RA-18-092, 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

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)

Text

Michael P. Gallagher Exelon Generation ~

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

Subject:

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 10 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 10 CFR 50.47(b), 10 CFR 50.47(c)(2), and 10 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 10 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 1O 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 10 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 10 CFR 51.22(c}(9} and does not require an environmental review. Therefore, pursuant to 10 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

Attachment 1 Oyster Creek Nuclear Generation Station Description and Evaluation of Proposed Changes

Attachment 1 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

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 Attachment 1 Permanently Defueled Emergency Plan Page 1 of 6 Proposed Effective and Implementation Dates Change 1.0

SUMMARY

DESCRIPTION Pursuant to 10 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 10 CFR 50.47(b),

10 CFR 50.47(c)(2), and 10 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), 10 CFR 50.47(c)(2), and 10 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 1O 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 Attachment 1 Permanently Defueled Emergency Plan Page 2 of 6 Proposed Effective and Implementation Dates Change 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 1O 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 Attachment 1 Permanently Defueled Emergency Plan Page 3 of 6 Proposed Effective and Implementation Dates Change 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 10 CFR 50.47 and 10 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 1O 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 1o 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 10 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 Attachment 1 Permanently Defueled Emergency Plan Page 4 of 6 Proposed Effective and Implementation Dates Change 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 1O 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 Attachment 1 Permanently Defueled Emergency Plan Page 5 of 6 Proposed Effective and Implementation Dates Change 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 10 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 10 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 Attachment 1 Permanently Defueled Emergency Plan Page 6 of 6 Proposed Effective and Implementation Dates Change 7 .0 REFERENCES

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)

Attachment 2 Oyster Creek Nuclear Generation Station Zirconium Fire Analysis for Drained Spent Fuel Pool, C-1302-226-E310-457, Revision 1

CC-AA-309-1001-Fl Revision 9 Page 1of41 Design Analysis l.._~~~!.!'.~Y.!..~.?._*_*_4_1_ _ _ _ _ _ _ _ _---1 Analysis No.: ' C-1302-226-E310-457 Revision:' 1 Major 181 Minor O

Title:

3 Oyster Creek Nuclear Generating Station Zirconium Fire Analysis for Drained Spent Fuel Pool EC/ECR No.:

• 624353 Revision:* 0 Station(s): ' OCNGS Component(s): **

Unit No.:* 1 NIA Discipline:

• MECH Descrip. Code/Keyword: ** NIA Safety/QA Class: NSR System Code: " NIA Structure: " SFP CONTROLLED DOCUMENT REFERENCES '"

Document No.: From/To Document No.: From/To C-1302-226-EJ 10-458, RO From GEH-0000-0118-3544, R1 From DB-0011.03, R1 From 26A7584,RO From 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 Print Name

~ f _,,,______, 6/5/2018 Sian N* me Date Method of Review: ,. Detailed Review 181 Alternate Calculations (attached) D Testing 0 Reviewer: " Dwayne Blay~ck ~,.,...e------ 61512018 Print Name ~ Sigo Name Dale Review Notes: 2' Independent review t8:1 Peer rev ew 0 This calculation has been independently reviewed per CC-AA-309 and CC-AA-309-1001 . All comments have been satisfactorily incorporated.

(For El<temal Analy$8S Only)

External Approver: ,. Guy Spikes ~ L .1 "'-c.. 6/5/2018 Exelon Reviewer: 2~ * ~oSC{(IPr>C'$:z:-u!f Print Name aA /?Pt:Z;N"""'

'- / .ISian N*~

7/J;'J1R I *~e 0

e-rle""J- i;. &-- No~l~

Independent 3rd Party Review Reqd?,. Yes Exelon Approver: ,. //

Print Na SionName

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 ~ LJ D have sufficient be readily retrievable within Exelon's documentation system.

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 Attachment 2 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 Attachment 2 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 IZI 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 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.

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.

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

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

C-1302-226-E310-457 Rev. 1 Page 6 of41

1.0 Purpose and Scope

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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 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 Attachment 2. 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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> (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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> heat-up time from 30 °C to 900 °C. NUREG-1738 shows that a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

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 0.50x10 3 J/kg*K (Reference 4), and

C-1302-226-E310-457 Rev. 1 Page 7 of 41 lnconel X-750 is 0.43x10 3 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/cm 3 (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/cm 3 (661.74 lb/ ft 3) (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)

Modeled as Zircaloy-2 Total 28.35 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 assem y

= 1979 bl 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):

!ff cj = m X Cp Xt-m = pxV Where:

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 ft 3 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:

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

Where:

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 = -.-q x (Pu x Vu x Cp,u + Pz x 11z x Cp,z + mz x Cp,z)

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:

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 Equation 7-6:

2 2 l'z,wr = ( Tr X Dw,o -

4 Dw,i )

Nwr X LFL Where:

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 Equation 7-7:

Where:

Vz,ch is the volume of zircaloy-2 in the channel Wch is the channel width thch is the minimum channel thickness Equation 7-8:

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:

2 2

_ C0.3496 12 in/ft) in ) 145.24 in ) (( (0.3496 in) 12 in/ft ) 102 in )

Vu - rr x 78 rods x . If + Tr x 8 rods x 12 . If

(( 4 12 m t 4 m t (0.3496 in) 2 ) )

12 in/ft 54 in

+ Tr x

(( 4 6 rods x 12 in/ft = 0.693 ft 3 The volume of zircaloy-2 in the cladding is determined below using Equation 7-5:

0.404 in) 2 (0.3567 in) 2 )

( 12 )

in/ft - 12 in/ft 145.24 in Vz,cl = 7r x 4 78 rods x 12 in/ft

((

0.404 in) 2 (0.3567 in) 2 )

( 12in/ft )

- 12in/ft 102in

+ (( rrx 4 8rodsx12in/ft 0.404 in) 2 (0.3567 in) 2 )

( 12 )

in/ft - 12 in/ft 54 in

+ rr x 6 rods x . If = 0.204ft 3

(( 4 12 Ln t The volume of zircaloy-2 in the water rods is determined below using Equation 7-6.

0.980 in) 2 (0.920 in) 2)

( 12 in/ft - 12 in/ft 145.24 in 3 l'z,wr = 7r x 4

2 rods X 12 in/ft = 0.015 ft

(

C-1302-226-E310-457 Rev. 1 Page 14 of41 The volume of zircaloy-2 in the channel is determined below using Equation 7-7.

5.283 in 0.05 in 145.24 in Vz,ch = 12 in/ft x 12 in/ft x 12 in/ft x 4 = 0.089 ft 3 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 BTU BTU )

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

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

Table 3: Results End Temperature (°C, "F) Decay Time (years) Heat-Up Time (hours) 565,1049 0.75 5.89 565,1049 1 7.13 565,1049 1.25 8.34 565,1049 1.5 9.56 565,1049 2 12.09 565, 1049 3 17.28 900,1652 0.75 9.74 900,1652 1 11.78 900,1652 1.25 13.78 900,1652 1.5 15.81 900, 1652 2 19.98 900,1652 3 28.56

C-1302-226-E310-457 Rev. 1 Page 15 of 41 The 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 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 <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 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.

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0 QJ

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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

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11. 11 ll6 Page 16 of 41

Attachment 2 C-1302-226-E310-457 Rev. 1 Page 17of41 Decay Heat Calculation 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 assembl.ies x MTU = 19.0024 MWt/ MTU 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) (W/MTU) (W/MTU) (W/MTU) (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

Attachment 3 C-1302-226-E310-457 Rev. 1 NUCLEAR FUELS TRANSMITTAL OF DESIGN INFORMATION D SAFETY RELATED Originating Organization NF ID# NF183597 fgJ NON-SAFETY RELATED fgJ Nuclear Fuels Revision 0 D REGULATORY RELATED 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 f

!/,,4f'".~/t!.

/1:;h-/:rt :;.:* ./

2/16/2018 Ferheen Qureshi Prepared by Signature Date

'/{(;. {)if~~ ' 2/16/2018 Robert Potter Reviewed by Signature Date Armando Johnson Approved by Signature

~ 16FEB18 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. Attachment 2: Oyster Creek Cycle 26 Fuel Bundle Identification Array

3. Attachment 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.

Armando Johnson Supplemental Distribution:

Brian Froese NCS Controlled Documents Distribution Page 18 of41

Attachment 3 C-1302-226-E310-457 Rev. 1 TOOi NF183597 Rev.O Page 2of18 ATTACHMENT 1: Oyster Creek Cycle 26 Fuel Bundle Inventory BUNDLE NO. FUEL BUt~Dl.E DESCRIPTION CHANHEL CYCU: BATCH TYPe MATERIAL. LOADED ID RANGE 6 48 GNF2-P100G2BJ70-16GZ-100l2-145-T6-3J56 ZR2RX 23 JYN41J-JYN460 7 12 GNF2-P10DG28369-16GZ-100T2-145-T6-JJ57-lTO ZR2RX 23 JYN501..JYN516 8 32 GNF2-P1 ODG2BJ70-16GZ-100T2-145-T6-4137 ZR2RX 24 JYX370..JYX401 9 16 GNF2-P10DG2Bl72-14GZ-100T2-145-T6-41J8 ZR4RX 24 JYX426-JYX441 10 16 GNF2-P1 ODG2BJ70-15GZ-100T2-145-T6-3355 ZR2RX 23 JYN381..JYN404 11 40 GNF2-P1 ODG2BJ71-14GZ-100T2-145-T6-4300 ZR2RX 25 YLD792-YLD831 12 24 GNF2-P10DG28371-16GZ-100T2-145-T6-4301 ZR2RX 25 YLD856-YLD879 13 16 GNF2-P1 ODG2BJ70-16GZ-1 OOT2-145-T6-J356 ZR4RX 23 JYN461..JYN476 14 16 GNF2-P1 ODG2BJ69-16GZ-1 OOT2-145-T6-JJ57-LTO ZR4RX 23 JYN525..JYN540 15 24 GNF2-P1 OOG2BJ72-14GZ-100l2-145-T6-41J8 ZR2RX 24 JYX402.JYX425 17 48 GNF2-P10DG2BJ71-14GZ-100T2-145-T6-41J6 ZR4RX 24 JYXJ22.JYXJ69 20 32 GNF2-P1 ODG2B371-14GZ-100T2-145-T6-41J6 ZR2RX 24 JYX290..JYXJ21 21 24 GNF2-P10DG2B369-16GZ-100T2-145-T6-430J ZR2RX 25 YLD888-YLD911 22 24 GNF2-P1 ODG2BJ71-14GZ-100T2-145-T6-4JOO ZR4RX 25 VLD832-VLD855 23 8 GNF2-P10DG2BJ71-16GZ-100T2-145-T6-4301 ZR4RX 25 VLD880-VLD887 24 32 GNF2-P1 OOG28369-16GZ-1 OOT2-145-T6-4JOJ ZR4RX 25 YLD912-YLD943 25 8 GNF2-P1 OOG28370-12GZ-100T2-145-T6-44J7 ZR2RX 26 Yll555-YLL562 26 56 GNF2-P10DG2BJ46-1 JGZ-100T2-145-T6-44J5-lTO ZR2RX 26 YLL423-YLL478 27 44 GNF2-P10DG2BJ43-14GZ-100T2-145-T6-4436-LTO ZR2RX 26 YLL479-Yll522 28 8 GNF2-P100G2BJ46-1JGZ-1 OOT2-145-T6-4435-l TO ZR4RX 26 Yll415-Yll422 29 32 GNF2-P10DG2BJ70-12GZ-100T2-145-T6-4437 ZR4RX 26 Yll523-YLL554 SUM= 560 Page 19 of 41

Attachment3 C-1302-226-E310-457 Rev. 1 TOOi NF183597 Rev.a Page 3of18 ATTACHMENT 2: Oyster Creek Cycle 26 Fuel Bundle Identification Array J/I 1 2 3 4 5 6 7 8 9 10 11 12 13 (PANAC) 1 JYN462 JYN509 JYN454 JYN382 JYN445 52 2 JVN438 JYN469 JYX323 YL0929 YLD937 YLD873 50 3 JVN534 JYN413 JYN422 JYN398 YLD905 YLD825 YLD809 YLD913 JVX363 48 4 JYNSOl JYN430 JYN502 YLD921 YLD849 JYX379 YLD880 JYX402 YLD817 VLD793 46 5 JYN533 JYN429 JYX386 YLD865 YLD897 YLD83 3 VLD857 Yll432 YllSOO VLL508 Yll416 44 6 JYN414 JYN529 YLD864 JYX338 YLD801 JYX299 YLL492 JYX307 Yll440 JYX427 JYX347 42 7 JYN421 VLD920 Yl0896 YLD800 VLL479 YLL484 YLD841 Yll556 JYX291 Yll540 YLD889 40 8 JYN437 JYN397 YLD848 YLD832 JYX298 YLL483 JYX419 YLL424 JYX435 Yll532 JYX395 YLL516 38 9 JYN461 JVN470 YLD904 JYX378 YLD856 VLL491 VL0840 VLL423 JYX354 Yll524 JYX411 Yll456 JYX315 36 10 JYN525 JYX322 YLD824 YLD881 YLL431 JYX306 Yll555 JYX434 YLL523 JYX339 Yll448 JYX370 Yll548 34 11 JVN453 YLD928 YL0808 JYX403 YLL499 YLL439 JYX290 VLL531 JYX410 Yll447 JYX387 Yll464 JYX330 32 12 JYN381 VLD936 YLD912 YLD816 Yll507 JYX426 YLL539 JYX394 YLL455 JYX371 Yll463 JYX355 YLL472 30 13 JYN446 YLD872 JYX362 YLD792 Yll415 JYX346 YLD888 YLLSlS JYX314 YLL547 JYX331 Yll471 JYX418 28 14 JYN451 YLD879 JYX369 YLD799 Yll422 JYX353 YLD895 YLL522 JVX321 Yll554 JYX336 Yll478 JYX425 26 15 JYN388 VL0943 VLD919 YLD823 Yll514 JYX433 YLL546 JYX401 YLL462 JYX376 Vll470 JYX360 VLL477 24 16 JYN460 YLD935 YLD815 JYX408 YLL506 Yll446 JYX297 Yll538 JYX417 Yll454 JYX392 YLL469 JVX337 22 17 JYN528 JVX329 YLD831 YLD886 Yll438 JYX313 YLL562 JYX441 YLL530 JYX344 VLL453 JYX377 Vll553 20 18 JYN468 JYN475 YLD911 JYX385 YLD863 YLL498 YLD847 YLL430 JYX361 Yll529 JYX416 YLL461 JVX320 18 19 JYN444 JYN404 VLD855 YL0839 JYX305 Yll490 JYX424 YLL429 JYX440 Yll537 JYX400 VLL521 16 20 JYN428 YLD927 YLD903 YLD807 YLL482 Yll489 YLD846 Yll561 JYX296 YLL545 YL0894 14 21 JYN419 JYN532 YLD871 JYX345 YLD806 JYX304 YLL497 JYX312 YLL445 JYX432 JYX352 12

22. JYN540 JYN436 JYX393 YLD870 YLD902 YLD838 YLD862 YLL437 YLLSOS YLL513 YLL421 10 23 JYN508 JYN435 JYN507 YLD926 YLD854 JYX384 YLD887 JYX409 VLD822 YLD798 8 24 JYN539 JYN420 JYN427 JVN403 YLD910 YLD830 YLD814 YLD918 JYX368 6 25 JYN443 JVN476 JYX328 YLD934 YLD942 YLD878 4 26 JVN467 JVN516 JYN459 JYN387 JYN452 2 X/Y 1 5 1 9 11 13 15 17 19 21 23 25 (SITE)

Page 20 of41

Attachment 3 C-1302-226-E310-457 Rev. 1 TOOi NF183597 Rev.a Page 4 of 18 J/1 14 15 16 17 18 19 10 21 ll 23 24 25 26 (PANAC) 1 JYN448 JYN383 JYN455 JYN512 JYN463 52 1 YLD874 YLD938 YLD930 JYX324 JVN472 JYN439 50 3 JYX364 YLD914 YLD810 YLD826 YLD906 JYN399 JYN423 JYN416 JYN535 48 4 YLD794 YLD818 JYX405 YLD883 JYX380 YLD850 YLD922 JYN503 JYN431 JYN504 46 5 YLL417 YLL509 YLLSOl YLL433 YLD858 YLD834 YLD898 YLD866 JYX389 JVN432 JYN536 44 6 JYX348 NX428 Yll441 JYX308 YLL493 JYX300 YLD802 JYX341 YLD867 JYN530 JYN415 42 7 YLD890 YLL541 JYX292 YLL557 YLD842 YLL485 Yll480 YLD803 YLD899 YLD923 JYN424 40 8 YLL517 JYX396 YLL533 JYX436 Yll425 JYX420 YLL486 JYX301 YLD835 YLD851 JYN400 JYN440 38 9 JYX316 YLL457 JVX412 YLLS25 JYX357 YLL426 YLD843 YLL494 YLD859 JYX381 YLD907 JYN471 JYN464 36 10 YLL549 JVX373 YLL449 JYX340 YLL526 JYX437 YLL558 JYX309 YLL434 YLD882 YLD827 JYX325 JVN526 34 11 JYX333 Yll465 JYX388 YLL450 JVX413 Vll534 JYX293 YLL442 VLL502 JVX404 YLD811 YLD931 JYN456 32 1l YLL473 JYX356 YLL466 JVX372 Yll458 JVX397 YLL542 JYX429 YLLSlO YLD819 YLD915 YLD939 JYN384 30 B JYX421 YLL474 JYX332 YLLSSO JYX317 YLL518 YLD891 JYX349 YLL418 YLD795 JYX365 YLD875 JYN447 28 14 JYX422 VLL475 JYX335 YLLSSl JYX318 YLL519 YLD892 JYX350 VLL419 YLD796 JYX366 YLD876 JYN450 26 15 YLL476 JYX359 YLL467 JYX375 YLL459 JYX398 YLL543 JYX430 Yll511 YLD820 YLD916 YLD940 JYN385 24 16 JYX334 YLL468 JYX391 YLL451 JYX414 YLL535 JYX294 YLL443 Yll503 JYX407 YLD812 YLD932 JVN457 11 17 YLL552 JYX374 YLL452 JYX343 YLL527 JYX438 YLL559 JYX310 YLL435 YLD885 YLD828 JYX326 JYN527 20 18 JYX319 YLL460 JYX415 Yll528 JYX358 Yll427 YLD844 YLL495 YLD860 JYX382 YLD908 JYN474 JYN465 18 19 Yll520 JYX399 Yll536 JYX439 YLL428 JYX423 YLL487 JYX302 YLD836 YLD852 JYN401 JVN441 16 20 YLD893 YLL544 JYX295 YLL560 YLD845 YLL488 YLL481 YLD804 YLD900 YLD924 JYN425 14 21 JYX351 JYX431 YLL444 JYX311 VLL496 JYX303 YLD805 JVX342 VLD868 JVN531 JVN418 1l 22 YLL420 YLL512 YLLS04 YLL436 YLD861 YLD837 YLD901 YLD869 JYX390 JVN433 JYN537 10 13 YLD797 YLD821 JYX406 YLD884 JVX383 YLD853 YLD925 JVN506 JYN434 JYNSOS 8 24 JYX367 YLD917 VLD813 YLD829 YLD909 JYN402 JYN426 JYN417 JYN538 6 25 VLD877 YL0941 YL0933 JYX327 JYN473 JYN442 4 26 JYN449 JVN386 JYN458 JVN513 JYN466 2 X/Y 27 29 31 :B 35 37 39 41 43 45 47 49 51 (SITE)

Page 21 of 41

Attachment 3 C-1302-226-E310-457 Rev. 1 TOOi NF183597 Rev.a Page 5of18 ATTACHMENT 3: Oyster Creek Cycle 26 Fuel IAT Map 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 13 7 6 10 6 6 10 6 7 13 52 l 6 13 17 24 24 12 12 24 24 17 13 6 50 3 14 6 6 10 21 11 11 24 17 17 24 11 11 21 10 6 6 14 48 4 7 6 7 24 22 8 23 15 11 11 11 11 15 23 8 22 24 7 6 7 46 s 14 6 8 12 21 22 12 26 27 27 28 18 27 27 26 12 22 21 12 8 6 14 44 6 6 14 12 17 11 20 27 20 26 9 17 17 9 26 20 27 20 11 17 12 14 6 42 7 6 24 21 11 27 17 22 25 20 19 l1 21 29 10 25 22 17 27 11 21 24 6 40 8 6 10 22 22 20 27 15 26 9 29 8 27 27 8 29 9 26 15 17 20 22 22 10 6 38 9 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 36 10 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 34 11 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 32 12 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 30 13 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 28 14 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 26 15 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 24 16 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 22 17 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 20 18 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 18 19 6 10 22 22 20 27 15 26 9 29 8 27 27 8 29 9 26 15 27 20 22 22 10 6 16 20 6 24 21 11 27 27 22 25 20 19 21 21 29 20 25 22 27 27 11 21 24 6 14 21 6 14 12 17 11 20 27 20 26 9 17 17 9 26 20 27 20 11 17 11 14 6 12 22 14 6 8 12 21 22 12 26 27 27 28 28 27 27 26 12 22 21 12 8 6 14 10 23 7 6 7 24 22 8 23 15 11 11 11 11 15 23 8 22 24 7 6 7 8 24 14 6 6 10 21 11 11 24 17 17 24 11 11 21 10 6 6 14 6 25 6 13 17 24 24 12 12 24 24 17 13 6 4 26 13 7 6 10 6 6 10 6 7 13 2 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

Attachment3 C-1302-226-E310-457 Rev. 1 TODI NF183597 Rev.O Page 6of18 ATTACHMENT 4: Oys t er C ree k C.ye Ie 26 F ue I Bun di e E xposure, u ramu m Mass, & Enrichment 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

Attachment 3 C-1302-226-E310-457 Rev. 1 TOOi NF183597 Rev.a Page 7 of 18 JYN540 14 47.7202 0.181000 0.036878 JYN501 7 47.3498 0.180795 0.036899 JYN429 6 44.6650 0.180914 0.036991 JYN529 14 42.2695 0.180882 0.036876 YLD920 24 27.4228 0.180421 0.036866 YLD848 22 29.2999 0.180549 0.037109 JYX378 8 44.8288 0.180675 0.036927 YLD881 23 31.2113 0.180360 0.037077 JYX403 15 46.9403 0.180663 0.037160 YLD816 11 32.7881 0.180477 0.037103 YLD792 11 32.6462 0.180476 0.037100 YLD799 11 32.6869 0.180409 0.037105 YLD823 11 32.7571 0.180571 0.037092 JYX408 15 46.9685 0.180746 0.037182 YLD886 23 31.2930 0.180373 0.037080 JYX385 8 44.8688 0.180675 0.036957 YLD855 22 29.2650 0.180620 0.037115 YLD927 24 27.4035 0.180413 0.036868 JYN532 14 42.2820 0.181096 0.036895 JYN436 6 44.6691 0.180912 0.037004 JYN508 7 47.3109 0.180898 0.036878 JYN534 14 47.6497 0.181186 0.036883 JYN430 6 44.4073 0.180948 0.037021 JYX386 8 40.1257 0.180689 0.036950 YLD864 12 28.3874 0.180331 0.037081 YLD896 21 30.6601 0.180305 0.036862 YLD832 22 31.8674 0.180541 0.037099 YLD856 12 31.5925 0.180333 0.037083 YLL431 26 16.8696 0.180710 0.034588 YLL499 27 17.8470 0.180610 0.034378 YLL507 27 17.9508 0.180526 0.034361 YLL415 28 17.0129 0.180802 0.034558 YLL422 28 17.0061 0.180803 0.034594 YLL514 27 17.9331 0.180491 0.034370 YLLS06 27 17.8062 0.180729 0.034359 YLL438 26 16.8367 0.180738 0.034586 YLD863 12 31.6397 0.180358 0.037075 YLD839 22 31.8582 0.180528 0.037116 YLD903 21 30.6213 0.180325 0.036856 YLD871 12 28.3465 0.180335 0.037092 JYX393 8 40.1549 0.180567 0.036945 JYN435 6 44.6145 0.180910 0.037006 JYN539 14 47.7421 0.180974 0.036871 JYN413 6 45.9948 0.180756 0.037000 Page 24 of 41

Attachment 3 C-1302-226-E310-457 Rev. 1 TOOi NF183597 Rev.O Page 8of18 JYN502 7 44.9950 0.180802 0.036895 YLD865 12 28.3737 0.180349 0.037085 JYX338 17 41.8157 0.181108 0.037098 YLD800 11 32.7274 0.180516 0.037084 JYX298 20 45 .6360 0.181269 0.037053 YLL491 27 17.0019 0.180551 0.034387 JYX306 20 44.1676 0.181211 0.037062 YLL439 26 18.5264 0 .180697 0 .034572 JYX426 9 44.7833 0.180649 0.037184 JYX346 17 44.4934 0.181069 0.037058 JYX353 17 44.5266 0.180972 0.037066 JYX433 9 44.7559 0.180754 0.037186 YLL446 26 18.4791 0.180800 0.034561 JYX313 20 44.1772 0.181120 0.037089 YLL498 27 16.9705 0.180516 0.034372 JYX305 20 45.6561 0.181209 0.037069 YLD807 11 32.7196 0.180492 0.037087 JYX345 17 41.8993 0.180865 0.037066 YLD870 12 28.3263 0.180307 0.037088 JYN507 7 45.0657 0.180806 0.036880 JYN420 6 45.9565 0.180962 0.037014 JYN422 6 48.6226 0.180838 0.036993 YLD921 24 27.4097 0.180460 0.036868 YLD897 21 30.6819 0.180310 0.036861 YLD801 11 32.7223 0.180507 0.037085 YLL479 27 17.0117 0.180544 0.034372 YLL483 27 17.7602 0.180552 0.034368 YLD840 22 34.4626 0.180564 0.037114 YLL555 25 18.8889 0.180792 0.036976 JYX290 20 43.2128 0.181331 0.037106 YLL539 29 18.1641 0.180677 0.036984 YLD888 21 34.7157 0.180372 0.036860 YLD895 21 34.7338 0.180292 0.036853 YLL546 29 18.0942 0.180766 0.036963 JYX297 20 43 .2096 0.181285 0.037071 YLL562 25 18.8547 0.180759 0.036995 YLD847 22 34.4445 0.180537 0.037117 YLL490 27 17.7204 0.180425 0.034404 YLL482 27 16.9472 0.180531 0.034374 YLD806 11 32.7282 0.180412 0.037103 YLD902 21 30.6202 0.180246 0.036860 YLD926 24 27.3851 0.180371 0.036867 JYN427 6 48.7491 0.180854 0.037044 JYN438 6 46.7672 0.180935 0.037015 Page 25 of 41

Attachment 3 C-1302-226-E310-457 Rev. 1 TODI NF183597 Rev.a Page 9of18 JYN398 10 44.8150 0.180889 0.037028 YLD849 22 29.3201 0.180606 0.037108 YLD833 22 31.6552 0.180518 0.037099 JYX299 20 45.6437 0.181246 0.037045 YLL484 27 17.7907 0.180577 0.034372 JYX419 15 48.2107 0.180746 0.037178 YLL423 26 18.6980 0.180753 0.034604 JYX434 9 43.2434 0.180742 0.037213 YLLS31 29 18.1953 0.180699 0.036989 JYX394 8 42.7113 0.180557 0.036936 YLLS15 27 18.4323 0.180536 0.034359 YLL522 27 18.4274 0.180438 0.034361 JYX401 8 42.7385 0.180634 0.036955 YLL538 29 18.1391 0.180677 0.036960 JYX441 9 43.2669 0.180616 0.037193 YLL430 26 18.6839 0.180659 0.034566 JYX424 15 48.2397 0.180634 0.037186 YLL489 27 17.7201 0.180444 0.034403 JYX304 20 45.6197 0.181183 0.037072 YLD838 22 31.8546 0.180477 0.037107 YLD854 22 29.2622 0.180618 0.037121 JYN403 10 44.9218 0.180869 0.037058 JYN443 6 47.1285 0.180906 0.036992 JYN462 13 46.8231 0.180805 0.037003 JYN469 13 45.7639 0.180774 0.036986 YLD905 21 28.2960 0.180282 0.036846 JYX379 8 44.7244 0.180721 0.036964 YLD857 12 31.5714 0.180313 0.037083 YLL492 27 17.0837 0.180564 0.034390 YLD841 22 34.3358 0.180563 0.037118 YLL424 26 18.7500 0.180762 0.034604 JYX354 17 42.4193 0.180987 0.037075 YLLS23 29 17.1289 0.180726 0.036985 JYX410 15 45.3287 0.180792 0.037177 YLL455 26 18.4172 0.180728 0.034558 JYX314 20 46.8374 0.180960 0.037070 JYX321 20 46.8404 0.180927 0.037078 YLL462 26 18.3917 0.180710 0.034554 JYX417 15 45.3668 0.180656 0.037160 YLL530 29 17.2251 0.180674 0.036995 JYX361 17 42.4970 0.180940 0.037069 YLL429 26 18.6871 0.180687 0.034572 YLD846 22 34.4469 0.180528 0.037123 YLL497 27 16.9617 0.180648 0.034371 Page 26 of 41

Attachment 3 C-1302-226-E310-457 Rev. 1 TOOi NF183597 Rev.a Page 10 of 18 YLD862 12 31.6431 0.180319 0 .037071 JYX384 8 44.8613 0.180668 0.036974 YLD910 21 28.1812 0.180339 0.036845 JYN476 13 46.0016 0.180996 0.036985 JYN467 13 46.8525 0.180784 0.036988 JYN509 7 45.8381 0.180834 0.036886 JYX323 17 34.5627 0.181008 0.037085 YLD825 11 28.7401 0.180503 0.037088 YLD880 23 31.3415 0.180345 0.037076 YLL432 26 16.9735 0.180626 0.034585 JYX307 20 44.0520 0.181211 0.037057 YLL556 25 19.0264 0.180757 0.036966 JYX435 9 42.8704 0.180732 0.037200 YLLS24 29 17.1724 0.180727 0.036984 JYX339 17 44.0875 0.180968 0.037070 YLL447 26 18.4052 0.180799 0.034578 JYX371 8 48.0557 0.180648 0.036922 YLL547 29 17.7631 0.180717 0.036968 YLL554 29 17.7460 0.180784 0.036964 JYX376 8 48.1056 0.180609 0.036942 YLL454 26 18.3937 0.180723 0.034578 JYX344 17 44.5069 0.180964 0.037083 YLL529 29 17.2271 0.180733 0.036992 JYX440 9 43.2925 0.180499 0.037174 YLL561 25 18.8723 0.180753 0.036973 JYX312 20 44.1475 0.181152 0.037066 YLL437 26 16.8377 0.180739 0.034582 YLD887 23 31.2919 0.180362 0.037081 YLD830 11 28.6645 0.180542 0.037104 JYX328 17 35.2568 0.181036 0.037069 JYN516 7 45.8050 0.180858 0.036857 JYN454 6 47.0448 0.180882 0.036991 YLD929 24 28.0211 0.180444 0.036863 YLD809 11 31.0860 0.180415 0.037107 JYX402 15 47.0036 0.180705 0.037185 YLLSOO 27 17.9618 0.180560 0.034370 YLL440 26 18.6669 0.180683 0.034574 JYX291 20 42.4912 0.181339 0.037101 YLL532 29 18.3131 0.180738 0.036981 JYX411 15 45.3085 0.180718 0.037179 YLL448 26 18.4315 0.180792 0.034587 JYX387 8 46.4990 0.180674 0.036947 YLL463 26 18.7416 0.180821 0.034582 JYX331 17 47.1711 0.181025 0.037069 Page 27 of 41

Attachment 3 C-1302-226-E310-457 Rev. 1 TODI NF183597 Rev.O Page 11 of 18 JYX336 17 47.2424 0.180949 0.037064 YLL470 26 18.7059 0.180779 0.034580 JYX392 8 46.6144 0.180578 0.036949 YLL453 26 18.4077 0.180657 0.034578 JYX416 15 45.3017 0.180679 0.037195 YLL537 29 18.1883 0.180713 0.036968 JYX296 20 43.2442 0.181311 0.037095 YLL445 26 18.5003 0.180737 0.034573 YLL505 27 17.8178 0.180638 0.034357 JYX409 15 46.9826 0.180703 0.037185 YLD814 11 31.0527 0.180490 0.037082 YLD934 24 27.9165 0.180399 0.036848 JYN459 6 47.0484 0.180923 0.036991 JYN382 10 46.9554 0.180962 0.037068 YLD937 24 27.5554 0.180422 0.036869 YLD913 24 31.5841 0 .180291 0.036860 YLD817 11 32.8022 0.180478 0.037084 YLL508 27 18.0691 0.180422 0.034351 JYX427 9 44.7431 0.180643 0.037156 YLLS40 29 18.2964 0.180649 0.036988 JYX395 8 42.6552 0.180591 0.036923 YLL456 26 18.4910 0.180643 0.034560 JYX370 8 48.0884 0.180629 0.036913 YLL464 26 18.7501 0.180867 0.034577 JYX355 17 43.3861 0.181006 0.037067 YLL471 26 18.7088 0.180769 0.034560 YLL478 26 18.6844 0.180825 0.034607 JYX360 17 43 .7634 0.180909 0.037068 YLL469 26 18.7096 0.180749 0.034575 JYX377 8 48.0993 0.180655 0.036959 YLL461 26 18.4082 0.180708 0.034558 JYX400 8 42.7886 0.180687 0.036956 YLL545 29 18.1485 0.180701 0.036973 JYX432 9 44.7015 0.180798 0.037184 YLLS13 27 17.9274 0.180527 0.034363 YLD822 11 32.7394 0.180595 0.037097 YLD918 24 31.6334 0.180379 0.036859 YLD942 24 27.4512 0 .180423 0.036860 JYN387 10 47.5847 0.180846 0.037057 JYN445 6 48.3269 0.180967 0.037031 YLD873 12 28.2644 0.180264 0.037090 JYX363 17 42.7492 0.181054 0.037051 YLD793 11 32.4134 0.180525 0.037097 YLL416 28 17.1023 0.180812 0.034562 Page 28 of41

Attachment 3 C-1302-226-E310-457 Rev. 1 TODI NF183597 Rev.a Page 12 of 18 JYX347 17 44.3304 0.181120 0.037031 YLD889 21 34.7511 0.180342 0.036858 YLL516 27 18.5141 0.180549 0.034369 JYX315 20 46.8702 0.180989 0.037079 YLL548 29 17.7942 0.180808 0.036948 JYX330 17 47.2091 0.180996 0.037083 YLL472 26 18.7158 0.180790 0.034576 JYX418 15 48.0746 0.180694 0.037180 JYX425 15 48.0784 0.180665 0.037191 YLL477 26 18.6809 0.180790 0.034597 JYX337 17 47.2216 0.181034 0.037070 YLL553 29 17.7512 0.180746 0.036965 JYX320 20 46.8314 0.180990 0.037084 YLL521 27 18.4269 0.180489 0.034362 YLD894 21 34.7344 0.180304 0.036848 JYX352 17 44.5040 0.180959 0.037074 YLL421 28 16.9910 0.180755 0.034594 YLD798 11 32.6632 0.180446 0.037104 JYX368 17 43.1878 0.181014 0.037076 YLD878 12 28.1661 0.180345 0.037066 JYN452 6 48.3690 0.180966 0.036985 JYN448 6 48.3978 0.180843 0.037034 YLD874 12 28.2375 0.180317 0.037078 JYX364 17 43.2605 0.181011 0.037059 YLD794 11 32.7562 0.180468 0.037109 YLL417 28 17.0808 0.180749 0.034561 JYX348 17 44.5129 0.181164 0.037020 YLD890 21 34.8123 0.180336 0.036860 YLL517 27 18.4960 0.180505 0.034357 JYX316 20 46.8684 0.180989 0.037067 YLL549 29 17.7924 0.180742 0.036960 JYX333 17 47.2210 0.181061 0.037049 YLL473 26 18.7018 0.180810 0.034581 JYX421 15 48.0658 0.180603 0.037143 JYX422 15 48.0469 0.180635 0.037179 YLL476 26 18.6873 0.180755 0.034599 JYX334 17 47.0472 0.181031 0.037054 YLL552 29 17.7518 0.180725 0.036963 JYX319 20 46.8249 0.180969 0.037072 YLL520 27 18.4231 0.180463 0.034349 YLD893 21 34.6975 0.180340 0.036848 JYX351 17 44.4371 0.180959 0.037084 YLL420 28 16.9791 0.180733 0.034574 YLD797 11 32.6599 0.180435 0.037107 Page 29 of 41

Attachment 3 C-1302-226-E310-457 Rev. 1 TOOi NF183597 Rev.a Page 13of18 JYX367 17 43.1568 0.181045 0.037069 YLD877 12 28.1457 0.180312 0.037075 JYN449 6 48.3112 0.180957 0.037037 JYN383 10 47.5977 0.180914 0.037077 YL0938 24 27.5089 0.180329 0.036871 YLD914 24 31.6962 0.180338 0.036861 YLD818 11 32.8089 0.180482 0.037089 YLL509 27 18.0018 0.180406 0.034336 JYX428 9 44.7523 0.180712 0.037201 YLLS41 29 18.2076 0.180639 0.037003 JYX396 8 42.8235 0.180594 0.036896 YLL457 26 18.4536 0.180680 0.034567 JYX373 8 48.1220 0.180583 0.036919 YLL465 26 18.7294 0.180829 0.034587 JYX356 17 43.7423 0.181017 0.037071 YLL474 26 18.6939 0.180777 0.034586 YLL475 26 18.6875 0.180800 0.034594 JYX359 17 43.7380 0.180934 0.037052 YLL468 26 18.6991 0.180806 0.034569 JYX374 8 48.0115 0.180621 0.036930 YLL460 26 18.3819 0.180741 0.034559 JYX399 8 42.7855 0.180630 0.036907 YLLS44 29 18.1251 0.180696 0.036967 JYX431 9 44.6190 0.180738 0.037192 YLLS12 27 17.8707 0.180410 0.034356 YLD821 11 32.6995 0.180610 0.037108 YLD917 24 31.6061 0.180427 0.036878 YLD941 24 27.4427 0.180426 0.036848 JYN386 10 47.5723 0.180909 0.037058 JYN455 6 47.0339 0.180919 0.036984 YLD930 24 27.9346 0.180489 0.036863 YLD810 11 31.0987 0.180436 0.037102 JYX405 15 46.9953 0.180721 0.037163 YLLSOl 27 17.8793 0.180466 0.034363 YLL441 26 18.5476 0 .180714 0 .034580 JYX292 20 43.2692 0.181318 0.037115 YLLS33 29 18.2307 0.180659 0.036998 JYX412 15 45.3158 0.180765 0.037183 YLL449 26 18.4280 0.180772 0.034579 JYX388 8 46.6409 0.180589 0.036940 YLL466 26 18.7212 0.180838 0.034580 JYX332 17 47.2195 0.181029 0.037055 JYX335 17 47.0755 0.180952 0.037060 YLL467 26 18.7044 0.180788 0.034572 Page 30 of41

Attachment 3 C-1302-226-E310-457 Rev. 1 TODI NF183597 Rev.a Page 14 of 18 JYX391 8 46.5964 0.180592 0.036922 YLL452 26 18.3581 0.180660 0.034589 JYX415 15 45 .2568 0.180713 0.037184 YLL536 29 18.1471 0.180720 0.036970 JYX295 20 43 .2028 0.181321 0.037104 YLL444 26 18.4263 0.180718 0.034560 YLLS04 27 17.7479 0.180588 0.034356 JYX406 15 46.8755 0.180684 0.037191 YLD813 11 31.0278 0.180493 0.037094 YLD933 24 27.8927 0.180406 0.036851 JYN458 6 47.0372 0.180886 0.037003 JYN512 7 45 .7916 0.180877 0.036862 JYX324 17 35.2609 0.181041 0.037065 YLD826 11 28.6710 0.180531 0.037085 YLD883 23 31.3223 0.180373 0.037083 YLL433 26 16.8806 0.180627 0.034592 JYX308 20 44.1635 0.181117 0.037075 YLL557 25 18.9065 0.180757 0.036958 JYX436 9 43.3048 0.180640 0.037212 YLL525 29 17.2571 0.180737 0.036989 JYX340 17 44.5228 0.180962 0.037067 YLL450 26 18.4234 0.180752 0.034581 JYX372 8 48.1106 0.180625 0.036917 YLLS50 29 17.7642 0.180748 0.036970 YLLS51 29 17.7581 0.180747 0.036962 JYX375 8 48.0181 0.180657 0.036935 YLL451 26 18.3540 0.180732 0.034600 JYX343 17 44.3587 0.181029 0.037070 YLLS28 29 17.0527 0.180758 0.036986 JYX439 9 43.2361 0.180529 0.037175 YLLS60 25 18.8327 0.180763 0.036964 JYX311 20 44.0779 0.181150 0.037063 YLL436 26 16.8077 0.180734 0.034591 YLD884 23 31.2685 0.180417 0.037076 YLD829 11 28.6426 0.180575 0.037090 JYX327 17 35.2392 0.181012 0.037071 JYN513 7 45.7883 0.180879 0.036867 JYN463 13 46.8103 0 .180816 0.037006 JYN472 13 45.9928 0.181008 0.036994 YLD906 21 28.2038 0.180346 0.036840 JYX380 8 44.8599 0.180709 0.036939 YLD858 12 31.6743 0.180343 0.037085 YLL493 27 16.9937 0.180595 0.034385 YLD842 22 34.4793 0.180567 0.037113 Page 31 of41

Attachment 3 C-1302-226-E310-457 Rev. 1 TODI NF183597 Rev.a Page 15of18 YLL425 26 18.7117 0.180753 0.034596 JYX357 17 42.4961 0 .180966 0 .037068 YLL526 29 17.2488 0.180785 0.036974 JYX413 15 45.3457 0.180808 0.037170 YLL458 26 18.4295 0.180717 0.034573 JYX317 20 46.8162 0.180992 0.037070 JYX318 20 46.8097 0.180985 0.037091 YLL459 26 18.3910 0.180769 0.034568 JYX414 15 45.3003 0.180693 0.037183 YLL527 29 17.0653 0.180669 0.036993 JYX358 17 42.3661 0.180895 0.037060 YLL428 26 18.6294 0.180682 0.034570 YLD845 22 34.4104 0.180518 0.037122 YLL496 27 16.9414 0.180641 0.034380 YLD861 12 31.6380 0.180315 0.037074 JYX383 8 44.8345 0.180717 0.036972 YLD909 21 28.1736 0.180342 0.036852 JYN473 13 45.9266 0.181026 0.036991 JYN466 13 46.7703 0.180825 0.036975 JYN439 6 47.0967 0.180960 0.037018 JYN399 10 44.9100 0.180857 0.037010 YLD850 22 29.2860 0.180587 0.037108 YLD834 22 31.8787 0.180523 0.037107 JYX300 20 45.6347 0.181261 0.037057 YLL485 27 17.7360 0.180559 0.034376 JYX420 15 48.2466 0.180704 0.037185 YLL426 26 18.7104 0.180755 0.034599 JYX437 9 43.2896 0.180639 0.037202 YLL534 29 18.2155 0.180700 0.036982 JYX397 8 42.7712 0.180673 0.036915 YLL518 27 18.4564 0.180441 0.034353 YLL519 27 18.4400 0.180521 0.034352 JYX398 8 42.7589 0.180643 0.036921 YLL535 29 18.1630 0.180689 0.036972 JYX438 9 43.2414 0.180577 0.037184 YLL427 26 18.6321 0.180701 0.034568 JYX423 15 48.1949 0.180695 0.037164 YLL488 27 17.7090 0.180394 0.034408 JYX303 20 45.5877 0.181226 0.037057 YLD837 22 31.8420 0.180497 0.037106 YLD853 22 29.2584 0.180556 0.037141 JYN402 10 44.9178 0.180862 0.037042 JYN442 6 47.0997 0.180881 0.036994 JYN423 6 48.7261 0.180866 0.037011 Page 32 of 41

Attachment 3 C-1302-226-E310-457 Rev. 1 TOOi NF183597 Rev.a Page 16 of 18 YLD922 24 27.4071 0.180369 0.036875 YL0898 21 30.6300 0.180332 0.036860 YL0802 11 32.7473 0.180475 0.037084 YLL480 27 16.9752 0.180507 0.034375 YLL486 27 17.7359 0.180582 0.034382 YL0843 22 34.4743 0.180556 0 .037109 YLL558 25 18.9016 0.180755 0.036966 JYX293 20 43.2147 0.181368 0.037108 YLL542 29 18.1733 0.180714 0.036992 YLD891 21 34.7475 0.180372 0.036850 YLD892 21 34.7241 0.180326 0.036849 YLL543 29 18.1533 0.180693 0.036984 JYX294 20 43.2177 0.181326 0.037108 YLL559 25 18.8529 0 .180735 0.036978 YLD844 22 34.4300 0.180538 0.037110 YLL487 27 17.7127 0.180421 0.034398 YLL481 27 16.9480 0.180509 0.034369 YLD805 11 32.6698 0.180456 0.037097 YLD901 21 30.6160 0.180272 0.036848 YLD925 24 27.3493 0.180410 0.036864 JYN426 6 48.7193 0.180869 0.037023 JYN416 6 45.9160 0.180940 0.036989 JYN503 7 45.0245 0.180789 0.036892 YLD866 12 28.3478 0.180322 0.037082 JYX341 17 41.8646 0.181001 0.037059 YL0803 11 32.7547 0.180450 0.037089 JYX301 20 45.6097 0.181253 0.037065 YLL494 27 16.9922 0.180614 0.034378 JYX309 20 44.1749 0.181156 0.037071 YLL442 26 18.5303 0.180724 0.034580 JYX429 9 44.7575 0.180783 0.037199 JYX349 17 44.4822 0.181147 0.037037 JYX350 17 44.5041 0.181009 0.037043 JYX430 9 44.7614 0.180712 0.037188 YLL443 26 18.5050 0.180713 0.034579 JYX310 20 44.1491 0.181169 0.037075 YLL495 27 16.9514 0.180650 0.034379 JYX302 20 45.5589 0.181238 0.037040 YLD804 11 32.6742 0.180482 0.037089 JYX342 17 41.8461 0.181063 0.037080 YLD869 12 28.2802 0.180322 0.037089 JYN506 7 45.0556 0.180823 0.036877 JYN417 6 45.9172 0.180947 0.036982 JYN535 14 47.6703 0.181174 0.036881 Page 33 of 41

Attachment3 C-1302-226-E310-457 Rev. 1 TODI NF183597 Rev.O Page 17of18 JYN431 6 44.5828 0.180945 0.037012 JYX389 8 40.1566 0.180608 0.036949 YLD867 12 28.3649 0.180351 0.037084 YLD899 21 30.6292 0.180307 0.036852 YLD835 22 31.8857 0.180497 0.037111 YLD859 12 31.6737 0.180329 0.037080 YLL434 26 16.8676 0.180702 0.034601 YLL502 27 17.8634 0.180458 0.034369 YLL510 27 17.9597 0.180495 0.034359 YLL418 28 17.0242 0.180762 0.034563 YLL419 28 17.0262 0.180703 0.034568 YLL511 27 17.9546 0.180438 0.034353 YLLS03 27 17.8463 0.180460 0.034349 YLL435 26 16.8405 0.180712 0.034594 YLD860 12 31.6518 0.180340 0.037085 YLD836 22 31.8715 0.180499 0.037096 YLD900 21 30.6251 0.180262 0.036852 YLD868 12 28.3021 0.180349 0.037082 JYX390 8 39.9972 0.180603 0.036909 JYN434 6 44.5889 0.180987 0.036996 JYN538 14 47.7226 0.180958 0.036875 JYN504 7 47.3102 0.180779 0.036899 JYN432 6 44.6346 0.180945 0.037014 JYN530 14 42.2638 0.180996 0.036877 YLD923 24 27.4076 0.180420 0.036869 YLD851 22 29.2723 0.180559 0.037121 JYX381 8 44.8622 0.180691 0.036968 YLD882 23 31.3245 0.180365 0.037075 JYX404 15 46.9712 0.180730 0.037173 YLD819 11 32.7664 0.180514 0.037088 YLD795 11 32.6858 0.180485 0.037105 YLD796 11 32.6929 0.180470 0.037108 YLD820 11 32.7636 0.180488 0.037097 JYX407 15 46.9106 0.180726 0.037188 YLD885 23 31.3014 0.180370 0 .037078 JYX382 8 44.8372 0.180726 0.036972 YLD852 22 29.2669 0.180540 0.037136 YLD924 24 27.3770 0.180412 0.036874 JYN531 14 42.2964 0.181041 0.036893 JYN433 6 44.6610 0.180908 0.037005 JYN505 7 47.2923 0.180866 0.036894 JYN536 14 47.6667 0.181143 0.036882 JYN415 6 45.8819 0.180959 0.036975 JYN424 6 48.7400 0.180833 0.037010 Page 34 of 41

Attachment 3 C-1302-226-E310-457 Rev. 1 TOOi NF183597 Rev.a Page 18of18 JYN400 10 44.9677 0.180851 0.037031 YLD907 21 28.2041 0.180342 0.036837 YLD827 11 28.6941 0.180541 0.037080 YLD811 11 31.0758 0.180423 0.037099 YLD915 24 31.6537 0.180397 0.036867 JYX365 17 43.1952 0.181066 0.037053 JYX366 17 43.1893 0.181021 0.037073 YLD916 24 31.6504 0.180346 0.036874 YLD812 11 31.0636 0.180428 0.037095 YLD828 11 28.6772 0.180623 0.037076 YLD908 21 28.1917 0.180347 0.036839 JYN401 10 44.9956 0.180849 0.037018 JYN425 6 48.7368 0.180848 0.037003 JYN418 6 45.9167 0.180939 0.036985 JYN537 14 47.6608 0.181130 0.036881 JYN440 6 47.0781 0.180946 0.037011 JYN471 13 46.0108 0.180827 0.036995 JYX325 17 35.2221 0.181070 0.037052 YLD931 24 27.9411 0.180382 0.036866 YLD939 24 27.4667 0.180338 0.036862 YLD875 12 28.1804 0.180317 0.037076 YLD876 12 28.1532 0.180328 0.037068 YLD940 24 27.4606 0.180331 0.036848 YLD932 24 27.9084 0.180444 0.036863 JYX326 17 35.2539 0.181016 0.037083 JYN474 13 45.9665 0.181023 0.036987 JYN441 6 47.0884 0.180976 0.036991 JYN464 13 46.7866 0.180853 0.036991 JYN526 14 47.2833 0.180833 0.036874 JYN456 6 46.9741 0.180960 0.037002 JYN384 10 47.5578 0.180923 0.037067 JYN447 6 48.3915 0.180952 0.037039 JYN450 6 48.4297 0.180908 0.037020 JYN385 10 47.5995 0.180850 0.037069 JYN457 6 46.9889 0.180900 0.037000 JYN527 14 47.1677 0.180921 0.036880 JYN465 13 46.7419 0.180897 0.036987 Page 35 of 41

Atlachment4 SPECIA1 C-1302-226-E310-457 Rev. 1 MEfA1S www.specialmetals.com JNCONEL alloy X-750 (UNS N07750/W. Nr. 2.4669) Table 1 - Limiting Chemical Composition, %

is a precipitation-hardenable nickel-chromium alloy Nickel (plus Cobalt) ................................................. ... 70.00 min.

used for its corrosion and oxidation resistance and high Chromium ... ................................................................ 14.0-17.0 strength at temperatures to I 300°F. Although much of lron ...................................... ............................................ 5.0-9.0 the effect of precipitation hardening is lost with Titanium...... ..... .. ...... ................. ..... ................... .. ... .... .. 2.25-2. 75 increasing temperature over J300°F, heat-treated Aluminum ............................ .... .......... ................. ......... 0.40-1.00 material has useful strength up to J800°F. Alloy X-750 Niobium (plus Tantalum) ..................................... ......... O. 70-1.20 also has excellent properties down to cryogenic Manganese ................................................................ .1.00 max.

termperatures. Composition is shown in Table I .

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

The economics of INCONEL alloy X-750 coupled with its availability in all standard mill forms has Sulfur............... ....... ....... ....... ................................. ......0.01 max.

resulted in applications in a wide variety of industrial Copper........... ...................... ....... ......... ........... ............0.50 max.

fields . Jn gas turbines, it is used for rotor blades and Carbon ..... ............................ ................................ .......0.08 max.

wheels, bolts, and other structural members. INCONEL Cobalt1.. . .. . ........ . .................. . ...... .. .... .............. . ............ 1.00 max alloy X-750 is used extensively in rocket-engine thrust 'Determination not required for routine acceptance.

chambers. Airframe applications include thrust reversers and hot-air ducting systems. Large pressure vessels are formed from INCONEL alloy X-750. Other Physical Constants and applications are heat-treating fixtures, forming tools, extrusion dies, and test machine grips. For springs and Thennal Properties fasteners, INCONEL alloy X-750 is used from sub-zero Some physical constants and thermal properties of to 1200°F. INCONEL alloy X-750 are given in Tables 2 and 3.

Depending on the application and the properties Values for thermal expansion, thermal conductivity, desired, various heat treatments are employed. For specific heat, and diffusivity are from Lucks and Deem service above 1100°F, particularly where loads are to be and electrical resistivity from tests conducted at Lehigh sustained for long times, optimum properties are University.

achieved by solution treating (2100°F) plus stabilization Effects of temperature on modulus of elasticity and treating ( J550°F) plus precipitation treating ( 1300°F}. additional data on resistivity are in Tables 4 and 5. More For service below 1100°F, the alloy may be modulus values can be found in the section on strengthened by precipitation treating after hot or cold working or by precipitation treating after equalizing or Mechanical Properties.

solution treating. A furnace-cooling treatment is also Table 2 - Physical Constants used to develop optimum properties for some 3 Density, lb/in . .... . . ................ . . . . .. . ... ................ . .. . . .... . . ......... 0.299 applications.

g/cm 3 ....................... . . . . . . .. ......... . ......... . .. .. .. ............. 8.28 The various heat treatments and the properties Melting Range, °F..................... .................................2540-2600 developed are described under the section on

• c.................................................... 1393-1427 Mechanical Properties.

Curie Temperature, °F Property values in this bulletin - the results of As hot-rolled .............................................. -225 extensive testing - are typical of the alloy but, unless Triple-heat-treated (2100°F/2 hr, A.C.,+ 1500°F shown as limiting, should not be used as specification

/24 hr, A.C., + 1300°F/20 hr, A.C.) ... .......... -193 values.

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 Publication No. SMC-067 600°F. ........ ... .. .................. .. ...................... o.095 Copyright© Special Metals Corporation, 2004 (Sept 04) 2000°F. ..... ...... ....... .... .................. ....... ......0.925 Linear Contraction during Precipitation Treatment (1300°F/20 INCONEL, MONEL and Nl-SPAN-C are trademarks of hr), in/in the Special Metals Corporation group of companies. Hot-Rolled ............................................0.00044 20% Cold-Rolled .............................. ... 0.00052 Annealed .. ........ ..... ......... ......................0.00026 Page 36 of41

Attachment 4 C-1302-226-E310-457 Rev. 1 INCONEL* alloy X-750 Table 3 - Thermal Properties*

Mean Linear Electrical Expansion, ln./ln.rF x Thermal Temperature, Conductivity, Specific Heat Diffusivity, Resistivity, "F o-e 1 from 70" F to Btu/ln.lhr/sq ft/"F Btullbl"F sqMlr ohm/clrc Temperature Shown mlVft

-250 6.5 67 0.073 0.150 -

-200 6.6 70 0.080 0.143 -

-100 6.7 74 0.090 0.135 -

70 - 83 0.103 0.132 731 200 7.0 89 0.109 0.133 739 400 7.2 96 0.116 0.140 746 600 7.5 109 0.120 0.148 761 BOO 7.8 120 0.125 0.156 771 1000 8.1 131 0.130 0.169 783 1200 8.4 143 0.137 0.173 786 1400 8.8 154 0.151 0.172 775 1600 9.3 164 0.171 0.164 761 1800 9.8 - - - -

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

Table 4 - Effect of Heat Treatment on Room-Temperature Table 5 - Modulus of Elasticity Resistivity of Hot-Rolled Bar Modulus of Elasticity, 1a3 ksl Resistivity, Temperature, Heat Treatment Tension Torsion ohm/clrc mlVft "F Static Dynamic Static As hot-rolled 759 2000°F11 hr, A.c . 763 so* 31 .0 31 .0 11 .0 2100°F/1 hr, A.C.+1500°F/24 hr, A.C.+ 500 26.7 29.1 10.2 1300°F/20 hr, A.C. 724 1000 25.0 26.7 9.0 1000°F11 hr, A.C.+1350°F/8 hr,F.C. to 1150°F. 1200 23.0 25.5 B.1 hold at 11 50°F for total time of 18 hr, A.C. 739 1350 21.0 24.4 -

1500 18.5 23.2 -

1600 - 22.1 -

1600 - 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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