms remain in the calculation such as:

Adiabatic heat up of the fuel bundle is utilized thus not accounting for the actual heat losses that would occur due to radiative and convective heat transfer to surrounding structures.

The calculation assumed power level was at 100% up to when shutdown occurred.

Reactor power level was 70% for 51 days prior to final shutdown. The reduced power level results in a reduction in the starting decay heat that would be present in the actual hottest fuel bundle.

The specific heat for fuel assembly hardware pieces (stainless steel or lnconel) were assumed to be the lower specific heat of zircalloy. Actual fuel heat-up would be slower with actual materials.

Starting temperature of the spent fuel pool was assumed to be 125°F instead of normal pool temperatures of less than 115°F. Lower temperature adds additional time to fuel heat-up.

The revised decay time is consistent with NRC's stated generic time for Boiling Water Reactors (BWRs) as documented in NUREG/CR-6451 BNL-NUREG-52498, "A Safety and Regulatory Assessment of Generic BWR and PWR [Pressurized Water Reactor] Permanently Shutdown Nuclear Power Plants" (Reference 8) and the Regulatory Basis document for "Regulatory Improvements for Power Reactors Transitioning to Decommissioning" (Reference 9). Oyster Creek is a lower power density plant than the BWR referenced in above documents; therefore, OCNGS would be expected to have a site-specific calculation that would be less than the generic required decay time.

Therefore, Exelon is requesting that the License Amendment No. 294 (Reference 5) become effective 9.38 months (285 days) from the date of the permanent shut down of OCNGS on September 17, 2018, as stated in the certification that OCNGS has been permanently shut down and defueled (Reference 4), which revises the amendment effective date to June 29, 2019.

4.0 TECHNICAL EVALUATION

As discussed above, based on actual conditions at the time of final shutdown, Exelon has revised the site-specific analysis that showed that the fuel stored in the SFP would not reach the zirconium ignition temperature in fewer than 1 O hours from the time at which it was assumed a loss of both water and air cooling of the spent fuel based on reconsideration of two key assumptions. The

License Amendment Request Permanently Defueled Emergency Plan Proposed Effective and Implementation Dates Change Page 3 of 6 revised analysis, "Oyster Creek Nuclear Generating Station Zirconium Fire Analysis for Drained Spent Fuel Pool" (Revision 1 ), is provided in Attachment 2.

5.0 REGULATORY EVALUATION

5.1 Applicable Regulatory Requirements and Guidance Exelon intends to meet the applicable emergency regulatory requirements with the Exemptions approved in Reference 6 and license provisions approved in License Amendment No. 294 (Reference 5).

5.2 Precedent The proposed change revises the effective and implementation dates of License Amendment No.

294, OCNGS PDEP, Permanently Defueled EAL scheme (Reference 5), and Exemptions from portions of 1 O CFR 50.47 and 1 O CFR Part 50, Appendix E (Reference 6). Three similarly related license amendments involving changes to license amendment implementation due dates were approved in 2015 and 2004, and are listed below:

1. Limerick Generating Station, Unit 2 - Issuance of Exigent Amendment RE: Extend Implementation Period for Amendment No. 174-Leak Detection System Setpoint and Allowable Value Changes (TAC NO.

MF5695),

dated February 25, 2015 (ML 150049A084).

2. Sequoyah Nuclear Plant Unit 1 (SON) - Issuance of Emergency Amendment to Extend Implementation Period for License Amendment No. 294 (TAC NO. MC5041 ), dated November 9, 2004 (ML043130006).

3. Fort Calhoun Station, Unit No.1 - Issuance of Amendment (TAC No. MC1949), dated February 13, 2004 (ML040490383).

5.3 No Significant Hazards Consideration Determination The proposed change would revise the effective and implementation dates of License Amendment No. 294, Oyster Creek Nuclear Generating Station (OCNGS) Permanently Defueled Emergency Plan (PDEP) and Emergency Action Level (EAL) scheme (Reference 5)

[ML18221A400] and Exemptions from portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (Reference 6) [ML 182220A980]. Implementation of the previously approved PDEP, Permanently Shutdown EALs, and associated Exemptions are predicated on a site-specific analysis that showed that the fuel stored in the spent fuel pool (SFP) would not reach the zirconium ignition temperature in fewer than 1 O hours from the time at which it was assumed a loss of both water and air cooling of the spent fuel at 12 months after the reactor had been shut down (zirc-fire window). The site-specific analysis has been revised to take into consideration actual conditions at the time of permanent shutdown that impact two key assumptions used in the original analysis. The revised site-specific analysis showed that the zirc-fire window may be revised to 9.38 months (285 days) after the reactor had been shutdown.

Pursuant to 1 o CFR 50.92, Exelon has reviewed the proposed changes and concludes that the changes do not involve a significant hazards consideration because the proposed changes satisfy the criteria in 1 O CFR 50.92(c). These criteria require that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different

License Amendment Request Permanently Defueled Emergency Plan Proposed Effective and Implementation Dates Change Page 4 of 6 kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.

The discussion below addresses each of these criteria and demonstrates that the proposed amendment does not constitute a significant hazard.

1.

Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The proposed change to the effective and implementation dates of License Amendment No. 294, OCNGS PDEP, Permanently Shutdown EAL scheme, and associated Exemptions at 9.38 months (285 days) does not impact the function of plant structures, systems, or components (SSCs). The proposed change does not affect accident initiators or precursors, nor does it alter design assumptions. The proposed change does not prevent the ability of the on-shift staff and emergency response organization (ERO) to perform their intended functions to mitigate the consequences of any accident or event that will be credible in the permanently defueled condition.

The probability of occurrence of previously evaluated accidents is not increased, since most previously analyzed accidents can no longer occur and the probability of the few remaining credible accidents are unaffected by the proposed amendment.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2.

Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No The proposed change to effective and implementation dates for License Amendment No.

294, PDEP, Permanently Shutdown EAL scheme, and associated Exemptions at 9.38 months (285 days) is commensurate with the hazards associated with a permanently shutdown and defueled facility based on the updated site-specific analysis that showed the fuel stored in the SFP would not reach the zirconium ignition temperature in fewer than 1 O hours from the time at which it was assumed a loss of both water and air cooling of the spent fuel. The proposed change does not involve installation of new equipment or modification of existing equipment, so that no new equipment failure modes are introduced. In addition, the proposed change does not result in a change to the way that the equipment or facility is operated so that no new or different kinds of accident initiators are created.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.

3.

Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No Margin of safety is associated with confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant system pressure boundary, and containment structure)

License Amendment Request Permanently Defueled Emergency Plan Proposed Effective and Implementation Dates Change Page 5 of 6 to limit the level of radiation dose to the public. The proposed change is associated with changing the effective and implementation dates of License Amendment No. 294, PDEP, Permanently Shutdown EAL scheme and associated Exemptions; it does not impact operation of the plant or its response to transients or accidents. The change does not affect the Technical Specifications. The proposed change does not involve a change in the method of plant operation, and no design bases accident analyses will be affected by the proposed changes. Safety analysis acceptance criteria are not affected by the proposed changes. The PDEP will continue to provide the necessary response staff with the appropriate guidance to protect the health and safety of the public.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Based on the above, Exelon concludes that the proposed change presents no significant hazards consideration under the standards set forth in 1 O CFR 50.92{c), and, accordingly, a finding of "no significant hazards consideration" is justified.

5.4 Conclusion In conclusion, based on the considerations discussed above: 1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, 2) such activities will be conducted in compliance with Commission's regulations, and 3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6.0 ENVIRONMENTAL CONSIDERATION

S This amendment request meets the eligibility criteria for categorical exclusion from environmental review set forth in 1 O CFR 51.22(c)(9) as follows:

(i)

The amendment involves no significant hazards consideration.

As described in Section 5.3 of this evaluation, the proposed changes involve no significant hazards consideration.

(ii)

There is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite.

The proposed changes do not involve any physical alterations to the plant configuration or any changes to the operation of the facility that could lead to a change in the type or amount of effluent release offsite.

(iii) There is no significant increase in individual or cumulative occupational radiation exposure.

The proposed changes do not involve any physical alterations to the plant configuration or any changes to the operation of the facility that could lead to a significant increase in individual or cumulative occupational radiation exposure.

Based on the above, Exelon concludes that the proposed change meets the eligibility criteria for categorical exclusion as set forth in 10 CFR 51.22{c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

License Amendment Request Permanently Defueled Emergency Plan Proposed Effective and Implementation Dates Change 7.0 REFERENCES Page 6 of 6

1. Letter from Keith R. Jury, Exelon Generation Company, LLC to U.S. Nuclear Regulatory Commission - "Permanent Cessation of Operations at Oyster Creek Nuclear Generating Station," dated January 7, 2011, (ML110070507)

2. Letter from Michael P. Gallagher, Exelon Generation Company, LLC to U.S. Nuclear Regulatory Commission -

"Certification of Permanent Cessation of Power Operations for Oyster Creek Nuclear Generating Station," dated February 14, 2018 (ML18045A084}

3. Electronic Mail Capture from John Lamb (U.S. Nuclear Regulatory Commission) to David Helker (Exelon Generation Company, LLC), "Oyster Creek Permanently Ceases Power Operations," dated September 17, 2018 (ML18263A163)

4. Letter from Michael P. Gallagher, Exelon Generation Company, LLC to U.S. Nuclear Regulatory Commission -

"Certification of Permanent Removal of Fuel from the Reactor Vessel for Oyster Creek Nuclear Generating Station," dated September 25, 2018 (ML18268A258)

5. Letter from U.S. Nuclear Regulatory Commission to Bryan C. Hanson (Exelon Generation Company, LLC) - "Oyster Creek Nuclear Generating Station - Issuance of Amendment Re:

Changes the Emergency Plan for Permanently Defue/ed Emergency Plan and Emergency Action Level Scheme (GAG NO. MG0160; EPID L-2017-LLA-0307), "dated October 17, 2018 (ML18221A400)

6. Letter from U.S. Nuclear Regulatory Commission to Bryan C. Hanson (Exelon Generation Company, LLC) - "Oyster Creek Nuclear Generating Station - Exemptions from Certain Emergency Planning Requirements and Related Safety Evaluation (GAG NO. MG0153; EPID L-2017-LLE-0020)," dated October 16, 2018 (ML18220A980)

7. Letter from Michael P. Gallagher, (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission - "Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E," dated August 22, 2017(ML17234A082)

8. U.S. Nuclear Regulatory Commission, NUREG/CR-6451 BNL-NUREG-52498, "A Safety and Regulatory Assessment of Generic BWR and PWR Permanently Shutdown Nuclear Power Plants," dated August 1997 (ML082260098)

9. U.S. Nuclear Regulatory Commission, "Regulatory Improvements for Power Reactors Transitioning to Decommissioning, Regulatory Basis Document" dated November 20, 2017, NRG Docket ID: NRC-2017-0070, RIN Number: 3150-AJ59 (ML17215A010)

Oyster Creek Nuclear Generation Station Zirconium Fire Analysis for Drained Spent Fuel Pool, C-1302-226-E310-457, Revision 1

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624353 Station(s): '

Unit No.:*

Discipline:

Descrip. Code/Keyword: **

Safety/QA Class:

System Code: "

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Document No.:

C-1302-226-EJ 10-458, RO GEH-0000-0118-3544, R1 DB-0011.03, R1 26A7584,RO OCNGS 1

MECH NIA NSR NIA SFP Revision:* 0 Component(s): **

NIA CONTROLLED DOCUMENT REFERENCES '"

From/To Document No.:

From From From From From/To Is this Design Analysis Safeguards Information?"

Yes 0 No 181 If yes, see SY-AA-101-106 Does this Design Analysis contain Unverified Assumptions? "

Yes 0 No 181 If yes, ATl/AR#: ------1 This Design Analysis SUPERCEDES:,.

N/A in its entirety.

Description of Revision (list changed pages when all pages of original analysis were not changed): **

Revision 1 calculates new decay heat values and the required decay time based on the revised final shutdown date at Oyster Creek, which will no longer have a Cycle 27 such that Cycle 26 becomes the final and bounding reload. Furthermore, the masses of assembly hardware pieces such as the channel box and tie plates are credited, which reduces the required decay time. This revision replaces all pages in the calculation.

Preparer: 10 Brian Froese

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CC-AA-103-1003 Revision 13 C-1302-226-E310-457 Rev. 1 Page 2 of 41 Owner's Acceptance Review checklist for External Design Analysis Page 1of3 Design Analysis No.: C-1302-226-E310-457 Rev:.!

Contract#: 00597114 Release #: 101 No Question Instructions and Guidance Yes/ No/N/A 1

Do assumptions have All Assumptions should be stated in clear terms with enough

~ LJ LJ sufficient documented justification to confirm that the assumption is conservative.

rationale?

For example, 1) the exact value of a particular parameter may not be known or that parameter may be known to vary over the range of conditions covered by the Calculation. It is appropriate to represent or bound the parameter with an assumed value. 2) The predicted performance of a specific piece of equipment in lieu of actual test data. It is appropriate to use the documented opinion/position of a recognized expert on that equipment to represent predicted equipment performance.

Consideration should also be given as to any qualification testing that may be needed to validate the Assumptions. Ask yourself, would you provide more justification if you were performing this analysis? If yes, the rationale is likely incomplete.

2 Are assumptions Ensure the documentation for source and rationale for the

~ LJ D compatible with the assumption supports the way the plant is currently or will be way the plant is operated post change and they are not in conflict with any operated and with the design parameters. If the Analysis purpose is to establish a licensing basis?

new licensing basis, this question can be answered yes, if the assumption supports that new basis.

3 Do all unverified If there are unverified assumptions without a tracking D D ~

assumptions have a mechanism indicated, then create the tracking item either tracking and closure through an ATI or a work order attached to the implementing mechanism in place?

WO. Due dates for these actions need to support verification prior to the analysis becoming operational or the resultant plant change being op authorized.

4 Do the design inputs The origin of the input, or the source should be identified and

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rationale?

If not, then the source should be attached to the analysis. Ask yourself, would you provide more justification if you were performing this analysis? If yes, the rationale is likely incomplete.

5 Are design inputs The expectation is that an Exelon Engineer should be able to

~ D D correct and reasonable clearly understand which input parameters are critical to the with critical parameters outcome of the analysis. That is, what is the impact of a identified, if change in the parameter to the results of the analysis? If the aooropriate?

impact is laroe, then that parameter is critical.

6 Are design inputs Ensure the documentation for source and rationale for the

~ D D compatible with the inputs supports the way the plant is currently or will be way the plant is operated post change and they are not in conflict with any operated and with the design parameters.

licensinQ basis?

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Revision 13 C-1302-226-E310-457 Rev. 1 Page 3 of 41 Owner's Acceptance Review checklist for External Design Analysis Page 2 of 3 Design Analysis No.: C-1302-226-E310-457 Rev: 1 No Question Instructions and Guidance Yes/ No/ N/A 7

Are Engineering See Section 2.13 in CC-AA-309 for the attributes that are D D ~

Judgments clearly sufficient to justify Engineering Judgment. Ask yourself, documented and would you provide more justification if you were performing justified?

this analysis? If yes, the rationale is likely incomplete.

8 Are Engineering Ensure the justification for the engineering judgment D D ~

Judgments compatible supports the way the plant is currently or will be operated with the way the plant is post change and is not in conflict with any design operated and with the parameters. If the Analysis purpose is to establish a new licensing basis?

licensing basis, then this question can be answered yes, if the judgment suooorts that new basis.

9 Do the results and Why was the analysis being performed? Does the stated 181 D D conclusions satisfy the purpose match the expectation from Exelon on the proposed purpose and objective of application of the results? If yes, then the analysis meets the Design Analysis?

the needs of the contract.

10 Are the results and Make sure that the results support the UFSAR defined 181 D D conclusions compatible system design and operating conditions, or they support a with the way the plant is proposed change to those conditions. If the analysis operated and with the supports a change, are all of the other changing documents licensing basis?

included on the cover sheet as impacted documents?

11 Have any limitations on Does the analysis support a temporary condition or D D ~

the use of the results procedure change? Make sure that any other documents been identified and needing to be updated are included and clearly delineated in transmitted to the the design analysis. Make sure that the cover sheet appropriate includes the other documents where the results of this organizations?

analysis provide the input.

12 Have margin impacts Make sure that the impacts to margin are clearly shown D LJ ~

been identified and within the body of the analysis. If the analysis results in documented reduced margins ensure that this has been appropriately appropriately for any dispositioned in the EC being used to issue the analysis.

negative impacts (Reference ER-AA-2007)?

13 Does the Design Are there sufficient documents included to support the 181 D D Analysis include the sources of input, and other reference material that is not applicable design basis readily retrievable in Exelon controlled Documents?

documentation?

14 Have all affected design Determine if sufficient searches have been performed to 181 D D analyses been identify any related analyses that need to be revised along documented on the with the base analysis. It may be necessary to perform Affected Documents List some basic searches to validate this.

(AOL) for the associated Configuration Change?

15 Do the sources of inputs Compare any referenced codes and standards to the current 181 D D and analysis design basis and ensure that any differences are reconciled.

methodology used meet If the input sources or analysis methodology are based on committed technical and an out-of-date methodology or code, additional reconciliation regulatory may be required if the site has since committed to a more requirements?

recent code

CC-AA-103-1003 Revision 13 C-1302-226-E310-457 Rev. 1 Page 4 of 41 Owner's Acceptance Review checklist for External Design Analysis Page 3 of 3 Design Analysis No.: C-1302-226-E310-457 Rev:.1 No Question Instructions and Guidance Yes I No IN/A 16 Have vendor supporting Based on the risk assessment performed during the pre-job LJ D technical documents brief for the analysis (per HU-AA-1212), ensure that and references sufficient reviews of any supporting documents not provided (including GE DRFs) with the final analysis are performed.

been reviewed when necessarv?

17 Do operational limits Ensure the Tech Specs, Operating Procedures, etc. contain LJ support assumptions operational limits that support the analysis assumptions and and inputs?

inputs.

18 List the critical characteristics of the product, and validate those critical characteristics.

Create an SFMS entry as required by CC-AA-4008. SFMS Number: _...... 6

...... 2...... 6...... 7..... 7 ______ _

Exelon Reviewer Comments:

An HU-AA-1212 pre-job brief for owner's acceptance was held on 3/15/17 with the DEM and Exelon acceptance reviewer. The overall risk ranking was a '1,' therefore, existing in-process reviews are sufficient. An ITPR is not required. The brief did identify that additional technical expertise was required as allowed by CC-AA-103-1003 in the form of a review committee. Technical experts in Nuclear Fuels (Jill Fisher), Reactor Engineering (Jim Frank), Oyster Creek Emergency Plan (Jim Frank), and ORIG EN program SME (Greg Heasley) were utilized to support the Exelon owner's acceptance review. The Exelon acceptance reviewer (Robert Csillag) acted as chair of this committee and coordinated all Exelon reviews performed per CC-AA-103-1003, Attachment 2 and resolution of all comments.

LJ Enercon was verified to be on the approved vendor list as an EOC per CC-AA-12, Attachment 1, therefore, a design review by Exelon is not required. Design qualifications were verified to be current for the Exelon owner's acceptance reviewer as was verification of being part of the ESP population.

Critical inputs and assumptions were scrutinized as was the veracity of the conclusions. Comments were supplied by the Exelon owner review committee. All comments were resolved to the satisfaction of the Exelon owner's review committee by the EOC.

Additional comment from ORIGEN Program SME Greg Heasley:

The method used in Attachment 2 to determine the decay heat used the bundle spec power. It was determined a Cycle 26 3rd burned bundle with higher power and exposure will produce approximately a 6% higher decay heat at 1 year. Due to the following conservatisms in the calculation, the zirc fire analysis performed herein is bounding: (1) No credit is taken for decay time between cycles, (2) stainless steel and lnconel in bundles are assumed to be Zirc-2, which has a considerably (>50%) lower specific heat, (3) conservatively assuming the pool starts at 125°F instead of 86°F (Section 5.6), and (4) conservatively not crediting the SFP rack material (Assumption 3.6) which has been demonstrated to reduce the cooling time by up to 50% in NRC-2015-0070-0224.

IZI

~

Contents C-1302-226-E310-457 Rev. 1 Page 5of41

1.0 Purpose and Scope

............................................................................................................................ 6 2.0 Acceptance Criteria........................................................................................................................... 6 3.0 Assumptions...................................................................................................................................... 6 4.0 References........................................................................................................................................ 7 5.0 Input Data......................................................................................................................................... 8 5.1 Zirconium Properties..................................................................................................................... 8 5.2 Uranium Properties....................................................................................................................... 8 5.3 Geometry for Limiting Assemblies................................................................................................ 8 5.4 Additional Hardware Masses........................................................................................................ 9 5.5 Heat Load...................................................................................................................................... 9 5.6 Water Temperature........................................................................................................................ 10 6.0 Identification of Computer Codes................................................................................................... 10 7.0 Method of Analysis......................................................................................................................... 10 8.0 Numeric Analysis............................................................................................................................. 13 9.0 Results and Conclusions.................................................................................................................. 14

1.0 Purpose and Scope

C-1302-226-E310-457 Rev. 1 Page 6 of41 The purpose of this calculation is to conservatively evaluate the length of time it takes for an uncovered spent fuel assembly in the spent fuel pool to reach the temperature where the zirconium cladding would fail. This analysis supports decommissioning of Oyster Creek Nuclear Generating Station (OCNGS).

Specifically, this analysis will be used to reduce the emergency planning staff once the hottest fuel assembly decay time is sufficient and is demonstrated to reach 900°C in 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months which supports the requirements of ISG-02, Section 5, Item 2 (Ref. 9).

The number of hours it takes for the fuel to heat up (the heat-up time) is determined as a function of the decay time after shutdown. The heat load from GNF2 fuel used in this analysis is determined in. Note, the heat load was previously taken from Attachment 8 of Reference 1 in Revision 0 of this calculation.

2.0 Acceptance Criteria There are no specific acceptance criteria for this analysis; however, SECY-99-168 (Ref. 8) suggests that "10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months (is) sufficient time to take mitigative action" and that for BWRs, 2 years is expected to be the decay time needed to reach a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months heat-up time from 30 °C to 900 °C. NUREG-1738 shows that a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months heat up time for a BWR requires less than 2 years of cooling time (Ref. 7, Fig. 2-1).

NUREG/CR-6451 (Ref. 6) presents several studies discussing the maximum allowable temperature of zirconium cladding that will ensure that failure of the zirconium cladding will not occur. NUREG/CR-6451 states 565 °C (1049 "F) is the lowest temperature where incipient cladding failure might occur. Per NUREG-1738 (Ref. 7, pg. 3-7), 900°C (1652 °F) is the temperature where "runaway oxidation" (zirconium fire) is expected to occur. Therefore, the decay period to reach a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months heat-up time from 30 *c (86 °F) to 900

°C is used as the acceptance criteria in this calculation. The decay period to reach a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months heat-up time from 30 *c to 565 *c is also presented to show when cladding failure may occur.

NRC-2015-0070, Appendix A, Section 4.2.6 (Ref. 17) states that for BWRs a 10 month period for Level 1 (post-shutdown emergency planning) shall be used unless a site-specific analysis demonstrates a shorter time period is acceptable for reaching a cladding temperature of 900 °C within 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

3.0 Assumptions 3.1 The heat-up time is conservatively assumed to start when the spent fuel pool has been completely drained. This is conservative as the drain down time would increase the time to cladding failure.

3.2 Additional hardware materials made of stainless steel and lnconel X-750 are assumed to be zircaloy-2. This assumption is conservative since the specific heat capacity of zircaloy-2 is less than that of both stainless steel and lnconel X-750. For instance, at 300K (-70"F) the specific heat of zircaloy-2 is 0.28x103 J/kg*K (Reference 4), stainless steel is 0.50x103 J/kg*K (Reference 4), and

C-1302-226-E310-457 Rev. 1 Page 7 of 41 lnconel X-750 is 0.43x103 J/kg*K (0.103 Btu/lb*"F) (Reference 14). A lower specific heat capacity is conservative because it results in a shorter heat-up time.

3.3 OCNGS final cycle 26 will contain a full core of GNF2 fuel (Ref. 12); therefore, the analysis herein will only evaluate the heat up of GNF2 fuel assemblies and not any other assembly type in the spent fuel pool because the offloaded fuel directly after a cycle contains the assemblies with the highest decay heat (referred to as the hottest fuel assembly here-in).

3.4 The specific heat for uranium dioxide and the zircaloy-2 cladding are determined at a temperature of 500°F. A temperature of 500 "Fis in the temperature range (approximately the midpoint of both ranges) for this analysis. From Reference 4, the specific heat slightly increases with an increase in temperatures; at higher temperatures, the uranium dioxide and zircaloy-2 would heat up more slowly. Thus, using a temperature at the midpoint for material properties is conservative with respect to the assembly heat-up. This temperature is used as representative of the full temperature range in this analysis.

3.5 This analysis conservatively assumes that there is no air cooling of the assemblies (i.e., adiabatic conditions): the flow paths that would provide natural circulation cooling are assumed to be blocked.

3.6 The fuel assembly material is assumed to start at a uniform temperature and heat up at uniform rate. While there are temperature gradients throughout the assemblies, these are small relative to the total heat up from 125 "F (Input 5.6) to either 1049 "F for cladding failure or 1652 "F for zirconium fire. Furthermore, this simplified approach is still conservative overall since convective and radiative heat transfer are not considered, nor is conduction to other structural materials such as the SFP racks.

3.7 Gadolinium, which is a burnable poison and can be used in some fuel rods (Reference 2), is conservatively not included in this evaluation.

4.0 References

1.

C-1302-226-E310-458, Rev. 0, "Dose at Exclusion Area Boundary and Control Room Due to Shine from Drained Spent Fuel Pool During SAFSTOR".

2.

TODI NF172795, Rev.a, "Transmit GNF2 Dimensional Data for Oyster Creek".

3.

OCNGS Technical Specification 5.3.1, Amendment No. 223.

4.

Glasstone and Sesonske, Nuclear Reactor Engineering, Van Nostrand Reinhold Company, 1981.

(Attachment 1)

5. GEH-0000-0118-3544, Rev. 1, "GNF2 Fuel Design Cycle-Independent Analyses for Exelon Oyster Creek Generating Station".

6.

NUREG/CR-6451, "A Safety and Regulatory Assessment of Generic BWR and PWR Permanently Shutdown Nuclear Power Plants", August 1997 (ML082260098).

7.

NUREG-1738, "Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants", February 2001 (ML010430066).

8.

SECY-99-168, "Improving Decommissioning Regulations for Nuclear Power Plants", June 30, 1999 (ML992800087).

C-1302-226-E310-457 Rev.1 Page 8 of 41

9.

NSIR/DPR-ISG-02, "Emergency Planning Exemption Requests for Decommissioning Nuclear Power Plants", May 11, 2015.

10. ORNL/TM-2005/39, SCALE 6.1, User's Manual, June 2011.

11. lncropera & DeWitt, "Fundamentals of Heat and Mass Transfer, Third Edition, John Wiley &

Sons, Inc., 1990

12. NF183597, Rev. 0, Oyster Creek Unit 1 Cycle 26 EOC Zirc Fire Calculation Inputs. (Attachment 3)

13. 26A7584, Rev. 0, GNF2 BWR/2-3 Fuel Bundle Weights (proprietary).

14. lnconel X-750 Technical Bulletin, Special Metals,

<http://www.specia Im eta ls.com/ assets/smc/documents/ alloys/inconel/inconel-alloy-x-750. pdf>

(accessed 2/19/2018). (Attachment 4)

15. GNF2 Product Sheet, General Electrical, <https://nuclear.gepower.com/fuel-a-plant/products/gnf2-advantage> (accessed 2/20/2018). (Attachment 5)

16. DB-0011.03, Rev. 1, GNF2 Design Basis (proprietary).

17. NRC-2015-0070, Regulatory Improvements for Power Reactors Transitioning to Decommissioning, RIN Number 3150-AJ59, November 20, 2017.

5.0 Input Data 5.1 Zirconium Properties The cladding for the GNF2 fuel is zircaloy-2 (Ref. 5). The specific heat of zircaloy-2 at 500°F (533 K)

(Assumption 3.4) is 0.0761 Btu/ lbm-°F (Ref. 5, p. 89) and the density of zircaloy-2 is 6.56 g/cm3 (409.53 lb/ft3) (Ref. 10). The GNF2 channel is also zirconium alloy (Reference 15).

5.2 Uranium Properties The specific heat of uranium dioxide at 500 °F (533 K) (Assumption 3.4) is 0.0683 Btu/ lbm-°F (Ref. 5, p. 89) and the density of uranium dioxide is 10.6 g/cm3 (661.74 lb/ ft3) (Ref. 5, p. 19).

5.3 Geometry for Limiting Assemblies The table below shows the geometry inputs for the fuel assemblies used in this analysis. OCNGS's final cycle before decommissioning will contain a full core of GNF2 fuel (Assumption 3.3); therefore, the analysis herein will only evaluate the heat up of GNF2 fuel assemblies and not any other assembly type in the spent fuel pool because the offloaded fuel directly after a cycle is the hottest fuel assemblies in the pool. Table 1 contains fuel assembly input data for GNF2 fuel.

C-1302-226-E310-457 Rev. 1 Page 9 of 41 Table 1: Fuel Assembly Inputs for GNF2 Fuel Number of Heated Rods 92 rods Reference 5 Number of Water Rods 2 rods Reference 5 Number of 2/3 Length Part Length 8 rods Reference 5 Rod Number of 3/8 Length Part length 6 rods Reference 5 Rod Length of 2/3 Part Length Rod 102 inches Reference 2 and 5 Length of 3/8 Part Length Rod 54inches Reference 2 and 5 Uranium Pellet Diameter 0.3496 inches Reference 2 Outer Diameter of Water Rods 0.980 inches Reference 2 Inner Diameter of Water Rods 0.920 inches Reference 2 Outer Diameter of Cladding 0.404 inches Reference 2 Inner Diameter of Cladding 0.3567 inches Reference 2 Heated Length of Rods 145.24 inches Reference 2 Channel Width 5.283 inches Reference 16 Channel Thickness 0.050 inches Reference 16 5.4 Additional Hardware Masses From Reference 13, the following additional hardware masses are also accounted for in calculating heat-up durations.

Table 2: Additional GNF2 Hardware Masses (Reference 13)

Component Mass (lb)

Material End plugs 5.66 Zircaloy-2 Upper tie plate, lower tie plate, lock tab 19.92 Stainless Steel washers and hex nuts, and retainer springs Spacers and expansion springs 2.77 Alloy X-750 (lnconel)

Total 28.35 Modeled as Zircaloy-2 per Assumption 3.2 5.5 Heat Load determines the maximum heat load from a single fuel assembly, based on the information provided in Attachment 3. The assembly with the highest heat load will have the shortest heat-up time.

The table showing the maximum fuel assembly heat generation rates for several years is in Attachment 2, Table A2-l.

The worst-case (hottest) bundle is one that was discharged at the end of Cycle 26 and has been cooling for nine months.

From Table A2-1, it has a heat load of 1.091xl04 W/MTU. The maximum 0.181368 MTU/assembly value was derived from Cycle 26 data (Reference 12). The worst-case heat per assembly is calculated as follows:

C-1302-226-E310-457 Rev. 1 Page 10of41 1.091£ + 04 W 0.181368 MTU W

Worst - case bundle heat load=

MTU x

bl

= 1979 bl assem y assem y

= 6752 BTU /hr assembly The worst-case bundle heat load is determined at the remaining decay times (1 year, 1.25 years, 1.5 years, etc) using the same methodology.

5.6 Water Temperature The starting temperature for the heat-up analysis is taken as a uniform 125 °F (51 °C). The temperature of 125 °F (51 °C) is the maximum initial pool temperature at or near the surface (Ref. 3). SECY-99-168 (Ref. 8) and NUREG-1738 (Ref. 7) both set the starting water temperature at 30 °C (86 °F), so setting the initial temperature to the maximum pool temperature is conservative.

6.0 Identification of Computer Codes The ORIGEN-ARP module of the SCALE 6.1 code package is used to calculate new decay heat values in of this calculation. This revised model is based on the existing ORIGEN-ARP models developed as part of C-1302-226-E310-458 (Reference 1). Further discussion on the use and application of this software is contained within C-1302-226-E310-458.

7.0 Method of Analysis This analysis determines the heat-up time of the fuel assembly using the thermal capacity of materials.

As discussed in Assumption 3.6, this simplified approach is both reasonable and conservative given the overall temperature range and not accounting for convective or radiative heat transfer in the analysis.

Equation 7-1(Ref.11, Ch. 8):

Where:

!ff cj = m X Cp X-t m = pxV cj is the heat generation rate in BTU/hr mis the mass of material in lb p is the density of the material in lb/ft3 V is the volume of the material in ft3 Cp is the specific heat in BTU/lb- °F llT is the temperature increase in °F t is the heat-up time in hr

C-1302-226-E310-457 Rev. 1 Page 11 of41 For this analysis, there are two materials that are considered: the uranium dioxide fuel pellets and zircaloy-2. Zircaloy-2 comprises the cladding, the water tubes, channel, and the additional hardware (Assumption 3.2), all of which are also being heated. Under adiabatic conditions, zircaloy-2 and the uranium dioxide are modeled as heating up at the same rate, so the ti.; will be the same for both materials.

Equation 7-2:

Where:

tlT q = t x (Pu x Vu x Cp,u + Pz x 11z x Cp,z + mz x Cp,z)

Xu signifies the property is for uranium dioxide Xz signifies the property is for zirconium mz signifies any additional hardware modeled as zirconium This calculation seeks the heat-up time, so Equation 7-2 is solved fort.

Equation 7-3:

t:J.T t = -.- x (Pu x Vu x Cp,u + Pz x 11z x Cp,z + mz x Cp,z) q The volume of uranium is given below.

Equation 7-4:

Where:

Dp is the diameter of the uranium pellet in ft NFL is the number of full length heated rods LFL is the heated length of the full length rods in ft N (i) is the number of 2/3 length heated rods L(i) is the heated length of 2/3 length rods in ft N (i) is the number of 3/8 length heated rods LC!) is the heated length of 3/8 length rods in ft 8

C-1302-226-E310-457 Rev.1 Page 12 of 41 The volume of zircaloy-2 along the heated portion of rods, water rods, and channel are given below. The length ofthe cladding, water rods, and channel that are heated are conservatively modeled as being the same as the heated length of uranium dioxide. In reality, they are longer than the length ofthe uranium dioxide pellets.

Equation 7-5:

Where:

Equation 7-6:

Where:

Equation 7-7:

Where:

Equation 7-8:

Vz,cl is the volume of zircaloy-2 in the cladding of heated tubes Dc,o is the outer diameter of the cladding Dc,i is the inner diameter of the cladding

(

Dw,o 2

Dw,i 2

)

l'z,wr =

Tr X 4

Nwr X LFL l'z.wr is the volume of zircaloy-2 in the water rods Dw,o is the outer diameter ofthe water rods Dw,i is the inner diameter of the water rods Nwr is the number of water rods Vz,ch is the volume of zircaloy-2 in the channel Wch is the channel width thch is the minimum channel thickness l1z = Vz,cl + l'z,wr + Vz,ch

C-1302-226-E310-457 Rev. 1 Page 13 of 41 The temperature increase (~T) for this analysis is taken to be from the initial temperature of the pool, 125"F (51 *q (Input 5.6), to the zirconium cladding failure temperatures of interest, 1049"F (565°C) and 1652"F (900°C) (Acceptance Criteria, Section 2).

The heat-up time is calculated as a function of the decay time for each of the times in Attachment 2. The hottest assembly source term methodology is described in Attachment 2.

8.0 Numeric Analysis The volume of Uranium Dioxide in the hottest fuel assembly is determined below using Equation 7-4:

((

0.3496 in 2

)

((

(0.3496 in) 2

)

C 12 in/ft) 145.24 in 12 in/ft 102 in Vu -

rr x 4

78 rods x

. If

+

Tr x 8 rods x 12. If 12 m t

4 m

t 12 in/ft 54 in 3

((

(0.3496 in)2)

)

+

Tr x 4

6 rods x 12 in/ft = 0.693 ft The volume of zircaloy-2 in the cladding is determined below using Equation 7-5:

12 in/ft -

12 in/ft 145.24 in

((

(0.404 in) 2 (0.3567 in) 2)

)

Vz,cl =

7r x 4

78 rods x 12 in/ft 12in/ft -

12in/ft 102in

((

(0.404 in) 2 (0.3567 in) 2)

)

+

rrx 4

8rodsx12in/ft

((

(0.404 in)2 (0.3567 in)2)

)

12 in/ft -

12 in/ft 54 in 3

+

rr x 6 rods x 2. If

= 0.204ft 4

1 Ln t

The volume of zircaloy-2 in the water rods is determined below using Equation 7-6.

12 in/ft -

12 in/ft 145.24 in 3

(

(0.980 in) 2 (0.920 in) 2) l'z,wr =

7r x 4

2 rods X 12 in/ft = 0.015 ft

The volume of zircaloy-2 in the channel is determined below using Equation 7-7.

C-1302-226-E310-457 Rev. 1 Page 14 of41 5.283 in 0.05 in 145.24 in 3

Vz,ch = 12 in/ft x 12 in/ft x 12 in/ft x 4 = 0.089 ft The total zircaloy-2 volume is then determined below from Equation 7-8:

l1z = 0.204 ft 3 + 0.015 ft 3 + 0.089 ft 3 = 0.308 ft 3 The heat-up time is then determined for end temperatures of 565°C (1049°F) and 900°C (1652°F) using the maximum bundle heat load at different decay times with Equation 7-3. The heat-up time to 1049°F for the nine-month decay maximum bundle (Section 5.5) is shown below; the heat-up for the remaining decay times is solved in the same exact manner (i.e., changing the heat load and keeping the remaining inputs constant) and the results are reported in Section 9. Note, as-presented values may differ slightly due to rounding in Excel.

_ (1049°F - 125°F) (

lb 3

BTU t -

6752 BTU /hr 661.74 ft 3 x 0.693 ft x 0.0683 lbm _ 0 F lb 3

BTU BTU

)

+ 409.53 ft 3 x 0.308 ft x 0.0761lbm_ 0 F + 28.35lb x 0.0761lbm_ 0 F

= 5.89 hours0.00103 days 0.0247 hours 1.471561e-4 weeks 3.38645e-5 months 9.0 Results and Conclusions The results are shown in Table 3.

End Temperature (°C, "F) 565,1049 565,1049 565,1049 565,1049 565,1049 565, 1049 900,1652 900,1652 900,1652 900,1652 900, 1652 900,1652 Table 3: Results Decay Time (years) 0.75 1

1.25 1.5 2

3 0.75 1

1.25 1.5 2

3 Heat-Up Time (hours) 5.89 7.13 8.34 9.56 12.09 17.28 9.74 11.78 13.78 15.81 19.98 28.56

C-1302-226-E310-457 Rev. 1 Page 15 of 41 The 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months heat-up time to a temperature of 565"C {1049 "F), which is when cladding failure is expected, occurs just after 1.5 years. The 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months heat-up time to a temperature of 900"C {1652"F), which is when zirconium fire is expected, occurs at a decay time of 9.38 months {0.78 years). This was conservatively calculated by interpolating between the nine month (0.75 year) and one year times. This aligns with the 10 month decay time for Emergency Planning Level 1 determined in NRC-2015-0070 (Ref. 17).

Figure 1 below shows the heat-up time vs decay time for both temperatures of interest.

30.00 25.00 Iii'

S QJ QJ

.... 20.00 E

0 QJ

J ro QJ c.

E QJ I-15.00 0....

LL Lil N

.-i E

0....

QJ E 10.00 i=

c.

=?

ro QJ

I:

5.00 0.00 9

12 15 18 24 36 Months After Shutdown

_... _. Temperature =565 C (1049 Fl

__._Temperature =900 C (1652 F)

Figure 1: Heat-Up Time vs. Decay Time C-1302*22.f>.E310-457 Rev. 1

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90 0.}8 f f Decay Heat Calculation C-1302-226-E310-457 Rev. 1 Page 17of41 The revised decay heat run is based on the Cycle 26 maximum burnup (48762.3 MWd/MTU), minimum enrichment (3.43%), and maximum MTU (0.181368 MTU/Assy) from Reference 12. Using the same 560 assemblies in the core, power level of 1930 MWt, and GNF2 fuel from Reference 1, the new bounding bundle power level is calculated below:

1 core 1

Bounding Avg. Power Level = 1930 MWt x 560 bl.

x MTU = 19.0024 MWt/ MTU assem ies 0.181368 __

~

assembly This results in a total irradiation period calculated as 48762.3MWd Irradiation Period=

~~ = 2566.11 days 19.0024 MTU These values are used to update the ORIG EN-ARP decay heat model from Reference 1 and the revised input file is included in Attachment 6 of this calculation. Table A8-2 from Attachment 8 of Reference 1 is recreated below using this Cycle 26 fuel information and accounts for the additional assembly hardware mass. This also includes a 9-month (0.75 year) time step due to the increased margin from using this cycle.

Table A2-1: Decay Heat Source Terms from ORIGEN-ARP 0.75 Year 1 Year 1.25 Year 1.5 Year 2 Year 3 Year 5 Year Decay Time Decay Decay Decay Decay Decay Decay Decay (W/MTU)

(W/MTU)

Cycle 26, max.

burnup, min.

1.091E+04 9.018E+03 7.707E+03 6.721E+03 5.318E+03 3.720E+03 2.454E+03 enrichment, max. MTU

D SAFETY RELATED fgJ NON-SAFETY RELATED D REGULATORY RELATED C-1302-226-E310-457 Rev. 1 NUCLEAR FUELS TRANSMITTAL OF DESIGN INFORMATION Originating Organization NF ID#

NF183597 fgJ Nuclear Fuels Revision 0

D Other (specify)

SRRS#

3A.130 PaQe 1 of 18

Subject:

Oyster Creek Unit 1 Cycle 26 EOC Zirc Fire Calculation Inputs Station:

Oyster Creek Unit:

1 Cycle:

26 Generic:

N/A To: Dwayne Blaylock (Enercon)

EC/ECR#: N/A

/1:;h-/:rt !/,,. /

f 4f'".~/t!.

2/16/2018 Ferheen Qureshi Prepared by Signature Date Robert Potter

'/{(;. {)if~~ '

2/16/2018 Reviewed by Signature ~

Date Armando Johnson 16FEB18 Approved by Signature Date Status of Information:

fgJ Verified 0 Unverified 0 Engineering Judgment Action Tracking #for Method and Schedule of Verification N/A for Unverified DESIGN INFORMATION:

Purpose of Information:

Provides inputs to Enercon calculation for "Oyster Creek Nuclear Generating Station Zirconium Fire Analysis for Drained Soent Fuel Pool" assuming a shutdown date of October 151, 2018.

Description of Information/Basis:

This package provides information necessary to revise the "Oyster Creek Nuclear Generating Station Zirconium Fire Analysis for Drained Spent Fuel Pool" which was previously based on the final operating cycle 27 fuel data.

With Exelon decision to shut down Oyster Creek after cycle 26, the calculation is being revised to determine the potential reduction in acceptable decay time for the limiting bundle for the cycle 26 core. The information generated assumes a shutdown date of October 151, 2018.

The following information is included as attachments in this TOOi:

1. Attachment 1: Oyster Creek Cycle 26 Fuel Bundle Inventory

2. : Oyster Creek Cycle 26 Fuel Bundle Identification Array

3. : Oyster Creek Cycle 26 Fuel IAT Map

4. Attachment 4: Oyster Creek Cycle 26 Fuel Bundle Exposure, Uranium Mass, & Enrichment Source of Information (References):

1.

Oyster Creek Unit 1 Cycle 26 Core Loading Plan Rev. 3

2.

Disk6:fReadonlv.OC.C26.Proiect.zircfirelOC1C26D OC 02-12-18.WRP E-Mail:

Hard Co12~l'.

Robert Csillag None.

Supplemental Distribution:

Armando Johnson Brian Froese NCS Controlled Documents Distribution Page 18 of41

BUNDLE NO.

TYPe 6

48 7

12 8

32 9

16 10 16 11 40 12 24 13 16 14 16 15 24 17 48 20 32 21 24 22 24 23 8

24 32 25 8

26 56 27 44 28 8

29 32 SUM=

560 C-1302-226-E310-457 Rev. 1 TOOi NF183597 Rev.O Page 2of18 ATTACHMENT 1: Oyster Creek Cycle 26 Fuel Bundle Inventory FUEL BUt~Dl.E DESCRIPTION CHANHEL CYCU:

BATCH MATERIAL.

LOADED ID RANGE GNF2-P100G2BJ70-16GZ-100l2-145-T6-3J56 ZR2RX 23 JYN41J-JYN460 GNF2-P10DG28369-16GZ-100T2-145-T6-JJ57-l TO ZR2RX 23 JYN501..JYN516 GNF2-P1 ODG2BJ70-16GZ-100T2-145-T6-4137 ZR2RX 24 JYX370..JYX401 GNF2-P10DG2Bl72-14GZ-100T2-145-T6-41J8 ZR4RX 24 JYX426-JYX441 GNF2-P1 ODG2BJ70-15GZ-100T2-145-T6-3355 ZR2RX 23 JYN381..JYN404 GNF2-P1 ODG2BJ71-14GZ-100T2-145-T6-4300 ZR2RX 25 YLD792-YLD831 GNF2-P10DG28371-16GZ-100T2-145-T6-4301 ZR2RX 25 YLD856-YLD879 GNF2-P1 ODG2BJ70-16GZ-1 OOT2-145-T6-J356 ZR4RX 23 JYN461..JYN476 GNF2-P1 ODG2BJ69-16GZ-1 OOT2-145-T6-JJ57-L TO ZR4RX 23 JYN525..JYN540 GNF2-P1 OOG2BJ72-14GZ-100l2-145-T6-41J8 ZR2RX 24 JYX402.JYX425 GNF2-P10DG2BJ71-14GZ-100T2-145-T6-41J6 ZR4RX 24 JYXJ22.JYXJ69 GNF2-P1 ODG2B371-14GZ-100T2-145-T6-41J6 ZR2RX 24 JYX290..JYXJ21 GNF2-P10DG2B369-16GZ-100T2-145-T6-430J ZR2RX 25 YLD888-YLD911 GNF2-P1 ODG2BJ71-14GZ-100T2-145-T6-4JOO ZR4RX 25 VLD832-VLD855 GNF2-P10DG2BJ71-16GZ-100T2-145-T6-4301 ZR4RX 25 VLD880-VLD887 GNF2-P1 OOG28369-16GZ-1 OOT2-145-T6-4JOJ ZR4RX 25 YLD912-YLD943 GNF2-P1 OOG28370-12GZ-100T2-145-T6-44J7 ZR2RX 26 Yll555-YLL562 GNF2-P10DG2BJ46-1 JGZ-100T2-145-T6-44J5-l TO ZR2RX 26 YLL423-YLL478 GNF2-P10DG2BJ43-14GZ-100T2-145-T6-4436-LTO ZR2RX 26 YLL479-Yll522 GNF2-P100G2BJ46-1JGZ-1 OOT2-145-T6-4435-l TO ZR4RX 26 Yll415-Yll422 GNF2-P10DG2BJ70-12GZ-100T2-145-T6-4437 ZR4RX 26 Yll523-YLL554 Page 19 of 41

J/I (PANAC) 1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21

22.

23 24 25 26 1

2 JYN437 JYN461 JVN470 JYN525 JYX322 JVN453 YLD928 JYN381 VLD936 JYN446 YLD872 JYN451 YLD879 JYN388 VL0943 JYN460 YLD935 JYN528 JVX329 JYN468 JYN475 JYN444 1

C-1302-226-E310-457 Rev. 1 ATTACHMENT 2: Oyster Creek Cycle 26 Fuel Bundle Identification Array 3

4 5

6 7

8 9

10 11 JYN462 JYN509 JYN454 JVN438 JYN469 JYX323 YL0929 JVN534 JYN413 JYN422 JYN398 YLD905 YLD825 YLD809 JYNSOl JYN430 JYN502 YLD921 YLD849 JYX379 YLD880 JYX402 JYN533 JYN429 JYX386 YLD865 YLD897 YLD833 VLD857 Yll432 YllSOO JYN414 JYN529 YLD864 JYX338 YLD801 JYX299 YLL492 JYX307 Yll440 JYN421 VLD920 Yl0896 YLD800 VLL479 YLL484 YLD841 Yll556 JYX291 JYN397 YLD848 YLD832 JYX298 YLL483 JYX419 YLL424 JYX435 Yll532 YLD904 JYX378 YLD856 VLL491 VL0840 VLL423 JYX354 Yll524 JYX411 YLD824 YLD881 YLL431 JYX306 Yll555 JYX434 YLL523 JYX339 Yll448 YL0808 JYX403 YLL499 YLL439 JYX290 VLL531 JYX410 Yll447 JYX387 YLD912 YLD816 Yll507 JYX426 YLL539 JYX394 YLL455 JYX371 Yll463 JYX362 YLD792 Yll415 JYX346 YLD888 YLLSlS JYX314 YLL547 JYX331 JYX369 YLD799 Yll422 JYX353 YLD895 YLL522 JVX321 Yll554 JYX336 VLD919 YLD823 Yll514 JYX433 YLL546 JYX401 YLL462 JYX376 Vll470 YLD815 JYX408 YLL506 Yll446 JYX297 Yll538 JYX417 Yll454 JYX392 YLD831 YLD886 Yll438 JYX313 YLL562 JYX441 YLL530 JYX344 VLL453 YLD911 JYX385 YLD863 YLL498 YLD847 YLL430 JYX361 Yll529 JYX416 JYN404 VLD855 YL0839 JYX305 Yll490 JYX424 YLL429 JYX440 Yll537 JYN428 YLD927 YLD903 YLD807 YLL482 Yll489 YLD846 Yll561 JYX296 JYN419 JYN532 YLD871 JYX345 YLD806 JYX304 YLL497 JYX312 YLL445 JYN540 JYN436 JYX393 YLD870 YLD902 YLD838 YLD862 YLL437 YLLSOS JYN508 JYN435 JYN507 YLD926 YLD854 JYX384 YLD887 JYX409 JYN539 JYN420 JYN427 JVN403 YLD910 YLD830 YLD814 JYN443 JVN476 JYX328 YLD934 JVN467 JVN516 JYN459 5

1 9

11 13 15 17 19 21 Page 20 of41 TOOi NF183597 Rev.a Page 3of18 12 13 JYN382 JYN445 YLD937 YLD873 YLD913 JVX363 YLD817 VLD793 VLL508 Yll416 JYX427 JYX347 Yll540 YLD889 JYX395 YLL516 Yll456 JYX315 JYX370 Yll548 Yll464 JYX330 JYX355 YLL472 Yll471 JYX418 Yll478 JYX425 JYX360 VLL477 YLL469 JVX337 JYX377 Vll553 YLL461 JVX320 JYX400 VLL521 YLL545 YL0894 JYX432 JYX352 YLL513 YLL421 VLD822 YLD798 YLD918 JYX368 YLD942 YLD878 JYN387 JYN452 23 25 52 50 48 46 44 42 40 38 36 34 32 30 28 26 24 22 20 18 16 14 12 10 8

6 4

2 X/Y (SITE)

J/1 (PANAC) 1 1

3 4

5 6

7 8

9 10 11 1l B

14 15 16 17 18 19 20 21 22 13 24 25 26 14 JYN448 YLD874 JYX364 YLD794 YLL417 JYX348 YLD890 YLL517 JYX316 YLL549 JYX333 YLL473 JYX421 JYX422 YLL476 JYX334 YLL552 JYX319 Yll520 YLD893 JYX351 YLL420 YLD797 JYX367 VLD877 JYN449 27 15 JYN383 YLD938 YLD914 YLD818 YLL509 NX428 YLL541 JYX396 YLL457 JVX373 Yll465 JYX356 YLL474 VLL475 JYX359 YLL468 JYX374 YLL460 JYX399 YLL544 JYX431 YLL512 YLD821 YLD917 YL0941 JVN386 29 16 17 18 JYN455 JYN512 JYN463 YLD930 JYX324 JVN472 YLD810 YLD826 YLD906 JYX405 YLD883 JYX380 YLLSOl YLL433 YLD858 Yll441 JYX308 YLL493 JYX292 YLL557 YLD842 YLL533 JYX436 Yll425 JVX412 YLLS25 JYX357 YLL449 JYX340 YLL526 JYX388 YLL450 JVX413 YLL466 JVX372 Yll458 JYX332 YLLSSO JYX317 JYX335 YLLSSl JYX318 YLL467 JYX375 YLL459 JYX391 YLL451 JYX414 YLL452 JYX343 YLL527 JYX415 Yll528 JYX358 Yll536 JYX439 YLL428 JYX295 YLL560 YLD845 YLL444 JYX311 VLL496 YLLS04 YLL436 YLD861 JYX406 YLD884 JVX383 VLD813 YLD829 YLD909 YL0933 JYX327 JYN473 JYN458 JVN513 JYN466 31

B 35 C-1302-226-E310-457 Rev. 1 19 10 21 JYN439 JYN399 JYN423 JYN416 YLD850 YLD922 JYN503 YLD834 YLD898 YLD866 JYX300 YLD802 JYX341 YLL485 Yll480 YLD803 JYX420 YLL486 JYX301 YLL426 YLD843 YLL494 JYX437 YLL558 JYX309 Vll534 JYX293 YLL442 JVX397 YLL542 JYX429 YLL518 YLD891 JYX349 YLL519 YLD892 JYX350 JYX398 YLL543 JYX430 YLL535 JYX294 YLL443 JYX438 YLL559 JYX310 Yll427 YLD844 YLL495 JYX423 YLL487 JYX302 YLL488 YLL481 YLD804 JYX303 YLD805 JVX342 YLD837 YLD901 YLD869 YLD853 YLD925 JVN506 JYN402 JYN426 JYN417 JYN442 37 39 41 Page 21 of 41 ll JYN535 JYN431 JYX389 YLD867 YLD899 YLD835 YLD859 YLL434 VLL502 YLLSlO YLL418 VLL419 Yll511 Yll503 YLL435 YLD860 YLD836 YLD900 VLD868 JYX390 JYN434 JYN538 43 23 24 JYN504 JVN432 JYN536 JYN530 JYN415 YLD923 JYN424 YLD851 JYN400 JYX381 YLD907 YLD882 YLD827 JVX404 YLD811 YLD819 YLD915 YLD795 JYX365 YLD796 JYX366 YLD820 YLD916 JYX407 YLD812 YLD885 YLD828 JYX382 YLD908 YLD852 JYN401 YLD924 JYN425 JVN531 JVN418 JVN433 JYN537 JYNSOS 45 47 TOOi NF183597 Rev.a Page 4 of 18 25 26 JYN440 JYN471 JYN464 JYX325 JVN526 YLD931 JYN456 YLD939 JYN384 YLD875 JYN447 YLD876 JYN450 YLD940 JYN385 YLD932 JVN457 JYX326 JYN527 JYN474 JYN465 JVN441 49 51 52 50 48 46 44 42 40 38 36 34 32 30 28 26 24 11 20 18 16 14 1l 10 8

6 4

2 X/Y (SITE)

C-1302-226-E310-457 Rev. 1 ATTACHMENT 3: Oyster Creek Cycle 26 Fuel IA T Map TOOi NF183597 Rev.a Page 5of18 J/I 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 1

l 3

4 s

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 13 7

6 10 6

7 13 6

13 17 24 24 12 12 24 24 17 13 6

14 6

6 10 21 11 11 24 17 17 24 11 11 21 10 6

6 14 7

6 7

24 22 8

23 15 11 11 11 11 15 23 8

22 24 7

6 7

14 6

8 12 21 22 12 26 27 27 28 18 27 27 26 12 22 21 12 8

6 14 6

14 12 17 11 20 27 20 26 9

17 17 9

26 20 27 20 11 17 12 14 6

6 24 21 11 27 17 22 25 20 19 l1 21 29 10 25 22 17 27 11 21 24 6

6 10 22 22 20 27 15 26 9

29 8

27 27 8

29 9

26 15 17 20 22 22 10 6

13 13 21 8

12 17 22 26 17 29 15 26 20 20 26 15 29 17 26 22 27 12 8

21 13 13 14 17 11 23 26 20 25 9

29 17 26 8

29 29 8

26 17 29 9

25 20 26 23 11 17 14 6

24 11 15 27 26 20 29 15 26 8

26 17 17 26 8

26 15 29 20 26 27 15 11 24 6

10 24 24 11 27 9

29 8

26 8

26 17 26 26 17 26 8

26 8

29 9

27 11 24 24 10 6

12 17 11 28 17 21 27 20 29 17 26 15 15 26 17 29 20 27 21 17 28 11 17 12 6

6 12 17 11 28 17 21 27 20 29 17 26 15 15 26 17 29 20 27 21 17 28 11 17 12 6

10 24 24 11 27 9

29 8

26 8

26 17 26 26 17 26 8

26 8

29 9

27 11 24 24 10 6

24 11 15 27 26 20 29 15 26 8

26 17 17 26 8

26 15 19 20 26 27 15 11 24 6

14 17 11 23 26 20 25 9

29 17 26 8

29 29 8

26 17 29 9

25 20 26 23 11 17 14 n

13 21 8

12 27 22 26 17 29 15 26 10 10 26 15 29 17 26 22 27 12 8

21 13 13 6

10 22 22 20 27 15 26 9

29 8

27 27 8

29 9

26 15 27 20 22 22 10 6

6 24 21 11 27 27 22 25 20 19 21 21 29 20 25 22 27 27 11 21 24 6

6 14 12 17 11 20 27 20 26 9

17 17 9

26 20 27 20 11 17 11 14 6

14 6

8 12 21 22 12 26 27 27 28 28 27 27 26 12 22 21 12 8

6 14 7

6 7

24 22 8

23 15 11 11 11 11 15 23 8

22 24 7

6 7

14 6

6 10 21 11 11 24 17 17 24 11 11 21 10 6

6 14 6

13 17 24 24 12 12 24 24 17 13 6

13 7

6 10 6

7 13 1

3 s

7 9

11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 Page 22 of41 52 50 48 46 44 42 40 38 36 34 32 30 28 26 24 22 20 18 16 14 12 10 8

6 4

2 C-1302-226-E310-457 Rev. 1 ATTACHMENT 4: Oy t C

k C I 26 F I B di E s er ree

.ye e ue un e xposure, u ramu EOC Bundle Bundle Bundle Initial Initial Serial Type Exp Weight Enrich ID (IAT)

(GWd/MT)

(MT)

(fraction)

JYN461 13 46.7913 0.180885 0.037016 JYN525 14 47.0963 0.180771 0.036880 JYN453 6

47.0508 0.180840 0.037038 JYN381 10 47.5784 0.180944 0.037066 JYN446 6

48.3574 0.180928 0.037036 JYN451 6

48.4346 0.180956 0.036993 JYN388 10 47.6153 0.180856 0.037038 JYN460 6

47.0528 0.180856 0.037001 JYN528 14 47.2909 0.180918 0.036880 JYN468 13 46.8265 0.180816 0.036971 JYN437 6

47.1013 0.180940 0.037017 JYN470 13 45.9430 0.180771 0.036983 JYX322 17 35.2095 0.181064 0.037105 YLD928 24 27.9412 0.180415 0.036866 YLD936 24 27.4603 0.180413 0.036864 YLD872 12 28.1927 0.180246 0.037090 YLD879 12 28.1668 0.180377 0.037078 YLD943 24 27.4484 0.180419 0.036864 YLD935 24 27.9199 0.180438 0.036856 JYX329 17 35.2612 0.181013 0.037096 JYN475 13 46.0372 0.180897 0.036996 JYN444 6

47.1046 0.180924 0.037018 JYN533 14 47.6656 0.181162 0.036891 JYN414 6

45.8782 0.180841 0.037004 JYN421 6

48.7544 0.180808 0.036971 JYN397 10 44.9803 0.180819 0.037039 YLD904 21 28.2190 0.180318 0.036853 YLD824 11 28.7219 0.180544 0.037086 YLD808 11 31.0810 0.180407 0.037103 YLD912 24 31.6330 0.180307 0.036856 JYX362 17 43.1786 0.180983 0.037061 JYX369 17 43.2291 0.180955 0.037072 YLD919 24 31.6384 0.180394 0.036872 YLD815 11 31.0659 0.180434 0.037088 YLD831 11 28.6980 0.180544 0.037080 YLD911 21 28.1943 0.180311 0.036851 JYN404 10 44.9880 0.180895 0.037045 JYN428 6

48.7623 0.180855 0.037046 JYN419 6

45.9307 0.180967 0.037029 Page 23 of 41 TODI NF183597 Rev.O Page 6of18 m Mass, & Enrichment

JYN540 JYN501 JYN429 JYN529 YLD920 YLD848 JYX378 YLD881 JYX403 YLD816 YLD792 YLD799 YLD823 JYX408 YLD886 JYX385 YLD855 YLD927 JYN532 JYN436 JYN508 JYN534 JYN430 JYX386 YLD864 YLD896 YLD832 YLD856 YLL431 YLL499 YLL507 YLL415 YLL422 YLL514 YLLS06 YLL438 YLD863 YLD839 YLD903 YLD871 JYX393 JYN435 JYN539 JYN413 C-1302-226-E310-457 Rev. 1 14 47.7202 0.181000 7

47.3498 0.180795 6

44.6650 0.180914 14 42.2695 0.180882 24 27.4228 0.180421 22 29.2999 0.180549 8

44.8288 0.180675 23 31.2113 0.180360 15 46.9403 0.180663 11 32.7881 0.180477 11 32.6462 0.180476 11 32.6869 0.180409 11 32.7571 0.180571 15 46.9685 0.180746 23 31.2930 0.180373 8

44.8688 0.180675 22 29.2650 0.180620 24 27.4035 0.180413 14 42.2820 0.181096 6

44.6691 0.180912 7

47.3109 0.180898 14 47.6497 0.181186 6

44.4073 0.180948 8

40.1257 0.180689 12 28.3874 0.180331 21 30.6601 0.180305 22 31.8674 0.180541 12 31.5925 0.180333 26 16.8696 0.180710 27 17.8470 0.180610 27 17.9508 0.180526 28 17.0129 0.180802 28 17.0061 0.180803 27 17.9331 0.180491 27 17.8062 0.180729 26 16.8367 0.180738 12 31.6397 0.180358 22 31.8582 0.180528 21 30.6213 0.180325 12 28.3465 0.180335 8

40.1549 0.180567 6

44.6145 0.180910 14 47.7421 0.180974 6

45.9948 0.180756 Page 24 of 41 0.036878 0.036899 0.036991 0.036876 0.036866 0.037109 0.036927 0.037077 0.037160 0.037103 0.037100 0.037105 0.037092 0.037182 0.037080 0.036957 0.037115 0.036868 0.036895 0.037004 0.036878 0.036883 0.037021 0.036950 0.037081 0.036862 0.037099 0.037083 0.034588 0.034378 0.034361 0.034558 0.034594 0.034370 0.034359 0.034586 0.037075 0.037116 0.036856 0.037092 0.036945 0.037006 0.036871 0.037000 TOOi NF183597 Rev.a Page 7 of 18

JYN502 YLD865 JYX338 YLD800 JYX298 YLL491 JYX306 YLL439 JYX426 JYX346 JYX353 JYX433 YLL446 JYX313 YLL498 JYX305 YLD807 JYX345 YLD870 JYN507 JYN420 JYN422 YLD921 YLD897 YLD801 YLL479 YLL483 YLD840 YLL555 JYX290 YLL539 YLD888 YLD895 YLL546 JYX297 YLL562 YLD847 YLL490 YLL482 YLD806 YLD902 YLD926 JYN427 JYN438 C-1302-226-E310-457 Rev. 1 7

44.9950 0.180802 12 28.3737 0.180349 17 41.8157 0.181108 11 32.7274 0.180516 20 45.6360 0.181269 27 17.0019 0.180551 20 44.1676 0.181211 26 18.5264 0.180697 9

44.7833 0.180649 17 44.4934 0.181069 17 44.5266 0.180972 9

44.7559 0.180754 26 18.4791 0.180800 20 44.1772 0.181120 27 16.9705 0.180516 20 45.6561 0.181209 11 32.7196 0.180492 17 41.8993 0.180865 12 28.3263 0.180307 7

45.0657 0.180806 6

45.9565 0.180962 6

48.6226 0.180838 24 27.4097 0.180460 21 30.6819 0.180310 11 32.7223 0.180507 27 17.0117 0.180544 27 17.7602 0.180552 22 34.4626 0.180564 25 18.8889 0.180792 20 43.2128 0.181331 29 18.1641 0.180677 21 34.7157 0.180372 21 34.7338 0.180292 29 18.0942 0.180766 20 43.2096 0.181285 25 18.8547 0.180759 22 34.4445 0.180537 27 17.7204 0.180425 27 16.9472 0.180531 11 32.7282 0.180412 21 30.6202 0.180246 24 27.3851 0.180371 6

48.7491 0.180854 6

46.7672 0.180935 Page 25 of 41 0.036895 0.037085 0.037098 0.037084 0.037053 0.034387 0.037062 0.034572 0.037184 0.037058 0.037066 0.037186 0.034561 0.037089 0.034372 0.037069 0.037087 0.037066 0.037088 0.036880 0.037014 0.036993 0.036868 0.036861 0.037085 0.034372 0.034368 0.037114 0.036976 0.037106 0.036984 0.036860 0.036853 0.036963 0.037071 0.036995 0.037117 0.034404 0.034374 0.037103 0.036860 0.036867 0.037044 0.037015 TOOi NF183597 Rev.O Page 8of18

JYN398 YLD849 YLD833 JYX299 YLL484 JYX419 YLL423 JYX434 YLLS31 JYX394 YLLS15 YLL522 JYX401 YLL538 JYX441 YLL430 JYX424 YLL489 JYX304 YLD838 YLD854 JYN403 JYN443 JYN462 JYN469 YLD905 JYX379 YLD857 YLL492 YLD841 YLL424 JYX354 YLLS23 JYX410 YLL455 JYX314 JYX321 YLL462 JYX417 YLL530 JYX361 YLL429 YLD846 YLL497 C-1302-226-E310-457 Rev. 1 10 44.8150 0.180889 22 29.3201 0.180606 22 31.6552 0.180518 20 45.6437 0.181246 27 17.7907 0.180577 15 48.2107 0.180746 26 18.6980 0.180753 9

43.2434 0.180742 29 18.1953 0.180699 8

42.7113 0.180557 27 18.4323 0.180536 27 18.4274 0.180438 8

42.7385 0.180634 29 18.1391 0.180677 9

43.2669 0.180616 26 18.6839 0.180659 15 48.2397 0.180634 27 17.7201 0.180444 20 45.6197 0.181183 22 31.8546 0.180477 22 29.2622 0.180618 10 44.9218 0.180869 6

47.1285 0.180906 13 46.8231 0.180805 13 45.7639 0.180774 21 28.2960 0.180282 8

44.7244 0.180721 12 31.5714 0.180313 27 17.0837 0.180564 22 34.3358 0.180563 26 18.7500 0.180762 17 42.4193 0.180987 29 17.1289 0.180726 15 45.3287 0.180792 26 18.4172 0.180728 20 46.8374 0.180960 20 46.8404 0.180927 26 18.3917 0.180710 15 45.3668 0.180656 29 17.2251 0.180674 17 42.4970 0.180940 26 18.6871 0.180687 22 34.4469 0.180528 27 16.9617 0.180648 Page 26 of 41 0.037028 0.037108 0.037099 0.037045 0.034372 0.037178 0.034604 0.037213 0.036989 0.036936 0.034359 0.034361 0.036955 0.036960 0.037193 0.034566 0.037186 0.034403 0.037072 0.037107 0.037121 0.037058 0.036992 0.037003 0.036986 0.036846 0.036964 0.037083 0.034390 0.037118 0.034604 0.037075 0.036985 0.037177 0.034558 0.037070 0.037078 0.034554 0.037160 0.036995 0.037069 0.034572 0.037123 0.034371 TODI NF183597 Rev.a Page 9of18

YLD862 JYX384 YLD910 JYN476 JYN467 JYN509 JYX323 YLD825 YLD880 YLL432 JYX307 YLL556 JYX435 YLLS24 JYX339 YLL447 JYX371 YLL547 YLL554 JYX376 YLL454 JYX344 YLL529 JYX440 YLL561 JYX312 YLL437 YLD887 YLD830 JYX328 JYN516 JYN454 YLD929 YLD809 JYX402 YLLSOO YLL440 JYX291 YLL532 JYX411 YLL448 JYX387 YLL463 JYX331 C-1302-226-E310-457 Rev. 1 12 31.6431 0.180319 8

44.8613 0.180668 21 28.1812 0.180339 13 46.0016 0.180996 13 46.8525 0.180784 7

45.8381 0.180834 17 34.5627 0.181008 11 28.7401 0.180503 23 31.3415 0.180345 26 16.9735 0.180626 20 44.0520 0.181211 25 19.0264 0.180757 9

42.8704 0.180732 29 17.1724 0.180727 17 44.0875 0.180968 26 18.4052 0.180799 8

48.0557 0.180648 29 17.7631 0.180717 29 17.7460 0.180784 8

48.1056 0.180609 26 18.3937 0.180723 17 44.5069 0.180964 29 17.2271 0.180733 9

43.2925 0.180499 25 18.8723 0.180753 20 44.1475 0.181152 26 16.8377 0.180739 23 31.2919 0.180362 11 28.6645 0.180542 17 35.2568 0.181036 7

45.8050 0.180858 6

47.0448 0.180882 24 28.0211 0.180444 11 31.0860 0.180415 15 47.0036 0.180705 27 17.9618 0.180560 26 18.6669 0.180683 20 42.4912 0.181339 29 18.3131 0.180738 15 45.3085 0.180718 26 18.4315 0.180792 8

46.4990 0.180674 26 18.7416 0.180821 17 47.1711 0.181025 Page 27 of 41 0.037071 0.036974 0.036845 0.036985 0.036988 0.036886 0.037085 0.037088 0.037076 0.034585 0.037057 0.036966 0.037200 0.036984 0.037070 0.034578 0.036922 0.036968 0.036964 0.036942 0.034578 0.037083 0.036992 0.037174 0.036973 0.037066 0.034582 0.037081 0.037104 0.037069 0.036857 0.036991 0.036863 0.037107 0.037185 0.034370 0.034574 0.037101 0.036981 0.037179 0.034587 0.036947 0.034582 0.037069 TOOi NF183597 Rev.a Page 10 of 18

JYX336 YLL470 JYX392 YLL453 JYX416 YLL537 JYX296 YLL445 YLL505 JYX409 YLD814 YLD934 JYN459 JYN382 YLD937 YLD913 YLD817 YLL508 JYX427 YLLS40 JYX395 YLL456 JYX370 YLL464 JYX355 YLL471 YLL478 JYX360 YLL469 JYX377 YLL461 JYX400 YLL545 JYX432 YLLS13 YLD822 YLD918 YLD942 JYN387 JYN445 YLD873 JYX363 YLD793 YLL416 C-1302-226-E310-457 Rev. 1 17 47.2424 0.180949 26 18.7059 0.180779 8

46.6144 0.180578 26 18.4077 0.180657 15 45.3017 0.180679 29 18.1883 0.180713 20 43.2442 0.181311 26 18.5003 0.180737 27 17.8178 0.180638 15 46.9826 0.180703 11 31.0527 0.180490 24 27.9165 0.180399 6

47.0484 0.180923 10 46.9554 0.180962 24 27.5554 0.180422 24 31.5841 0.180291 11 32.8022 0.180478 27 18.0691 0.180422 9

44.7431 0.180643 29 18.2964 0.180649 8

42.6552 0.180591 26 18.4910 0.180643 8

48.0884 0.180629 26 18.7501 0.180867 17 43.3861 0.181006 26 18.7088 0.180769 26 18.6844 0.180825 17 43.7634 0.180909 26 18.7096 0.180749 8

48.0993 0.180655 26 18.4082 0.180708 8

42.7886 0.180687 29 18.1485 0.180701 9

44.7015 0.180798 27 17.9274 0.180527 11 32.7394 0.180595 24 31.6334 0.180379 24 27.4512 0.180423 10 47.5847 0.180846 6

48.3269 0.180967 12 28.2644 0.180264 17 42.7492 0.181054 11 32.4134 0.180525 28 17.1023 0.180812 Page 28 of41 0.037064 0.034580 0.036949 0.034578 0.037195 0.036968 0.037095 0.034573 0.034357 0.037185 0.037082 0.036848 0.036991 0.037068 0.036869 0.036860 0.037084 0.034351 0.037156 0.036988 0.036923 0.034560 0.036913 0.034577 0.037067 0.034560 0.034607 0.037068 0.034575 0.036959 0.034558 0.036956 0.036973 0.037184 0.034363 0.037097 0.036859 0.036860 0.037057 0.037031 0.037090 0.037051 0.037097 0.034562 TODI NF183597 Rev.O Page 11 of 18

JYX347 YLD889 YLL516 JYX315 YLL548 JYX330 YLL472 JYX418 JYX425 YLL477 JYX337 YLL553 JYX320 YLL521 YLD894 JYX352 YLL421 YLD798 JYX368 YLD878 JYN452 JYN448 YLD874 JYX364 YLD794 YLL417 JYX348 YLD890 YLL517 JYX316 YLL549 JYX333 YLL473 JYX421 JYX422 YLL476 JYX334 YLL552 JYX319 YLL520 YLD893 JYX351 YLL420 YLD797 C-1302-226-E310-457 Rev. 1 17 44.3304 0.181120 21 34.7511 0.180342 27 18.5141 0.180549 20 46.8702 0.180989 29 17.7942 0.180808 17 47.2091 0.180996 26 18.7158 0.180790 15 48.0746 0.180694 15 48.0784 0.180665 26 18.6809 0.180790 17 47.2216 0.181034 29 17.7512 0.180746 20 46.8314 0.180990 27 18.4269 0.180489 21 34.7344 0.180304 17 44.5040 0.180959 28 16.9910 0.180755 11 32.6632 0.180446 17 43.1878 0.181014 12 28.1661 0.180345 6

48.3690 0.180966 6

48.3978 0.180843 12 28.2375 0.180317 17 43.2605 0.181011 11 32.7562 0.180468 28 17.0808 0.180749 17 44.5129 0.181164 21 34.8123 0.180336 27 18.4960 0.180505 20 46.8684 0.180989 29 17.7924 0.180742 17 47.2210 0.181061 26 18.7018 0.180810 15 48.0658 0.180603 15 48.0469 0.180635 26 18.6873 0.180755 17 47.0472 0.181031 29 17.7518 0.180725 20 46.8249 0.180969 27 18.4231 0.180463 21 34.6975 0.180340 17 44.4371 0.180959 28 16.9791 0.180733 11 32.6599 0.180435 Page 29 of 41 0.037031 0.036858 0.034369 0.037079 0.036948 0.037083 0.034576 0.037180 0.037191 0.034597 0.037070 0.036965 0.037084 0.034362 0.036848 0.037074 0.034594 0.037104 0.037076 0.037066 0.036985 0.037034 0.037078 0.037059 0.037109 0.034561 0.037020 0.036860 0.034357 0.037067 0.036960 0.037049 0.034581 0.037143 0.037179 0.034599 0.037054 0.036963 0.037072 0.034349 0.036848 0.037084 0.034574 0.037107 TODI NF183597 Rev.a Page 12 of 18

JYX367 YLD877 JYN449 JYN383 YL0938 YLD914 YLD818 YLL509 JYX428 YLLS41 JYX396 YLL457 JYX373 YLL465 JYX356 YLL474 YLL475 JYX359 YLL468 JYX374 YLL460 JYX399 YLLS44 JYX431 YLLS12 YLD821 YLD917 YLD941 JYN386 JYN455 YLD930 YLD810 JYX405 YLLSOl YLL441 JYX292 YLLS33 JYX412 YLL449 JYX388 YLL466 JYX332 JYX335 YLL467 C-1302-226-E310-457 Rev. 1 17 43.1568 0.181045 12 28.1457 0.180312 6

48.3112 0.180957 10 47.5977 0.180914 24 27.5089 0.180329 24 31.6962 0.180338 11 32.8089 0.180482 27 18.0018 0.180406 9

44.7523 0.180712 29 18.2076 0.180639 8

42.8235 0.180594 26 18.4536 0.180680 8

48.1220 0.180583 26 18.7294 0.180829 17 43.7423 0.181017 26 18.6939 0.180777 26 18.6875 0.180800 17 43.7380 0.180934 26 18.6991 0.180806 8

48.0115 0.180621 26 18.3819 0.180741 8

42.7855 0.180630 29 18.1251 0.180696 9

44.6190 0.180738 27 17.8707 0.180410 11 32.6995 0.180610 24 31.6061 0.180427 24 27.4427 0.180426 10 47.5723 0.180909 6

47.0339 0.180919 24 27.9346 0.180489 11 31.0987 0.180436 15 46.9953 0.180721 27 17.8793 0.180466 26 18.5476 0.180714 20 43.2692 0.181318 29 18.2307 0.180659 15 45.3158 0.180765 26 18.4280 0.180772 8

46.6409 0.180589 26 18.7212 0.180838 17 47.2195 0.181029 17 47.0755 0.180952 26 18.7044 0.180788 Page 30 of41 0.037069 0.037075 0.037037 0.037077 0.036871 0.036861 0.037089 0.034336 0.037201 0.037003 0.036896 0.034567 0.036919 0.034587 0.037071 0.034586 0.034594 0.037052 0.034569 0.036930 0.034559 0.036907 0.036967 0.037192 0.034356 0.037108 0.036878 0.036848 0.037058 0.036984 0.036863 0.037102 0.037163 0.034363 0.034580 0.037115 0.036998 0.037183 0.034579 0.036940 0.034580 0.037055 0.037060 0.034572 TOOi NF183597 Rev.a Page 13of18

JYX391 YLL452 JYX415 YLL536 JYX295 YLL444 YLLS04 JYX406 YLD813 YLD933 JYN458 JYN512 JYX324 YLD826 YLD883 YLL433 JYX308 YLL557 JYX436 YLL525 JYX340 YLL450 JYX372 YLLS50 YLLS51 JYX375 YLL451 JYX343 YLLS28 JYX439 YLLS60 JYX311 YLL436 YLD884 YLD829 JYX327 JYN513 JYN463 JYN472 YLD906 JYX380 YLD858 YLL493 YLD842 C-1302-226-E310-457 Rev. 1 8

46.5964 0.180592 26 18.3581 0.180660 15 45.2568 0.180713 29 18.1471 0.180720 20 43.2028 0.181321 26 18.4263 0.180718 27 17.7479 0.180588 15 46.8755 0.180684 11 31.0278 0.180493 24 27.8927 0.180406 6

47.0372 0.180886 7

45.7916 0.180877 17 35.2609 0.181041 11 28.6710 0.180531 23 31.3223 0.180373 26 16.8806 0.180627 20 44.1635 0.181117 25 18.9065 0.180757 9

43.3048 0.180640 29 17.2571 0.180737 17 44.5228 0.180962 26 18.4234 0.180752 8

48.1106 0.180625 29 17.7642 0.180748 29 17.7581 0.180747 8

48.0181 0.180657 26 18.3540 0.180732 17 44.3587 0.181029 29 17.0527 0.180758 9

43.2361 0.180529 25 18.8327 0.180763 20 44.0779 0.181150 26 16.8077 0.180734 23 31.2685 0.180417 11 28.6426 0.180575 17 35.2392 0.181012 7

45.7883 0.180879 13 46.8103 0.180816 13 45.9928 0.181008 21 28.2038 0.180346 8

44.8599 0.180709 12 31.6743 0.180343 27 16.9937 0.180595 22 34.4793 0.180567 Page 31 of41 0.036922 0.034589 0.037184 0.036970 0.037104 0.034560 0.034356 0.037191 0.037094 0.036851 0.037003 0.036862 0.037065 0.037085 0.037083 0.034592 0.037075 0.036958 0.037212 0.036989 0.037067 0.034581 0.036917 0.036970 0.036962 0.036935 0.034600 0.037070 0.036986 0.037175 0.036964 0.037063 0.034591 0.037076 0.037090 0.037071 0.036867 0.037006 0.036994 0.036840 0.036939 0.037085 0.034385 0.037113 TODI NF183597 Rev.a Page 14 of 18

YLL425 JYX357 YLL526 JYX413 YLL458 JYX317 JYX318 YLL459 JYX414 YLL527 JYX358 YLL428 YLD845 YLL496 YLD861 JYX383 YLD909 JYN473 JYN466 JYN439 JYN399 YLD850 YLD834 JYX300 YLL485 JYX420 YLL426 JYX437 YLL534 JYX397 YLL518 YLL519 JYX398 YLL535 JYX438 YLL427 JYX423 YLL488 JYX303 YLD837 YLD853 JYN402 JYN442 JYN423 C-1302-226-E310-457 Rev. 1 26 18.7117 0.180753 17 42.4961 0.180966 29 17.2488 0.180785 15 45.3457 0.180808 26 18.4295 0.180717 20 46.8162 0.180992 20 46.8097 0.180985 26 18.3910 0.180769 15 45.3003 0.180693 29 17.0653 0.180669 17 42.3661 0.180895 26 18.6294 0.180682 22 34.4104 0.180518 27 16.9414 0.180641 12 31.6380 0.180315 8

44.8345 0.180717 21 28.1736 0.180342 13 45.9266 0.181026 13 46.7703 0.180825 6

47.0967 0.180960 10 44.9100 0.180857 22 29.2860 0.180587 22 31.8787 0.180523 20 45.6347 0.181261 27 17.7360 0.180559 15 48.2466 0.180704 26 18.7104 0.180755 9

43.2896 0.180639 29 18.2155 0.180700 8

42.7712 0.180673 27 18.4564 0.180441 27 18.4400 0.180521 8

42.7589 0.180643 29 18.1630 0.180689 9

43.2414 0.180577 26 18.6321 0.180701 15 48.1949 0.180695 27 17.7090 0.180394 20 45.5877 0.181226 22 31.8420 0.180497 22 29.2584 0.180556 10 44.9178 0.180862 6

47.0997 0.180881 6

48.7261 0.180866 Page 32 of 41 0.034596 0.037068 0.036974 0.037170 0.034573 0.037070 0.037091 0.034568 0.037183 0.036993 0.037060 0.034570 0.037122 0.034380 0.037074 0.036972 0.036852 0.036991 0.036975 0.037018 0.037010 0.037108 0.037107 0.037057 0.034376 0.037185 0.034599 0.037202 0.036982 0.036915 0.034353 0.034352 0.036921 0.036972 0.037184 0.034568 0.037164 0.034408 0.037057 0.037106 0.037141 0.037042 0.036994 0.037011 TODI NF183597 Rev.a Page 15of18

YLD922 YL0898 YL0802 YLL480 YLL486 YL0843 YLL558 JYX293 YLL542 YLD891 YLD892 YLL543 JYX294 YLL559 YLD844 YLL487 YLL481 YLD805 YLD901 YLD925 JYN426 JYN416 JYN503 YLD866 JYX341 YL0803 JYX301 YLL494 JYX309 YLL442 JYX429 JYX349 JYX350 JYX430 YLL443 JYX310 YLL495 JYX302 YLD804 JYX342 YLD869 JYN506 JYN417 JYN535 C-1302-226-E310-457 Rev. 1 24 27.4071 0.180369 21 30.6300 0.180332 11 32.7473 0.180475 27 16.9752 0.180507 27 17.7359 0.180582 22 34.4743 0.180556 25 18.9016 0.180755 20 43.2147 0.181368 29 18.1733 0.180714 21 34.7475 0.180372 21 34.7241 0.180326 29 18.1533 0.180693 20 43.2177 0.181326 25 18.8529 0.180735 22 34.4300 0.180538 27 17.7127 0.180421 27 16.9480 0.180509 11 32.6698 0.180456 21 30.6160 0.180272 24 27.3493 0.180410 6

48.7193 0.180869 6

45.9160 0.180940 7

45.0245 0.180789 12 28.3478 0.180322 17 41.8646 0.181001 11 32.7547 0.180450 20 45.6097 0.181253 27 16.9922 0.180614 20 44.1749 0.181156 26 18.5303 0.180724 9

44.7575 0.180783 17 44.4822 0.181147 17 44.5041 0.181009 9

44.7614 0.180712 26 18.5050 0.180713 20 44.1491 0.181169 27 16.9514 0.180650 20 45.5589 0.181238 11 32.6742 0.180482 17 41.8461 0.181063 12 28.2802 0.180322 7

45.0556 0.180823 6

45.9172 0.180947 14 47.6703 0.181174 Page 33 of 41 0.036875 0.036860 0.037084 0.034375 0.034382 0.037109 0.036966 0.037108 0.036992 0.036850 0.036849 0.036984 0.037108 0.036978 0.037110 0.034398 0.034369 0.037097 0.036848 0.036864 0.037023 0.036989 0.036892 0.037082 0.037059 0.037089 0.037065 0.034378 0.037071 0.034580 0.037199 0.037037 0.037043 0.037188 0.034579 0.037075 0.034379 0.037040 0.037089 0.037080 0.037089 0.036877 0.036982 0.036881 TOOi NF183597 Rev.a Page 16 of 18

JYN431 JYX389 YLD867 YLD899 YLD835 YLD859 YLL434 YLL502 YLL510 YLL418 YLL419 YLL511 YLLS03 YLL435 YLD860 YLD836 YLD900 YLD868 JYX390 JYN434 JYN538 JYN504 JYN432 JYN530 YLD923 YLD851 JYX381 YLD882 JYX404 YLD819 YLD795 YLD796 YLD820 JYX407 YLD885 JYX382 YLD852 YLD924 JYN531 JYN433 JYN505 JYN536 JYN415 JYN424 C-1302-226-E310-457 Rev. 1 6

44.5828 0.180945 8

40.1566 0.180608 12 28.3649 0.180351 21 30.6292 0.180307 22 31.8857 0.180497 12 31.6737 0.180329 26 16.8676 0.180702 27 17.8634 0.180458 27 17.9597 0.180495 28 17.0242 0.180762 28 17.0262 0.180703 27 17.9546 0.180438 27 17.8463 0.180460 26 16.8405 0.180712 12 31.6518 0.180340 22 31.8715 0.180499 21 30.6251 0.180262 12 28.3021 0.180349 8

39.9972 0.180603 6

44.5889 0.180987 14 47.7226 0.180958 7

47.3102 0.180779 6

44.6346 0.180945 14 42.2638 0.180996 24 27.4076 0.180420 22 29.2723 0.180559 8

44.8622 0.180691 23 31.3245 0.180365 15 46.9712 0.180730 11 32.7664 0.180514 11 32.6858 0.180485 11 32.6929 0.180470 11 32.7636 0.180488 15 46.9106 0.180726 23 31.3014 0.180370 8

44.8372 0.180726 22 29.2669 0.180540 24 27.3770 0.180412 14 42.2964 0.181041 6

44.6610 0.180908 7

47.2923 0.180866 14 47.6667 0.181143 6

45.8819 0.180959 6

48.7400 0.180833 Page 34 of 41 0.037012 0.036949 0.037084 0.036852 0.037111 0.037080 0.034601 0.034369 0.034359 0.034563 0.034568 0.034353 0.034349 0.034594 0.037085 0.037096 0.036852 0.037082 0.036909 0.036996 0.036875 0.036899 0.037014 0.036877 0.036869 0.037121 0.036968 0.037075 0.037173 0.037088 0.037105 0.037108 0.037097 0.037188 0.037078 0.036972 0.037136 0.036874 0.036893 0.037005 0.036894 0.036882 0.036975 0.037010 TODI NF183597 Rev.O Page 17of18

JYN400 YLD907 YLD827 YLD811 YLD915 JYX365 JYX366 YLD916 YLD812 YLD828 YLD908 JYN401 JYN425 JYN418 JYN537 JYN440 JYN471 JYX325 YLD931 YLD939 YLD875 YLD876 YLD940 YLD932 JYX326 JYN474 JYN441 JYN464 JYN526 JYN456 JYN384 JYN447 JYN450 JYN385 JYN457 JYN527 JYN465 C-1302-226-E310-457 Rev. 1 10 44.9677 0.180851 21 28.2041 0.180342 11 28.6941 0.180541 11 31.0758 0.180423 24 31.6537 0.180397 17 43.1952 0.181066 17 43.1893 0.181021 24 31.6504 0.180346 11 31.0636 0.180428 11 28.6772 0.180623 21 28.1917 0.180347 10 44.9956 0.180849 6

48.7368 0.180848 6

45.9167 0.180939 14 47.6608 0.181130 6

47.0781 0.180946 13 46.0108 0.180827 17 35.2221 0.181070 24 27.9411 0.180382 24 27.4667 0.180338 12 28.1804 0.180317 12 28.1532 0.180328 24 27.4606 0.180331 24 27.9084 0.180444 17 35.2539 0.181016 13 45.9665 0.181023 6

47.0884 0.180976 13 46.7866 0.180853 14 47.2833 0.180833 6

46.9741 0.180960 10 47.5578 0.180923 6

48.3915 0.180952 6

48.4297 0.180908 10 47.5995 0.180850 6

46.9889 0.180900 14 47.1677 0.180921 13 46.7419 0.180897 Page 35 of 41 0.037031 0.036837 0.037080 0.037099 0.036867 0.037053 0.037073 0.036874 0.037095 0.037076 0.036839 0.037018 0.037003 0.036985 0.036881 0.037011 0.036995 0.037052 0.036866 0.036862 0.037076 0.037068 0.036848 0.036863 0.037083 0.036987 0.036991 0.036991 0.036874 0.037002 0.037067 0.037039 0.037020 0.037069 0.037000 0.036880 0.036987 TOOi NF183597 Rev.a Page 18of18

Atlachment4 C-1302-226-E310-457 Rev. 1 SPECIA1 MEfA1S www.specialmetals.com JNCONEL alloy X-750 (UNS N07750/W. Nr. 2.4669) is a precipitation-hardenable nickel-chromium alloy used for its corrosion and oxidation resistance and high strength at temperatures to I 300°F. Although much of the effect of precipitation hardening is lost with increasing temperature over J 300°F, heat-treated material has useful strength up to J 800°F. Alloy X-750 also has excellent properties down to cryogenic termperatures. Composition is shown in Table I.

The economics of INCONEL alloy X-750 coupled with its availability in all standard mill forms has resulted in applications in a wide variety of industrial fields. Jn gas turbines, it is used for rotor blades and wheels, bolts, and other structural members. INCONEL alloy X-750 is used extensively in rocket-engine thrust chambers. Airframe applications include thrust reversers and hot-air ducting systems. Large pressure vessels are formed from INCONEL alloy X-750. Other applications are heat-treating fixtures, forming tools, extrusion dies, and test machine grips. For springs and fasteners, INCONEL alloy X-750 is used from sub-zero to 1200°F.

Depending on the application and the properties desired, various heat treatments are employed. For service above 1100°F, particularly where loads are to be sustained for long times, optimum properties are achieved by solution treating (2100°F) plus stabilization treating ( J 550°F) plus precipitation treating ( 1300°F}.

For service below 1100°F, the alloy may be strengthened by precipitation treating after hot or cold working or by precipitation treating after equalizing or solution treating. A furnace-cooling treatment is also used to develop optimum properties for some applications.

The various heat treatments and the properties developed are described under the section on Mechanical Properties.

Property values in this bulletin - the results of extensive testing - are typical of the alloy but, unless shown as limiting, should not be used as specification values.

INCONEL, MONEL and Nl-SPAN-C are trademarks of the Special Metals Corporation group of companies.

Table 1 - Limiting Chemical Composition, %

Nickel (plus Cobalt).................................................... 70.00 min.

Chromium................................................................... 14.0-17.0 lron.................................................................................. 5.0-9.0 Titanium....................................................................... 2.25-2. 75 Aluminum.................................................................... 0.40-1.00 Niobium (plus Tantalum).............................................. O. 70-1.20 Manganese................................................................. 1.00 max.

Silicon......................................................................... 0.50 max.

Sulfur........................................................................... 0.01 max.

Copper........................................................................ 0.50 max.

Carbon........................................................................ 0.08 max.

Cobalt1......................................................................... 1.00 max

'Determination not required for routine acceptance.

Physical Constants and Thennal Properties Some physical constants and thermal properties of INCONEL alloy X-750 are given in Tables 2 and 3.

Values for thermal expansion, thermal conductivity, specific heat, and diffusivity are from Lucks and Deem and electrical resistivity from tests conducted at Lehigh University.

Effects of temperature on modulus of elasticity and additional data on resistivity are in Tables 4 and 5. More modulus values can be found in the section on Mechanical Properties.

Table 2 - Physical Constants Density, lb/in3..................................................................... 0.299 g/cm3...................................................................... 8.28 Melting Range, °F...................................................... 2540-2600

c.................................................... 1393-1427 Curie Temperature, °F As hot-rolled.............................................. -225 Triple-heat-treated (2100°F/2 hr, A.C.,+ 1500°F

/24 hr, A.C., + 1300°F/20 hr, A.C.)............. -193 Magnetic Permeability, 70°F, 200H As Hot-Rolled......................................... 1.0020 Triple-heat-treated (2100°F/2 hr, A.C.,+ 1500°F

/24 hr, A.C., + 1300°F/20 hr, A.C.)......... 1.0035 Emissivity, oxidized surface 600°F........................................................ o.095 2000°F...................................................... 0.925 Linear Contraction during Precipitation Treatment (1300°F/20 hr), in/in Hot-Rolled............................................ 0.00044 20% Cold-Rolled................................. 0.00052 Annealed.............................................. 0.00026 Page 36 of41

INCONEL

alloy X-750 Mean Linear Temperature, Expansion, ln./ln.rF x "F

1 o-e from 70" F to Temperature Shown

-250 6.5

-200 6.6

-100 6.7 70 200 7.0 400 7.2 600 7.5 BOO 7.8 1000 8.1 1200 8.4 1400 8.8 1600 9.3 1800 9.8 C-1302-226-E310-457 Rev. 1 Table 3 - Thermal Properties*

Thermal Conductivity, Specific Heat Btu/ln.lhr/sq ft/"F Btullbl"F 67 0.073 70 0.080 74 0.090 83 0.103 89 0.109 96 0.116 109 0.120 120 0.125 131 0.130 143 0.137 154 0.151 164 0.171

Material heat-treated 2100°F/3 hr, A.C., + 1 SSO"F/24 hr, A.C., + 1300°F/20 hr, A.C.

Table 4 - Effect of Heat Treatment on Room-Temperature Resistivity of Hot-Rolled Bar Heat Treatment As hot-rolled 2000°F11 hr, A.c.

2100°F/1 hr, A.C.+1500°F/24 hr, A.C.+

1300°F/20 hr, A.C.

1000°F11 hr, A.C.+1350°F/8 hr,F.C. to 1150°F.

hold at 1150°F for total time of 18 hr, A.C.

Resistivity, ohm/clrc mlVft 759 763 724 739 Temperature, "F

so*

500 1000 1200 1350 1500 1600 1600 Electrical Diffusivity, Resistivity, sqMlr ohm/clrc mlVft 0.150 0.143 0.135 0.132 731 0.133 739 0.140 746 0.148 761 0.156 771 0.169 783 0.173 786 0.172 775 0.164 761 Table 5 - Modulus of Elasticity Modulus of Elasticity, 1 a3 ksl Tension Torsion Static Dynamic Static 31.0 31.0 11.0 26.7 29.1 10.2 25.0 26.7 9.0 23.0 25.5 B.1 21.0 24.4 18.5 23.2 22.1 20.0

Poisson's ratio = 0.29 Mechanical Properties INCONEL alloy X-750 may be given any one of a variety of heat treatments. Each develops special properties and puts the product form in the best condition for its intended application. In all conditions, alloy X-750 is resistant to oxidation up to 1800°F. The most often used heat treatments have been incorporated by the Society of Automotive Engineers in their AMS specifications* for various product forms. The heat treatments, specifications, and product forms are summarized in Table 6.

AMS spcc1ficahons are subject to re\\ 1sion. The ones referenced in this publication were current when 1t was released. Publisher is the Society of Automoll\\'e Engineers. Inc 2

Page 37 of 41

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v t e Letter Sequence Request
EPID:L-2018-LLA-0305, Exemption - Oyster Creek - Change Adiabatic Heat-Up Calc (Approved, Closed)
Initiation Request, Request Acceptance Administration Questions 24 January 2019 Answers Results Approval, Approval, Approval, Approval, Approval Other:
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