Text

Supplement to License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations
	ML24191A422
Person / Time
Site:	Palisades
Issue date:	07/09/2024
From:	Fleming J; Holtec Decommissioning International
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	HDI PNP 2024-027
	Download: ML24191A422 (1)
	v • d • e

Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 HOLTEC Telephone (856) 797-0900 DECOMMISSIONING Fax (856) 797-0909 INTERNATIONAL

HDI PNP 2024-027 10 CFR 50.90

July 09, 2024

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Palisades Nuclear Plant NRC Docket No. 50-255 Renewed Facility Operating License No. DPR-20

Reference:

Holtec Decommissioning International, LLC letter to U.S. Nuclear Regulatory Commission (HDI PNP 2023-030), "License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations" dated December 14, 2023 (ADAMS Accession No. ML23348A148)

Subject:

Supplement to License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations

In the above referenced letter, HDI PNP 2023-030, Holtec Decommissioning Internatio nal, LLC (HDI) on behalf of Holtec Palisades LLC, requested U. S. Nuclear Regulatory Commission (NRC) review and approval of a proposed license amendment request (LAR) to revise the Palisades Nuclear Plant (PNP) Renewed Facility Operating License (RFOL) DPR-20. The proposed LAR would revise the RFOL, Appendix A Permanently Defueled Technical Specifications (PDTS), and the Appendix B Environmental Protection Plan (EPP) to reflect the resumption of power operations at PNP.

Since submittal of HDI PNP 2023-030, the NRC has informed HDI of several items that potentially could require clarification or administrative corrections. HDI has reviewed the NRC identified items and is submitting this supplemental information to provide further clarity and administrative corrections to HDI PNP 2023-030.

The enclosure to this letter provides supplemental information to the HDI PNP 2023-030 enclosure titled "Evaluation of Proposed Changes ." Enclosure Attachment 1 to this letter provides updated Proposed Changes (mark-up) to the Palisades Plant Renewed Facility Operating License DRP-20 and Appendix A Permanently Defueled Technical Specifications.

Enclosure Attachment 2 to this letter provides updated retyped RFOL and Technical Specifications (TS) pages. Enclosure Attachment 3 to this letter provides updated TS Bases changes. The proposed TS Bases changes are provided for information and will be incorporated in accordance with the TS Bases Control Program upon implementation of the approved amendment.

HDI PNP 2024-027 Page 2 of 2

This supplement does not alter the no significant hazards consideration or environmental evaluation contained in the above Reference (HDI PNP 2023-030).

In accordance with 10 CFR 50.91(b), State consultation, HDI is notifying the State of Michigan of this LAR supplement by transmitting a copy of this letter, with its enclosures, to the designated State of Michigan official.

This letter contains no new regulatory commitments and no revisions to existing regulatory commitments.

If you have any questions regarding this submittal, please contact Jim Miksa, Manager Regulatory Assurance, Palisades, at (269) 764-2945.

I declare under penalty of perjury that the foregoing is true and correct. Executed on July 09, 2024.

Respectfully,

Digitally signed by Jean A. Fleming Jean A. DN: cn=Jean A. Fleming, c=US, o=Holtec Decommissioning International, LLC, ou=Regulatory and Environmental Affairs, Fleming email=J.Fleming@Holtec.com Date: 2024.07.09 11:14:35 -04'00'

Jean A. Fleming Vice President of Licensing and Regulatory Affairs Holtec International

Enclosure:

Updates to License Amendment Request (LAR) Evaluation of Proposed Changes

Enclosure Attachments:

1. Updated Proposed Changes (mark-up) to Palisades Plant Renewed Facility Operating License DPR-20, Appendix A Permanently Defueled Technical Specifications

2. Updated Retyped Pages for the Palisades Plant Renewed Facility Operating License DPR-20, Appendix A Technical Spec ifications

3. Updated Proposed Technical Specifications Bases Changes (for information only)

cc: NRC Region III Regional Administrator NRC Senior Resident Inspector - PNP NRC Project Manager PNP Designated Michigan State Official HDI PNP 2024-027 Enclosure Page 1 of 14

HDI PNP 2024-027

Enclosure

Updates to License Amendment Request (LAR) Evaluation of Proposed Changes

HDI PNP 2024-027 Enclosure Page 2 of 14 Updates to License Amendment Request (LAR) Evaluation of Proposed Changes

Provided below is supplemental information and administrative updates to the Holtec Decommissioning International, LLC (HDI) letter to the U.S. Nuclear Regulatory Commission (HDI PNP 2023-030), "License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations" dated December 14, 2023 (Reference 1) for Palisades Nuclear Plant (PNP). HDI is submitting this supplemental information to provide further clarity and ad ministrative corrections to HDI PNP 2023-030.

The supplemental information and administrative updates are listed below as items and are arranged in the order in which they appear in HDI PNP 2023-030. For each item the location in HDI PNP 2023-030, the original text in HDI PNP 2023-030 (if applicable), the updated text, and the reason for the change is provided.

Item 1 - HDI PNP 2023-030 Enclosure, Evaluation of the Proposed Changes

Section affected:

Table of Contents, Page 2 of 97 and 3.2 Evaluation of the Proposed Change, page 17 of 97

HDI PNP 2023-030 text Updated text

Table of Contents Table of Contents

3.1.2 Proposed Changes to the 3.2.2 Proposed Changes to the Permanently Permanently Defueled Technical Defueled Technical Specifications Specifications

Section Title Section Title

3.1.2 Proposed Changes to the 3.2.2 Proposed Changes to the Permanently Permanently Defueled Technical Defueled Technical Specifications Specifications

Reason:

The misnumbering of this section is an editorial error. It is listed within section 3.2, Evaluation of the Proposed Change and should be numbered 3.2.2

HDI PNP 2024-027 Enclosure Page 3 of 14

Item 2 - HDI PNP 2023-030 Enclosure, Evaluation of the Proposed Changes

Section affected:

3.2.1, Proposed Changes to the PNP Renewed Facility Operating License, Page 8 of 97, 1st paragraph

HDI PNP 2023-030 text Updated text

"License Conditions removed in Amendment License Conditions removed in Amendment 272 because they were identified as historical 272 because they were identified as historical Conditions will not be reinstated (i.e., original Conditions will not be reinstated (i.e., original License Conditions 2.C(4), 2.C(7), 2.H, and License Conditions 2.C(4) and 2.C(7) 2.H, and 2.I)." 2.I).

Reason:

License Conditions 2.H and 2.I associated with Palisades license renewal period will be reinstated to support HDI plans to pursue subsequent license renewal. See Item 5. This is consistent with subsequent license renewal industry precedent.

Item 3 - HDI PNP 2023-030 Enclosure, Evaluation of the Proposed Changes

Section affected:

3.2.1, Proposed Changes to the PNP Renewed Facility Operating Licen se (RFOL),

Page 8 of 97

Updated text

Add as 3rd paragraph: Prior to and since docketing of the 10 CFR 50.82(a)(1) certifications, there have been no non-conservative Technical Specifications (TS) entered in the Palisades corrective action process. Therefore, the process described by Regulatory Guide 1.239 (ML20294A510) is not needed for this license amendment.

Reason:

HDI PNP 2023-030 did not specifically document that there were no unresolved non-conservative PNP Technical Sp ecifications (TS) in the PNP corrective action process prior to transitioning to permanently defueled technical specifications. Therefore, this supplemental information to HDI PNP 2023-030 is provided to clarify that there were no non-conservative TS associated with PNP TS prior to or since docketing the 10 CFR 50.82(a)(1) certifications.

HDI PNP 2024-027 Enclosure Page 4 of 14

Item 4 - HDI PNP 2023-030 Enclosure, Evaluation of the Proposed Changes

Section affected:

3.2.1, Proposed Changes to the PNP Renewed Facility Operating License, Page 8 of 97

Updated text

Add as 4th paragraph: License Condition 2.E. for the PNP Physical Security Plan (PSP) is not proposed for modification by this power operations technical specification LAR and was not modified by the PDTS amendment. License condition 2.E remains unchanged from the pre-permanent cessation of power operations / permanent removal of fuel from the PNP reactor power operations technical specifications version. However, the Palisades Physical security plan has been revised since certification of permanent defueling and permanent removal of fuel from the reactor to reflect the reduced risks of a reactor in decommissioning. To support the transition of PNP back to a power operations plant the PSP will be updated, in accordance with 10 CFR 50.54(p), Conditions of licenses, to reflect the docketed version that was in effect prior to the 10 CFR 50.82(a)(1) certifications, PSP Revision 16 (Reference 16). Any PSP changes made during decommissioning that will be retained in the reinstated POLB PSP have been or will be evaluated in accordance with 50.54(p) against the PNP POLB to determine if NRC approval is required to retain the change prior to exiting the period of decommissioning.

The power operations PSP revisio n will be implemented coincident with the implementation of the power operations technical specification (POTS) amendment.

Add as a Reference on page 97 of 97:

16. Entergy Nuclear Operations, Inc. letter to U.S. Nuclear Regulatory Commission, Palisades Nuclear Plant Security Plan Revision 16 (U), dated June 11, 2014 (ADAMS Accession Number ML14163A564)

Reason:

License Condition 2.E describes the requirement to maintain a PSP and PSP element s. It does not reference the specific PNP documents that comprise the PSP. Therefore, this supplemental information to HDI PNP 2023-030 is provided to clarify the PSP document that will be the basis for the PNP power operations PSP.

HDI PNP 2024-027 Enclosure Page 5 of 14

Item 5 - HDI PNP 2023-030 Enclosure, Evaluation of the Proposed Changes

Section affected:

3.2.1, Proposed Changes to the PNP Renewed Facility Operating License, Page 14 of 97

Updated text

Add the below tables following License Condition 2.D

Reason:

Changes proposed to the RFOL are necessary t o reinstate the license conditions that were removed by license amendment 272 (Reference 8*) due to docketing the 10 CFR 50.82 decommissioning certifications (Reference 2*). Reinstatement of License Conditions 2.H and 2.I supports HDI plans to pursue subsequent license renewal. This is consistent with subsequent license renewal industry precedent.

Note that the reinstated License Conditions 2.H and 2.I list Entergy Nuclear Operations (ENO) as the entity responsible for the actions of the License Conditions. Since these License Conditions were deleted during the transition to decommissioning, HDI did not have responsibility for the actions of these License Conditions. Because they are now included in this LAR, the change of responsibility to the new owner is appropriate and the use of [Palisades Energy] as a placeholder for the change in ownership is applicable.

References 2 and 8 are listed in HDI PNP 2023-030 (the original LAR), Enclosure, Page 96 of 97.

License Condition 2.H Current License Condition 2.H Proposed License Condition 2.H

[Deleted] The Updated Safety Analysis Report supplement, as revised, submitted pursuant to 10 CFR 54.21(d), shall be included in the next scheduled update to the Updated Safety Analysis Report required by 10 CFR 50.71(e)(4) following the issuance of this renewed operating license. Until that update is complete, ENO [Palisa des Energy]

may make changes to the progra ms and activities described in the supplement without prior Commission approval, provided that ENO [Palisades Energy]

evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and HDI PNP 2024-027 Enclosure Page 6 of 14 otherwise complies with the requirements in

that section.

Basis This License Condition is proposed for reinstatement in its entirety to that which was in effect prior to the 10 CFR 50.82(a)(1) certifications to restore the PNP power operations RFOL. Upon recission of the 10 CFR 50.82(a)(1) certifications, as conditioned by the exemption to 10 CFR 50.82(a)(2), Reference 3, this license condition is reinstated to restore a one-time Updated Final Safety Analysis Report (UFSAR) supplement requirement associated with Palisades license renewal. This TS is reinstated as it existed in the previously approved TS prior to Amendment 272 (Reference 8), to reflect the power operation condition of the plant.

License Condition 2.I Current License Condition 2.I Proposed License Condition 2.I

[Deleted] The Updated Safety Analysis Report supplement, as revised, describes certain future activities to be completed prior to the period of extended operation. ENO

[Palisades Energy] shall complete these activities no later than March 24, 2011, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

Basis This License Condition is proposed for reinstatement in its entirety to that which was in effect prior to the 10 CFR 50.82(a)(1) certifications to restore the PNP power operations RFOL. Upon recission of the 10 CFR 50.82(a)(1) certifications, as conditioned by the exemption to 10 CFR 50.82(a)(2), Reference 3, this license condition is reinstated to restore a one-time requirement to complete license renewal commitments prior to entering the period of extended operation. This TS is reinstated as it existed in the previously approved TS prior to Amendment 272 (Reference 8), to reflect the power operation condition of the plant.

HDI PNP 2024-027 Enclosure Page 7 of 14

Item 6 - HDI PNP 2023-030 Enclosure, Evaluation of the Proposed Changes

Sections affected:

TS 1.2, Logical Connectors, Basis, Page 25 of 97 TS 1.3, Completion Times, Basis, Pages 25 of 97, 26 of 97 and 27 of 97 TS 1.4, Frequency, Basis, Page 29 of 97 TS Section 2.0, Safety Limits (SL), Basis, Page 30 of 97 LCO 3.0.1, Basis, Page 31 of 97 LCO 3.0.2, Basis, Page 31 of 97 LCO 3.0.3, Basis, Page 31 of 97 LCO 3.0.4, Basis, Page 32 of 97 LCO 3.0.5, Basis, Page 32 of 97 LCO 3.0.6, Basis, Page 33 of 97 LCO 3.0.7, Basis, Page 33 of 97 LCO 3.0.8, Basis, Page 34 of 97 LCO 3.0.9, Basis, Page 34 of 97 TS 5.6.2, Radiological Environmental Operating Report, Basis for Change, Page 82 of 97 TS 5.6.3, Radioactive Effluent Release Report, Basis for Change, page 82 of 97

Updated text

Add to each Basis: This TS is reinstated as it existed in the previously approved TS prior to Amendment 272 (Reference 8), to reflect the power operation condition of the plant.

Reason:

In HDI PNP 2023-030 Enclosure Section 2.1, Reason for Proposed Change, it explains that this LAR is needed to reinstate the PNP TS that were in effect just prior to the 10 CFR 50.82(a)(1) certifications to support returning PNP to a power operations licensing basis.

Proposed changes to the PNP TS are described in HDI PNP 2023-030 Enclosure Section 3.2.2, Proposed Changes to the Permanently Defueled Technical Specifications, (PDTS).

HDI PNP 2023-030 Enclosure Section 3.2.2 is arranged in a table format that summarizes the proposed changes to each affected PNP TS Section and provides a basis for the proposed changes.

The basis for the proposed changes typically states, this TS is proposed for reinstatement in its entirety to that which was in effect prior to the 10 CFR 50.82(a)(1) certification to restore the PNP power operations renewed facility operating license. In addition, the basis for most proposed changes typically clarifies that the TS is reinstated as it existed in the previously approved TS prior to Amendment 272 (PDTS), to reflect the power operation condition of the plant. Referencing Amendment 272 provides information that supports and clarifies the basis for the proposed changes to the PDTS.

HDI PNP 2024-027 Enclosure Page 8 of 14

Item 7 - HDI PNP 2023-030 Enclosure, Evaluation of the Proposed Changes

Sections affected:

TS Section 2.0, Safety Limits (SLs), description of change, Page 29 of 97

HDI PNP 2023-030 text Updated text

.SL violations in TS Section 2.2 are values .SL violations in TS Section 2.2 are values of various parameters for which automatic of various parameters for which automatic protective action is needed during normal protective action is needed during normal operations or anticipated transients to operations or anticipated transients to prevent exceeding an SL. prevent exceeding an SL. Proposed Safety Limits for reinstatement are listed below.

The corresponding TS Bases are also reinstated to reflect these changes.

Reason:

TS Section 2.0 has associated TS Bases that a re proposed for reinstatement. Therefore, a statement to that effect is appropriate.

Item 8 - HDI PNP 2023-030 Enclosure, Evaluation of the Proposed Changes

Section affected:

TS Section 3.0, Limiting Conditions for Operation (LCO), title for description of chang e, Page 30 of 97

HDI PNP 2023-030 text Updated text

"TS Section 3.0, Limiting Conditions for TS Section 3.0, Limiting Conditions for Operation (LCO)" Operation (LCO) Applicability

Reason:

The correct title of the TS section includes the word Applicability at the end. This corrects an editorial error.

HDI PNP 2024-027 Enclosure Page 9 of 14

Item 9 - HDI PNP 2023-030 Enclosure, Evaluation of the Proposed Changes

Section affected:

TS Section 3.1 Reactivity Control Systems, description of change, Page 37 of 97

HDI PNP 2023-030 text Updated text

."TS Section 3.1 is proposed for .TS Section 3.1 is proposed for reinstatement in its entirety.". reinstatement in its entirety , except for the SR 3.1.4.3 NOTE..

Reason:

SR 3.1.4.3 previously contained a NOTE that is no longer ap plicable and was removed as part of the PDTS amendment 272 (Reference 2). The proposed SR 3.1.4.3 listed in HDI PNP 2023-030 does not include reinstatement of the NOTE. This supplemental information is included to clarify that the proposed power operations technical specification SR 3.1.4.3 does not include the NOTE.

Item 10 - HDI PNP 2023-030 Enclosure, Evaluation of the Proposed Changes

Sections affected:

TS 3.7.14, Spent Fuel Pool (SFP) Water Level, Basis for Ch ange, Page 65 of 97 TS 3.7.15, Spent Fuel Pool (SFP) Boron Concentration, Basis for Chan ge, Page 67 of 97 TS 3.7.16, Spent Fuel Pool Storage, Basis for Change, Page 67 of 97 Add to the end of the first paragraph in each Basis:

HDI PNP 2023-030 text Updated text

.Amendment 272, to reflect the power .Amendment 272, to reflect the power operation condition of the plant.. operation condition of the plant. This TS is proposed for reinstatement in its entirety to that which was in effect prior to the 10 CFR 50.82(a)(1) certifications to restore the PNP power operations renewed facility operating license..

HDI PNP 2024-027 Enclosure Page 10 of 14

Reason:

In HDI PNP 2023-030 Enclosure Section 2.1, Reason for Proposed Change, it explains that this LAR is needed to reinstate the PNP TS that were in effect just prior to the 10 CFR 50.82(a)(1) certifications to support returning PNP to a power operations licensing basis.

Proposed changes to the PNP TS are described in HDI PNP 2023-030 Enclosure Section 3.2.2, Proposed Changes to the Permanently Defueled Technical Specifications (PDTS). The HDI PNP 2023-030 Enclosure Section 3.2.2 is arranged in a table format that summarizes the proposed changes to each affected PNP TS Section and provides a basis for the proposed changes.

The basis for the proposed changes typically states, is reinstated as it existed in the previously approved TS prior to Amendment 272 (PDTS), to reflect the power operation condition of the plant. In addition, the basis for most proposed changes typically clarifies that this TS is proposed for reinstatement in its entirety to that which was in effect prior to the 10 CFR 50.82(a)(1) certification to restore the PNP power operations renewed facility operating license. The supplemental information provided clarifies that TS 3.7.14, 3.7.15, and 3.7.16 are reinstated to that which was in effect prior to the 10 CFR 50.82(a)(1) certifications.

Item 11 - HDI PNP 2023-030 Enclosure Attachment 1, Proposed Changes (mark-up) to Palisades Plant Renewed Facility Operating License DPR-20, Appendix A Permanently Defueled Technical Speci fications, and Appendix B Environmental Protection Plan Pages

Section affected:

The following changes are associated with HDI PNP 2023-030 Enclosure Attachment 1, Proposed Changes (mark-up) to Palisades Plant Renewed Facility Operating License DPR-20, Appendix A Permanently Defueled Technical Spec ifications, and Appendix B Environmental Protection Plan Pages.

Attachment 1 to this enclosure (HDI PNP 2024-027) contains replacement pages that supersede those provided in HDI PNP 2023-030. The corresponding pages in the HDI PNP 2023-030 Attachment 1 (Reference 1) are to be replaced with the pages in Attachment 1 to this enclosure.

Proposed Changes (mark-up) to Palisades Plant Renewed Facility Operating License DPR-20, Appendix A Permanently Defueled Technical Spec ifications, and Appendix B Environmental Protection Plan Pages

Remove Pages Insert Pages Renewed Facility Operating Licen se (RFOL) Renewed Facility Operating License (RFOL)

Pages 7 and 8 Pages 7 and 8 HDI PNP 2024-027 Enclosure Page 11 of 14 RFOL Appendix A Technical Specifications for RFOL Appendix A Technical Specifications for TS 5.6.5 TS 5.6.5

Pages 5.0-17, 5.0-18, and 5.0-19 Pages 5.0-17, 5.0-18, and 5.0-19

Reason:

These changes provide marked up replacement pages for the added License Conditions 2.H and 2.I (see Item 5) and to consistently indent the title COLR (continued) with the indenting approach used in this section to improve reader clarity.

Item 12 - HDI PNP 2023-030 Enclosure Attachment 2, Page Change Instructions and Retyped Pages for the Palisades Plant Renewed Facility Operating License DPR-20, Appendix A Technical Specifications, and Appendix B Environmental Protection Plan

Section affected:

The following changes are associated with HDI PNP 2023-030 Enclosure Attachment 2, Page Change Instructions and Retyped Pages for the Palisades Plant Renewed Facility Operating License DPR-20, Appendix A Technical Spec ifications, and Appendix B Environmental Protection Plan.

Attachment 2 to this enclosure (HDI PNP 2024-027) contains replacement pages that supersede those provided in HDI PNP 2023-030. The corresponding pages in the HDI PNP 2023-030 Attachment 2 (Reference 1) are to be replaced with the pages in Attachment 2 to this enclosure.

Page Change Instructions and Retyped Pages for the Palisades Plant Renewed Facility Operating License DPR-20, Appendix A Technical Specifications, and Appendix B Environmental Protection Plan

Remove Pages Insert Pages Renewed Facility Operating Licen se (RFOL) Renewed Facility Operating License (RFOL)

Page 7 Page 7 Page 8 Page 8

RFOL Appendix A Technical Specifications RFOL Appendix A Technical Specifications Pages Pages 3.1.4-2 Missing (continued) 3.1.4-2 3.1.4-4 Missing (continued) 3.1.4-4 3.1.6-2 Missing (continued) 3.1.6-2 3.1.7-2 Missing (continued) 3.1.7-2 3.2.1-2 Missing (continued) 3.2.1-2 3.2.1-3 Missing (continued) 3.2.1-3 HDI PNP 2024-027 Enclosure Page 12 of 14

RFOL Appendix A Technical Specifications RFOL Appendix A Technical Specifications Pages (continued) Pages (continued) 3.2.1-4 Missing (continued) 3.2.1-4 3.3.1-2 Missing (continued) 3.3.1-2 3.3.1-3 Missing (continued) 3.3.1-3 3.3.1-4 Missing (continued) 3.3.1-4 3.3.1-5 Missing (continued) 3.3.1-5 3.3.2-2 Missing (continued) 3.3.2-2 3.3.3-2 Missing (continued) 3.3.3-2 3.3.8-3 Tbl 3.3.8-1 PARAMATER Spelling 3.3.8-3 3.3.4-2 Missing (continued) 3.3.4-2 3.3.5-2 Missing (continued) 3.3.5-2 3.3.7-2 Missing (continued) 3.3.7-2 3.4.3-2 Missing (continued) 3.4.3-2 3.4.5-2 Missing (continued) 3.4.5-2 3.4.5-3 Missing (continued) 3.4.5-3 3.4.6-2 ACTION indent incorrect placement 3.4.6-2 3.4.8-3 Missing (continued) 3.4.8-3 3.4.9-2 Missing (continued) 3.4.9-2 3.4.9-3 Missing (continued) 3.4.9-3 3.4.11-2 Missing (continued) 3.4.11-2 3.4.12-2 Missing (continued) 3.4.12-2 3.4.14-2 Missing (continued) 3.4.14-2 3.4.14-4 Missing (continued) 3.4.14-4 3.4.15-2 Missing (continued) 3.4.15-2 3.4.15-3 Missing (continued) 3.4.15-3 3.4.16-2 Missing (continued) 3.4.16-2 3.4.16-3 Missing (continued) 3.4.16-3 3.5.1-1 3.5.1 Hour is missing s 3.5.1-1 3.5.2-3 Missing (continued) 3.5.2-3 3.6.2-2 Missing (continued) 3.6.2-2 3.6.2-3 Missing (continued) 3.6.2-3 3.6.3-2 Missing (continued) 3.6.3-2 3.6.3-3 Missing (continued) 3.6.3-3 3.6.3-5 Missing (continued) 3.6.3-5 3.6.6-3 Missing (continued) 3.6.6-3 3.7.5-2 Missing (continued) 3.7.5-2 3.7.10-2 Missing (continued) 3.7.10-2 3.7.10-3 E. Logic Connector Incorrect 3.7.10-3 3.7.11-2 D. Logic Connectors Incorrect 3.7.11-2 3.7.11-3 Missing (continued) 3.7.11-3 3.8.1-2 Missing (continued) 3.8.1-2 3.8.1-3 Missing (continued) 3.8.1-3 3.8.1-4 Missing (continued) 3.8.1-4 3.8.1-5 Missing (continued) 3.8.1-5

HDI PNP 2024-027 Enclosure Page 13 of 14

RFOL Appendix A Technical Specifications RFOL Appendix A Technical Specifications Pages (continued) Pages (continued) 3.8.1-6 Missing (continued) 3.8.1-6 3.8.1-7 Missing (continued) 3.8.1-7 3.8.1-8 Missing (continued) 3.8.1-8 3.8.2-2 Missing (continued) 3.8.2-2 3.8.3-2 Missing (continued) 3.8.3-2 3.8.4-2 Missing (continued) 3.8.4-2 3.8.4-3 Missing (continued) 3.8.4-3 3.8.4-4 Missing (continued) 3.8.4-4 3.8.5-2 Missing (continued) 3.8.5-2 3.8.6-2 Missing (continued) 3.8.6-2 3.8.6-3 Missing (continued) 3.8.6-3 3.8.9-2 Missing (continued) 3.8.9-2 3.8.10-2 Missing (continued) 3.8.10-2 3.9.4-2 Missing (continued) 3.9.4-2 3.9.5-2 Missing (continued) 3.9.5-2 5.0-9 Am 271 in footer incorrect 5.0-9 5.0-12 5.5.8 d. Indent incorrect 5.0-12 5.0.13 5.5.9 Extra Space Secondary 5.0.13 5.0-15 Am 271 in footer incorrect 5.0-15 5.0-16 Am 271 in footer incorrect 5.0-16 5.0-17 5.5.14 Extra Space Containment 5.0-17 5.0-18 5.5.14 d. Para. formatting Incorrect 5.0-18 5.0-20 5.5.16 Extra Space Control 5.0-20 5.0-21 5.5.17 Extra Space Surveillance 5.0-21 5.0-22 5.6.5 Extra Space CORE 5.0-22 5.0-23 5.6.5 COLR Indent Incorrect 5.0-23 5.0-24 5.6.5 COLR Indent Incorrect 5.0-24 5.0-25 5.6.5 COLR Indent Incorrect 5.0-25 5.0-26 5.6.8 Extra Space Steam 5.0-26

Reason:

These changes are being provided to add License Conditions 2.H and 2.I (see Item 5),

correct editorial errors, and improve formatting consistency.

Additionally, the ACTIONS tables and SURVEILLANCE REQUIREMENTS tables are sometimes continued on the next page. The ACTIONS (continued) or "SURVEILLANCE REQUIREMENTS (continued)" headings have been added, consistent with NUREG-1432 Standard Technical Specifications Combustion Engineering Plants, Revision 5.0, Volume 1 guidance.

An abbreviated reason for the change to each page is provided in column one of the above table for clarity as to why the change is included in this LAR Supplement.

HDI PNP 2024-027 Enclosure Page 14 of 14

Item 13 - HDI PNP 2023-030 Enclosure, Attachment 3

Section affected:

The following changes are associated with HDI PNP 2023-030 Enclosure Attachment 3, Proposed Technical Specifications Bases Changes (for information only ).

Attachment 3 to this enclosure (HDI PNP 2024-027) contains replacement pages that supersede those provided in HDI PNP 2023-030. The corresponding pages in the HDI PNP 2023-030 Attachment 3 (Reference 1) are to be replaced with the pages in Attachment 3 to this enclosure.

Proposed Technical Specifications Bases Changes (for information only)

Remove Pages Insert Pages Technical Specification Bases Technical Specification Bases

Pages Pages B 3.0-1 B 3.0-1 B 3.0-2 B 3.0-2 B 3.0-3 B 3.0-3 B 3.0-4 B 3.0-4 B 3.0-5 B 3.0-5 B 3.1.3-3 B 3.1.3-3 B 3.7.16-1 B 3.7.16-1

Reason:

These changes are being provided t o improve reader clarity, correct editorial errors, and add information to TS Bases 3.7.16 to conform to the TS Basis that existed prior to the 10 CFR 50.82(a)(1) certifications.

References

1. Holtec Decommissioning International, LLC letter to U.S. Nuclear Regulatory Commission (HDI PNP 2023-030), "License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations," dated December 14, 2023 (ADAMS Accession No. ML23348A148)

2. U. S. Nuclear Regulatory Commission letter to Entergy Nuclear Operations, Inc., P alisades Nuclear Plant - Issuance of Amend ment No. 272 re: Permanently Defueled Technical Specifications, dated May 13, 2022 (ADAMS Accession No. ML22039A198)

HDI PNP 2024-027

Enclosure Attachment 1

Updated Proposed Changes (mark-up) to Palisades Plant

Renewed Facility Operating License DPR-20,

Appendix A Permanently Defueled Technical Specifications

Only replacement pages are provided. Please replace the affected pages from HDI PNP 2023-030 (Reference 1) with the attached pages.

Note, references to "HDI" are replaced by bracketed Palisades Energy, LLC, or Palisades Energy (e.g. [Palisades Energy]) to reflect the change in operating authority per license transfer application conforming amendments.

5 pages follow 7

(8) Amendment 257 authorizes the implementation of 10 CFR 50.61a in lieu of 10 CFR 50.61.[deleted]

D. The facility has been granted certain exemptions from Appendix J to 10 CFR Part 50, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors.

This section contains leakage test requirements, scheduled and acceptance criteria for tests of the leak-tight integrity of the primary reactor containment and systems and components which penetrate the containment. These exemptions were granted in a letter dated December 6, 1989.

These exemptions granted pursuant to 10 CFR 50.12, are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.[deleted]

E. HDI[Palisades Energy] shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Palisades Nuclear Plant Physical Security Plan.

HDI[Palisades Energy] shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Palisades CSP was approved by License Amendment No. 243 as supplemented by changes approved by License Amendment Nos. 248, 253, 259, and 264.

F. [deleted]

G. Holtec Palisades and HDI[Palisades Energy] shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

H. The Updated Safety Analysis Report supplement, as revised, subm itted pursuant to 10 CFR 54.21(d), shall be included in the next scheduled update to the Updated Safety Analysis Report required by 10 CFR 50.71(e)(4) following the issuance of this renewed operating license. Until that update is complete, ENO [Palisades Energy] may make changes to the programs and activities described in the supplement without prior Commission approval, provided that ENO [Palisades Energy] evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.[deleted]

Renewed License No. DPR-20 Amendment No. XXX 8

I. The Updated Safety Analysis Report supplement, as revised, describes certain future activities to be completed prior to the period of extended operation. ENO [Palisades Energy] shall complete these activities no later than March 24, 2011, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.[deleted]

J. All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal scheduled, including spare capsules, must be approved by the NRC prior to implementation. All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the NRC, as required by 10 CFR Part 50, Appendix H.[deleted]

K. This license is effective as of the date of issuance and shall expire at midnight March 24, 2031until the Commission notifies the licensee in writing that the license is terminated.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

J. E. Dyer, Director Office of Nuclear Reactor Regulation

Attachments:

1. Appendix A - Permanently Defueled Technical Specifications

2. Appendix B - Environmental Protection Plan

Date of Issuance: January 17, 2007

Renewed License No. DPR-20 Amendment No. XXX 5.6 Reporting Requirements

5.6.5 COLR (Continued)

b. The analytical methods used to determine the core operating limits shall be those approved by the NRC, specifically those described in the latest approved revision of the following documents:

1. EMF-96-029(P)(A) Volumes 1 and 2, Reactor Analysis System for PWRs, Siemens Power Corporation.

(LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

2. ANF-84-73 Appendix B (P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation. (Bases report not approved) (LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

3. XN-NF-82-21(P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company.

(LCOs 3.2.1, 3.2.2, & 3.2.4)

4. EMF-84-093(P)(A), Steam Line Break Methodology for PWRs, Siemens Power Corporation.

(LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

5. XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company. (Bases document not approved)

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

6. EMF-2310 (P)(A), Revision 0, Framatome ANP, Inc., May 2001, SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

7. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, & 3.2.2)

8. ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events,"

Advanced Nuclear Fuels Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

9. EMF-92-153(P)(A) and Supplement 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel,"

Siemens Power Corporation. (LCOs 3.2.1, 3.2.2, & 3.2.4)

Palisades Nuclear Plant 5.0-17 Amendment No. 261, 272 5.6 Reporting Requirements

5.6.5 COLR (Continued)

10. XN-NF-621(P)(A), Exxon Nuclear DNB Correlation for PWR Fuel Designs, Exxon Nuclear Company. (LCOs 3.2.1, 3.2.2, & 3.2.4)

11. XN-NF-82-06(P)(A) and Supplements 2, 4, and 5, Qualification of Exxon Nuclear Fuel for Extended Burnup, Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

12. ANF-88-133(P)(A) and Supplement 1, Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWD/MTU, Advanced Nuclear Fuels Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

13. XN-NF-85-92(P)(A), Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results, Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

14. EMF-92-116(P)(A), Generic Mechanical Design Criteria for PWR Fuel Designs, Siemens Power Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

15. EMF-2087(P)(A), SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications, Siemens Power Corporation.

(LCOs 3.1.6, 3.2.1, & 3.2.2)

16. ANF-87-150 Volume 2, Palisades Modified Reactor Protection System Report: Analysis of Chapter 15 Events, Advanced Nuclear Fuels Corporation. [Approved for use in the Palisades design during the NRC review of license Amendment 118, November 15, 1988] (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.4.1)

17. EMF-1961(P)(A), Revision 0, Siemens Power Corporation, July 2000, Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors. (LCOs 3.1.6, 3.2.1, 3.2.2, 3.2.4, &

3.4.1)

18. EMF-2328 (P)(A), Revision 0, Framatome ANP, Inc., March 2001, PWR Small Break LOCA Evaluation Model, S-RELAP5 Based.

(LCOs 3.1.6, 3.2.1, & 3.2.2)

19. BAW-2489P, Revised Fuel Assembly Growth Correlation for Palisades. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

Palisades Nuclear Plant 5.0-18 Amendment No. 261, 272 5.6 Reporting Requirements

5.6.5 COLR (Continued)

20. EMF-2103(P)(A), Realistic Large Break LOCA Methodology for Pressurized Water Reactors. (LCOs 3.1.6, 3.2.1, & 3.2.2)

21. BAW-10240(P)-A, Incorporation of M5 Properties in Framatome ANP Approved Methods. (LCOs 3.1.6, 3.2.1, 3.2.2, 3.2.4, & 3.4.1)

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any mid cycle revisions or supplements, shall be provided, upon issuance for each reload cycle, to the NRC.

5.6.6 (Deleted) Post Accident Monitoring Report

When a report is required by LCO 3.3.7, "Post Accident Monitoring Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to OPERABLE status.

5.6.7 (Deleted) Containment Structural Integrity Surveillance Report

Reports shall be submitted to the NRC covering Prestressing, Anchorage, and Dome Delamination tests within 90 days after completion of the tests.

5.6.8 (Deleted) Steam Generator Tube Inspection Report

A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.8, Steam Generator (SG) Program. The report shall include:

a. The scope of inspections performed on each SG,

b. Active degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism,

Palisades Nuclear Plant 5.0-19 Amendment No. 261, 272 HDI PNP 2024-027

Enclosure Attachment 2

Updated Retyped Pages for the Palisades Plant

Renewed Facility License DPR-20,

Appendix A Technical Specifications

Only replacement pages are provided. Please replace the affected pages from (HDI PNP 2023-030) (Reference 1) with the attached pages.

Note, references to "HDI" are replaced by bracketed Palisades Energy, LLC, or Palisades Energy (e.g. [Palisades Energy]) to reflect the change in operating authority per license transfer application conforming amendments.

80 pages follow (7) [deleted]

(8) Amendment 257 authorizes the implementation of 10 CFR 50.61a in lieu of 10 CFR 50.61.

D. The facility has been granted certain exemptions from Appendix J to 10 CFR Part 50, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors.

This section contains leakage test requirements, scheduled and acceptance criteria for tests of the leak-tight integrity of the primary reactor containment and systems and components which penetrate the containment. These exemptions were granted in a letter dated December 6, 1989.

These exemptions granted pursuant to 10 CFR 50.12, are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

E. [Palisades Energy] shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Palisades Nuclear Plant Physical Security Plan.

[Palisades Energy] shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Palisades CSP was approved by License Amendment No. 243 as supplemented by changes approved by License Amendment Nos. 248, 253, 259, and 264.

F. [deleted]

G. Holtec Palisades and [Palisades Energy] shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

Renewed License No. DPR-20 Amendment No. 272, 273, XXX H. The Updated Safety Analysis Report supplement, as revised, submitted pursuant to 10 CFR 54.21(d), shall be included in the next scheduled update to the Updated Safety Analysis Report required by 10 CFR 50.71(e)(4) following the issuance of this renewed operating license. Until that update is complete, [Palisades Energy] may make changes to the programs and activities described in the supplement without prior Commission approval, provided that [Palisades Energy] evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

I. The Updated Safety Analysis Report supplement, as revised, describes certain future activities to be completed prior to the period of extended operation. [Palisades Energy]

shall complete these activities no later than March 24, 2011, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

J. All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal scheduled, including spare capsules, must be approved by the NRC prior to implementation. All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the NRC, as required by 10 CFR Part 50, Appendix H.

K. This license is effective as of the date of issuance and shall expire at midnight March 24, 2031.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

J. E. Dyer, Director Office of Nuclear Reactor Regulation

Attachments:

1. Appendix A -Technical Specifications

2. Appendix B - Environmental Protection Plan

Date of Issuance: January 17, 2007

Renewed License No. DPR-20 Amendment No. 272, 273, XXX Control Rod Alignment 3.1.4

ACTIONSFRQWLQXHG

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

OR

One or more control rods inoperable for reasons other than Condition D.

OR

Two or more control rods misaligned by > 8 inches.

OR

Both rod position indication channels inoper able for one or more control rods.

Palisades Nuclear Plant 3.1.4-2 Amendment No. XXX Control Rod Alignment 3.1.4

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.1.4.6 Verify each full-length control rod drop time is Prior to reactor d 2.5 seconds. criticality, after each reinstallation of the reactor head

Palisades Nuclear Plant 3.1.4-4 Amendment No. XXX Regulating Rod Group Position Limits 3.1.6

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

B. Regulating rod groups not B.1 Restore regulating rod 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months within sequence or overlap groups to within limits. appropriate sequence and overlap limits.

C. PDIL or CROOS alarm C.1 Perform SR 3.1.6.1 Once within circuit inoperable. (group position 15 minutes following verification). any rod motion

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.1.6.1 Verify each regulating rod group is within its In accordance with withdrawal sequence, overlap, and insertion limits. the Surveillance Frequency Control Program

SR 3.1.6.2 Verify PDIL alarm circuit is OPERABLE. In accordance with the Surveillance Frequency Control Program

SR 3.1.6.3 Verify CROOS alarm circuit is OPERABLE. In accordance with the Surveillance Frequency Control Program

Palisades Nuclear Plant 3.1.6-2 Amendment No. .XXX Special Test Exceptions (STE) 3.1.7

ACTIONS FRQWLQXHG CONDITION REQUIRED ACTION COMPLETION TIME

D. Required Action and D.1 Suspend PHYSICS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion TESTS.

Time not met.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.1.7.1 Verify THERMAL POWER is d 2% RTP. In accordance with the Surveillance Frequency Control Program

SR 3.1.7.2 Verify Tave is t 500q F. In accordance with the Surveillance Frequency Control Program

SR 3.1.7.3 Verify t 1% shutdown reactivity is available for trip In accordance with insertion. the Surveillance Frequency Control Program

Palisades Nuclear Plant 3.1.7-2 Amendment No. XXX LHR 3.2.1

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

B. Incore Alarm and Excore B.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Monitoring Systems POWER to 85% RTP.

inoperable for monitoring LHR. AND

B.2 Verify LHR is within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months limits using manual incore readings. AND

Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thereafter

C. Required Action and C.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.2.1.1 -------------------------------NOTE---------------------------

Only required to be met when the Incore Alarm System is being used to monitor LHR.

Verify LHR is within the limits specified in the In accordance with COLR. the Surveillance Frequency Control Program

Palisades Nuc lear Plant 3.2.1-2 Amendment No. XXX LHR 3.2.1

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.2.1.2 ------------------------------NOTE----------------------------

Only required to be met when the Incore Alarm System is being used to monitor LHR.

Adjust incore alarm setpoints based on a Prior to operation measured power distribution. > 50% RTP after each fuel loading

AND

In accordance with the Surveillance Frequency Control Program

SR 3.2.1.3 -------------------------------NOTE---------------------------

Only required to be met when the Excore Monitoring System is being used to monitor LHR.

Verify measured ASI has been within 0.05 of Prior to each initial target ASI for last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . use of Excore Monitoring System to monitor LHR

SR 3.2.1.4 -------------------------------NOTE---------------------------

Only required to be met when the Excore Monitoring System is being used to monitor LHR.

Verify THERMAL POWER is less than the APL. In accordance with the Surveillance Frequency Control Program

Palisades Nuclear Plant 3.2.1-3 Amendment No. XXX LHR 3.2.1

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.2.1.5 -------------------------------NOTE---------------------------

Only required to be met when the Excore Monitoring System is being used to monitor LHR.

Verify measured ASI is within 0.05 of target ASI. In accordance with the Surveillance Frequency Control Program

SR 3.2.1.6 -------------------------------NOTE---------------------------

Only required to be met when the Excore Monitoring System is being used to monitor LHR.

Verify Tq d 0.03. In accordance with the Surveillance Frequency Control Program

Palisades Nuclear Plant 3.2.1-4 Amendment No. XXX RPS Instrumentation 3.3.1

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

C. One Loss of Load trip unit C.1 Restore trip unit and Prior to increasing or associated instrument associated instrument THERMAL POWER channel inoperable. channel to OPERABLE to tt 17% RTP status. following entry into MODE 3

D. One or more ZPM Bypass D.1 Remove the affected Immediately Removal channels ZPM Bypasses.

inoperable.

OR

D.2 Declare affected trip Immediately units inoperable.

E. -------------NOTE-------------- E.1 Place one trip unit in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Not applicable to ZPM Bypass Removal AND Function.

-----------------NOTE-------------------

One or more Functions Not applicable to High Startup with two RPS trip units or Rate or Loss of Load Functions.

associated instrument ---------------------------------------------

channels inoperable. E.2 Restore one trip unit and 7 days associated instrument channel to OPERABLE status.

F. Two power range F.1 Restrict THERMAL s channels inoperable. POWER to d

Palisades Nuclear Plant 3.3.1-2 Amendment No. XXX RPS Instrumentation 3.3.1

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND

OR G.2.1 Verify no more than one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Control room ambient air full-length control rod is temperature > 90 oF. capable of being withdrawn.

OR

G.2.2 Verify PCS boron 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months concentration is at REFUELING BORON CONCENTRATION.

SURVEILLANCE REQUIREMENTS

NOTE----------------------------------------------------------

Refer to Table 3.3.1-1 to determine which SR shall be performed for each Function.

SURVEILLANCE FREQUENCY

SR 3.3.1.1 Perform a CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program

SR 3.3.1.2 Verify control room temperature is dd 90qF. In accorth the Survll equency Contro ogram

Palisades Nuclear Plant 3.3.1-3 Amendment No. XXX RPS Instrumentation 3.3.1

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.3.1.3 -----------------------------NOTE-----------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is tt 15% RTP.

Perform calibration (heat balance only) and adjust In accorth the power range excore and T power channels to the Survll agree with calorimetric calculation if the absolute equency Contro difference is t 1.5% ogram

SR 3 -NOTE-Not requirorforl 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months se THERMALER is t 25% RTP.

Caliatthe power range excore channelsng In accorth tnre detes. the Survll equency Contro ogram

SR 3.1.5 Perform aUONA and In accorth ve eheal Mainonironsn. the Survll equency Contro ogram

SR 3.1.6 Perform aibratick of the power range In accorth excores with a test signal. the Survll equency Contro ogram

SR 3.1.7 Perform aUONAL TEST of High hin artute ior toro tup

Palisades Nuclear Plant 3.3.1-4 Amendment No. XXX RPS Instrumentation 3.3.1

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.3.1.8 -----------------------------NOTE-----------------------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform a CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program

Palisades Nuclear Plant 3.3.1-5 Amendment No. XXX RPS Logic and Trip Initiation 3.3.2

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND

OR E.2.1 Verify no more than one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months One or more Functions full-length control rod is with two or more Manual capable of being Trip, Matrix Logic or Trip withdrawn.

Initiation Logic channels OR inoperable for reasons other than Condition D. E.2.2 Verify PCS boron 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

concentration is at REFUELING BORON CONCENTRATION.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.3.2.1 Perform a CHANNEL FUNCTIONAL TEST on In accordance with each RPS Matrix Logic channel and each RPS the Surveillance Trip Initiation Logic channel. Frequency Control Program

SR 3.3.2.2 Perform a CHANNEL FUNCTIONAL TEST on Once within 7 days each RPS Manual Trip channel. prior to each reactor startup

Palisades Nuclear Plant 3.3.2-2 Amendment No. XXX ESF Instrumentation 3.3.3

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

C. One RAS bistable or C.1 Bypass affected 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated instrument bistable.

channel inoperable.

AND

C.2 Restore bistable and 7 days associated instrument channel to OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met for Functions 1, 2, 3, AND 4, or 7.

D.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met for Functions 5 or 6. AND

E.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

Palisades Nuclear Plant 3.3.3-2 Amendment No. XXX ESF Logic and Manual Initiation 3.3.4

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

C. One or more Functions with C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months two Manual Initiation, or Actuation Logic channels AND inoperable for Functions 5 or 6. C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

OR

Required Action and associated Completion Time of Condition A not met for Functions 5 or 6.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.3.4.1 Perform functional test of each SIS actuation In accordance with channel normal and standby power functions. the Surveillance Frequency Control Program

SR 3.3.4.2 Perform a CHANNEL FUNCTIONAL TEST of each In accordance with AFAS actuation logic channel. the Surveillance Frequency Control Program

SR 3.3.4.3 Perform a CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program

Palisades Nuclear Plant 3.3.4-2 Amendment No. XXX DG - UV Start 3.3.5

SURVEILLANCE REQUIREMENTS FRQWLQXHG SURVEILLANCE FREQUENCY

SR 3.3.5.2 Perform CHANNEL CALIBRATION on each Loss In accordance with of Voltage and Degraded Voltage channel with the Surveillance setpoints as follows: Frequency Control Program

a. 'HJUDGHG9ROWDJH)XQFWLRQ 2187 V and 2264 V

1. Time delay (degraded voltage sensing relay) 0.5 seconds and 0.8 seconds; and

2. Time delay (degraded voltage sensing relay plus time delay relay): 6.2 VHFRQGVDQG 7.1 seconds.

b. /RVVRI9ROWDJH)XQFWLRQ 1780 V and 1940 V

7LPHGHOD\\ 5.45 seconds and 8.15 seconds at 1400 V.

Palisades Nuclear Plant 3.3.5-2 Amendment No. XXX PAM Instrumentation 3.3.7

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

D. (Not Used)

E. Required Action and E.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C not Table 3.3.7-1 for the met. channel.

F. As required by Required F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action E.1 and referenced in Table 3.3.7-1. AND

F.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months

G. As required by Required G.1 Initiate action in Immediately Action E.1 and referenced accordance with in Table 3.3.7-1. Specification 5.6.6.

Palisades Nuclear Plant 3.3.7-2 Amendment No. XXX Alternate Shutdown System 3.3.8

Table 3.3.8-1 (page 1 of 1)

Alternate Shutdown System Instrumentation and Controls FUNCTION, INSTRUMENT REQUIRED OR CONTROL PARAMETER CHANNELS

1. Source Range Neutron Flux 1

2. Pressurizer Pressure 1

3. Pressurizer Level 1

4. Primary Coolant System (PCS) #1 Hot Leg Temperature 1

5. PCS #2 Hot Leg Temperature 1

6. PCS #1 Cold Leg Temperature 1

7. PCS #2 Cold Leg Temperature 1

8. Steam Generator (SG) A Pressure 1

9. SG B Pressure 1

10. SG A Wide Range Level 1

11. SG B Wide Range Level 1

12. Safety Injection Refueling Water (SIRW) Tank Level 1

13. Auxiliary Feedwater (AFW) Flow Indication to SG A 1

14. AFW Flow Indication to SG B 1

15. AFW Low Suction Pressure Alarm (P-8B) 1

16. AFW Pump P-8B Steam Supply Valve Control 1

17. AFW Flow Control to SG A 1

18. AFW Flow Control to SG B 1

Palisades Nuclear Plant 3.3.8-3 Amendment No. XXX PCS P/T Limits 3.4.3

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

C. --------------NOTE-------------C.1 Initiate action to restore Immediately Required Action C.2 shall parameter(s) to within be completed whenever limits.

this Condition is entered.

AND

Requirements of LCO not C.2 Determine PCS is Prior to entering met any time in other than acceptable for continued MODE 4 MODE 1, 2, 3, or 4. operation.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.4.3.1 -------------------------------NOTE---------------------------

Only required to be performed during PCS heatup and cooldown operations.

Verify PCS pressure, PCS temperature, and PCS In accordance with heatup and cooldown rates are within the limits of the Surveillance Figure 3.4.3-1 and Figure 3.4.3-2. Frequency Control Program

Palisades Nuclear Plant 3.4.3-2 Amendment No. XXX PCS Loops - MODE 3 3.4.5

ACTIONS FRQWLQXHG CONDITION REQUIRED ACTION COMPLETION TIME

B. Required Action and B.1 Be in MODE 4. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months associated Completion Time of Condition A not met.

C. No PCS loop OPERABLE. C.1 Suspend all operations Immediately involving a reduction of OR PCS boron concentration.

No PCS loop in operation.

AND

C.2 Initiate action to restore Immediately one PCS loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.4.5.1 Verify required PCS loop is in operation. In accordance with the Surveillance Frequency Control Program

SR 3.4.5.2 Verify secondary side water level in each steam In accordance with generator t -84%. the Surveillance Frequency Control Program

Palisades Nuclear Plant 3.4.5-2 Amendment No. XXX PCS Loops - MODE 3 3.4.5

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.4.5.3 Verify correct breaker alignment and indicated In accordance with power available to the required primary coolant the Surveillance pump that is not in operation. Frequency Control Program

Palisades Nuclear Plant 3.4.5-3 Amendment No. XXX PCS Loops - MODE 4 3.4.6

ACTIONS

CONDITION REQUIRED ACTION COMPLE TION TIM E

A. One PCS loop inoperable. A.1 Initiate action to restore Immediately a second PCS loop or AND one SDC train to OPERABLE status.

Two SDC trains inoperable.

B. One SDC train inoperable. B.1 Be in MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

AND

Two PCS loops inoperable.

C. No PCS loops or SDC C.1 Suspend all operations Immediately trains OPERABLE. involving reduction of PCS boron OR concentration.

No PCS loop in operation AND with SDC flow through the reactor core not within C.2.1 Initiate action to restore Immediately limits. one PCS loop to OPERABLE status and operation.

OR

C.2.2 Initiate action to restore Immediately one SDC train to OPERABLE status and operation with t 2810 gpm flow through the reactor core.

Palisades Nuclear Plant 3.4.6-2 Amendment No. XXX PCS Loops - MODE 5, Loops Not Filled SURVEILLANCE REQUIREMENTS FRQWLQXHG 3.4.8

SURVEILLANCE FREQUENCY

SR 3.4.8.2 -------------------------------NOTE---------------------------

Only required to be met when complying with LCO 3.4.8.b.

Verify one SDC train is in operation with In accordance with t 650 gpm flow through the reactor core. the Surveillance Frequency Control Program

SR 3.4.8.3 --------------------------------NOTE--------------------------

Only required to be met when complying with LCO 3.4.8.b.

Verify two of three charging pumps are incapable In accordance with of reducing the boron concentration in the PCS the Surveillance below the minimum value necessary to maintain Frequency Control the required SHUTDOWN MARGIN. Program

SR 3.4.8.4 Verify correct breaker alignment and indicated In accordance with power available to the SDC pump that is not in the Surveillance operation. Frequency Control Program

Palisades Nuclear Plant 3.4.8-3 Amendment No. XXX Pressurizer 3.4.9

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

B. < 375 kW pressurizerB.1 Restore required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months heater capacity available pressurizer heaters to from electrical bus 1D, or OPERABLE status.

electrical bus 1E,

OR

Required pressurizer heater capacity from electrical bus 1E not capable of being powered from an emergency power supply.

C. ------------NOTE---------------C.1 Restore at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Not applicable when the electrical bus 1D or remaining electrical bus 1D electrical bus 1E or electrical bus 1E required pressurizer required pressurizer heaters to OPERABLE heaters intentionally made status.

inoperable.

< 375 kW pressurizer heater capacity available from electrical bus 1D, and electrical bus 1E,

OR

< 375 kW pressurizer heater capacity available from electrical bus 1D, and required pressurizer heater capacity from electrical bus 1E not capable of being powered from an emergency power supply.

Palisades Nuclear Plant 3.4.9-2 Amendment No. XXX Pressurizer 3.4.9

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition B or C AND not met.

D.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.4.9.1 -------------------------------NOTE---------------------------

Not required to be met until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after establishing a bubble in the pressurizer and the pressurizer water level has been lowered to within its normal operating band.

Verify pressurizer water level is < 62.8%. In accordance with the Surveillance Frequency Control Program

SR 3.4.9.2 Verify the capacity of pressurizer heaters from In accordance with electrical bus 1D, and electrical bus 1E is the Surveillance 375 kW. Frequency Control Program

SR 3.4.9.3 Verify the required pressurizer heater capacity In accordance with from electrical bus 1E is capable of being powered the Surveillance from an emergency power supply. Frequency Control Program

Palisades Nuclear Plant 3.4.9-3 Amendment No. XXX Pressurizer PORVs 3.4.11

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

C. Two PORVs inoperable. C.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months valves.

AND

C.2 Restore at least one 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months PORV to OPERABLE status.

D. Two block valves D.1 Place associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. PORVs in manual control.

AND

D.2 Restore at least one 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months block valve to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Palisades Nuclear Plant 3.4.11-2 Amendment No. XXX LTOP System 3.4.12

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

B. One required PORV B.1 Restore required PORV 7 days inoperable and pressurizer to OPERABLE status.

water level 57%.

C. One required PORV C.1 Restore required PORV 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable and pressurizer to OPERABLE status.

water level > 57%.

D. Two required PORVs D.1 Depressurize PCS and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable. establish PCS vent capable of relieving OR 167 gpm at a PCS pressure of 315 psia.

Required Action and associated Completion Time not met.

OR

LTOP System inoperable for any reason other than Condition A, B, or C.

Palisades Nuclear Plant 3.4.12-2 Amendment No. XXX PCS PIV Leakage 3.4.14

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

A. (continued) A.1 Isolate the high pressure 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

AND

A.2 Restore PCS PIV 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

C. One or both SDC suction C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valve interlocks penetration by use of inoperable. one closed deactivated valve.

Palisades Nuclear Plant 3.4.14-2 Amendment No. XXX PCS PIV Leakage 3.4.14

SURVEILLANCE REQUIREMENTSFRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.4.14.3 -------------------------------NOTE----------------------------

Only required to be performed in MODES 1 and 2.

Prior to entering Verify each of the four Low Pressure Safety MODE 2 after each Injection (LPSI) check valves are closed. use of the LPSI check valves for SDC

Palisades Nuclear Plant 3.4.14-4 Amendment No. XXX PCS Leakage Detection Instrumentation 3.4.15

SURVEILLANCE REQUIREMENTSFRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.4.15.6 Perform CHANNEL CALIBRATION of the required In accordance with containment atmosphere gaseous activity monitor. the Surveillance Frequency Control Program

SR 3.4.15.7 Perform CHANNEL CALIBRATION of the required In accordance with containment atmosphere humidity monitor. the Surveillance Frequency Control Program

Palisades Nuclear Plant 3.4.15-3 Amendment No. XXX PCS Specific Activity 3.4.16 3.4 PRIMARY COOLANT SYSTEM (PCS)

3.4.16 PCS Specific Activity

LCO 3.4.16 The specific activity of the primary coolant shall be within limits.

APPLICABILITY: MODES 1 and 2, MODE 3 with PCS average temperature (Tave) 500°F.

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

A. DOSE EQUIVALENT I-131 -----------------NOTE-------------------

>1.0 Ci/gm. LCO 3.0.4.c is applicable.

A.1 Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT I-131

< 40 Ci/gm.

AND

A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT I-131 to within limit.

Palisades Nuclear Plant 3.4.16-1 Amendment No. XXX PCS Specific Activity 3.4.16

ACTIONS FRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

B. Required Action and B.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Tave < 500qF.

Time of Condition A not met.

OR

DOSE EQUIVALENT I-131 t 40 Ci/gm.

OR

Gross specific activity of the primary coolant not within limit.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.4.16.1 Verify primary coolant gross specific activity In accordance with d 100/ Ci/gm. the Surveillance Frequency Control Program

Palisades Nuclear Plant 3.4.16-2 Amendment No. XXX PCS Specific Activity 3.4.16

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.4.16.2 -------------------------------NOTE---------------------------

Only required to be performed in MODE 1.

In accordance with Verify primary coolant DOSE EQUIVALENT I-131 the Surveillance specific activity d 1.0 Ci/gm. Frequency Control Program

AND

Once between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after THERMAL POWER change of t 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period

SR 3.4.16.3 -------------------------------NOTE---------------------------

Not required to be performed until 31 days after a minimum of 2 EFPD and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for t 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Determine IURPDsample taken in MODE 1 after In accordance with a minimum of 2 EFPD and 20 days of MODE 1 the Surveillance operation have elapsed since the reactor was last Frequency Control subcritical for t 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . Program

Palisades Nuclear Plant 3.4.16-3 Amendment No. XXX SITs 3.5.1

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

3.5.1 Safety Injection Tanks (SITs)

LCO 3.5.1 Four SITs shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. One SIT inoperable due to A.1 Restore SIT to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months boron concentration not OPERABLE status.

within limits.

OR

One SIT inoperable due to the inability to verify level or pressure.

B. One SIT inoperable for B.1 Restore SIT to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months reasons other than OPERABLE status.

Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B not met.

D. Two or more SITs D.1 Enter LCO 3.0.3. Immediately inoperable.

Palisades Nuclear Plant 3.5.1-1 Amendment No. XXX ECCS - Operating 3.5.2

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.5.2.6 Verify each ECCS pump starts automatically on an In accordance with actual or simulated actuation signal. the Surveillance Frequency Control Program

SR 3.5.2.7 Verify each LPSI pump stops on an actual or In accordance with simulated actuation signal. the Surveillance Frequency Control Program

SR 3.5.2.8 Verify, for each ECCS throttle valve listed below, In accordance with each position stop is in the correct position. the Surveillance Frequency Control Valve Number Function Program

MO-3008 LPSI to Cold leg 1A MO-3010 LPSI to Cold leg 1B MO-3012 LPSI to Cold leg 2A MO-3014 LPSI to Cold leg 2B MO-3082 HPSI to Hot leg 1 MO-3083 HPSI to Hot leg 1

SR 3.5.2.9 Verify, by visual inspection, the containment sump In accordance with passive strainer assemblies are not restricted by the Surveillance debris, and the containment sump passive strainer Frequency Control assemblies and other containment sump entrance Program pathways show no evidence of structural distress or abnormal corrosion.

Palisades Nuclear Plant 3.5.2-3 Amendment No. XXX Containment Air Locks 3.6.2

ACTIONSFRQWLQXHG CONDITION REQUIRED ACTION COMPLETION TIME

A. (continued) A.2 Lock the OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months door closed in the affected air lock.

AND

NOTE-----------------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

A.3 Verify the OPERABLE Once per 31 days door is locked closed in the affected air lock.

B. One or more containment -----------------NOTES----------------

air locks with containment 1. Required Actions B.1, B.2, air lock interlock and B.3 are not applicable if mechanism inoperable. both doors in the same air lock are inoperable and Condition C is entered.

2. Entry and exit of containment is permissible under the control of a dedicated individual.

B.1 Verify an OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed in the affected air lock.

AND

(continued)

Palisades Nuclear Plant 3.6.2-2 Amendment No. XXX Containment Air Locks 3.6.2

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

B. (continued) B.2 Lock an OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months door closed in the affected air lock.

AND

NOTE-----------------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

B.3 Verify an OPERABLE Once per 31 days door is locked closed in the affected air lock.

C. One or more containment C.1 Initiate action to Immediately air locks inoperable for evaluate overall reasons other than containment leakage Condition A or B. rate per LCO 3.6.1.

AND

C.2 Verify a door is closed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in the affected air lock.

AND

C.3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND

D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

Palisades Nuclear Plant 3.6.2-3 Amendment No. XXX Containment Isolation Valves 3.6.3

ACTIONSFRQWLQXHG CONDITION REQUIRED ACTION COMPLETION TIME

A. (continued) --------------------NOTE----------------

Isolation devices in high radiation areas may be verified by use of administrative means.

A.2 Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment

AND

Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment

B. --------------NOTE------------- B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths with use of at least one two containment isolation closed and de-activated valves. automatic valve, closed

manual valve, or blind flange.

One or more penetration flow paths with two containment isolation valves inoperable (except for purge exhaust valve or air room supply valve not locked closed).

Palisades Nuclear Plant 3.6.3-2 Amendment No. XXX Containment Isolation Valves 3.6.3

ACTIONSFRQWLQXHG CONDITION REQUIRED ACTION COMPLETION TIME

C.1 Isolate the affected 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. --------------NOTE------------- penetration flow path by Only applicable to use of at least one penetration flow paths with closed and de-activated only one containment automatic valve, closed isolation valve and a manual valve, or blind closed system. flange.

AND One or more penetration flow paths with one -------------------NOTE-----------------

containment isolation valve Isolation devices in high radiation inoperable. areas may be verified by use of administrative means.

C.2 Verify the affected Once per 31 days penetration flow path is isolated.

D. One or more purge D.1 Lock closed the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months exhaust or air room supply valves.

valves not locked closed.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND

E.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

Palisades Nuclear Plant 3.6.3-3 Amendment No. XXX Containment Isolation Valves 3.6.3

SURVEILLANCE REQUIREMENTS FRQWLQXHG SURVEILLANCE FREQUENCY

SR 3.6.3.4 Verify the isolation time of each automatic power In accordance with operated containment isolation valve is within the INSERVICE limits. TESTING PROGRAM

SR 3.6.3.5 Verify each containment 8 inch purge exhaust and In accordance with 12 inch air room supply valve is closed by the Surveillance performance of a leakage rate test. Frequency Control Program

SR 3.6.3.6 Verify each automatic containment isolation valve In accordance with that is not locked, sealed, or otherwise secured in the Surveillance position, actuates to the isolation position on an Frequency Control actual or simulated actuation signal. Program

Palisades Nuclear Plant 3.6.3-5 Amendment No. XXX Containment Cooling Systems 3.6.6

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.6.6.7 Verify each containment spray pump starts In accordance with automatically on an actual or simulated actuation the Surveillance signal. Frequency Control Program

SR 3.6.6.8 Verify each containment cooling fan starts In accordance with automatically on an actual or simulated actuation the Surveillance signal. Frequency Control Program

SR 3.6.6.9 Verify each spray nozzle is unobstructed. Following maintenance which could result in nozzle blockage

Palisades Nuclear Plant 3.6.6-3 Amendment No. XXX AFW System 3.7.5

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months OR

Less than 100% of the required AFW flow available to either steam generator.

OR

Less than two AFW pumps OPERABLE in MODE 1, 2, OR 3.

C. Less than 100% of the ------------------NOTE------------------

required AFW flow LCO 3.0.3 and all other LCO available, to both steam Required Actions requiring MODE generators. changes or power reductions are suspended until at least 100% of the required AFW flow is available.

C.1 Initiate action to restore Immediately one AFW train to OPERABLE status.

Palisades Nuclear Plant 3.7.5-2 Amendment No. XXX CRV Filtration 3.7.10

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

C. ------------NOTE------------ C.1 Initiate action to implement Immediately Not applicable when mitigating actions.

second CRV Filtration train intentionally made AND inoperable.

C.2 Verify LCO 3.4.16, PCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Specific Activity, is met.

Two CRV Filtration trains AND inoperable in MODE 1, 2, 3, or 4 for reasons C.3 Restore at least one CRV 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months other than Condition B. Filtration train to OPERABLE status.

D. Required Action and D.1 Place OPERABLE CRV Immediately associated Completion Filtration train in Time of Condition A not emergency mode.

met during CORE ALTERATIONS, during OR movement of irradiated fuel assemblies, or D.2.1 Suspend CORE Immediately during movement of a ALTERATIONS.

fuel cask in or over the SFP. AND

D.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND

D.2.3 Suspend movement of a Immediately fuel cask in or over the SFP.

Palisades Nuclear Plant 3.7.10-2 Amendment No. XXX CRV Filtration 3.7.10

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

E. Two CRV Filtration E.1 Suspend CORE Immediately trains inoperable during ALTERATIONS.

CORE ALTERATIONS, during movement of AND irradiated fuel assemblies, or during E.2 Suspend movement of Immediately movement of a fuel cask irradiated fuel assemblies.

in or over the SFP.

AND OR E.3 Suspend movement of a Immediately One or more CRV fuel cask in or over the Filtration trains SFP.

inoperable due to an inoperable CRE boundary during CORE ALTERATIONS, during movement of irradiated fuel assemblies, or during movement of a fuel cask in or over the SFP.

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, B, AND or C not met in MODE 1, 2, 3, or 4. F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

Palisades Nuclear Plant 3.7.10-3 Amendment No. XXX CRV Cooling 3.7.11

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

D. Required Action and D.1 Place OPERABLE CRV Immediately associated Completion Cooling train in Time of Condition A not operation.

met during CORE ALTERATIONS, during OR movement of irradiated fuel assemblies, or D.2.1 Suspend CORE Immediately movement of a fuel cask in ALTERATIONS.

or over the SFP.

AND

D.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND

D.2.3 Suspend movement of a Immediately fuel cask in or over the SFP.

Palisades Nuclear Plant 3.7.11-2 Amendment No. XXX CRV Cooling 3.7.11

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

E. Two CRV Cooling trains E.1 Suspend CORE Immediately inoperable during CORE ALTERATIONS.

ALTERATIONS, during movement of irradiated AND fuel assemblies, or movement of a fuel cask in E.2 Suspend movement of Immediately or over the SFP. irradiated fuel assemblies.

AND

E.3 Suspend movement of a Immediately fuel cask in or over the SFP.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.7.11.1 Verify each CRV Cooling train has the capability to In accordance with remove the assumed heat load. the Surveillance Frequency Control Program

Palisades Nuclear Plant 3.7.11-3 Amendment No. XXX AC Sources - Operating 3.8.1

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

B. One DG inoperable. B.1 Perform SR 3.8.1.1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (offsite source check) for the OPERABLE AND offsite circuit(s).

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND

B.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from feature(s) supported by discovery of the inoperable DG Condition B inoperable when its concurrent with redundant required inoperability of feature(s) is inoperable. redundant required feature(s)

AND

B.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG is not inoperable due to common cause failure.

OR

B.3.2 Perform SR 3.8.1.2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (start test) for OPERABLE DG.

AND

B.4 Restore DG to 7 days OPERABLE status.

AND

10 days from discovery of failure to meet LCO

Palisades Nuclear Plant 3.8.1-2 Amendment No. XXX AC Sources - Operating 3.8.1

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

C. Two offsite circuits C.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from inoperable. feature(s) inoperable discovery of when its redundant Condition C required feature(s) is concurrent with inoperable. inoperability of redundant required feature(s)

AND

C.2 Restore one offsite 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months circuit to OPERABLE status.

D. One offsite circuit ------------------NOTE------------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.9, AND "Distribution Systems -

Operating," when Condition D is One DG inoperable. entered with no AC power source to any train.

D.1 Restore offsite circuit to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

OR

D.2 Restore DG to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

E. Two DGs inoperable. E.1 Restore one DG to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months OPERABLE status.

Palisades Nuclear Plant 3.8.1-3 Amendment No. XXX AC Sources - Operating 3.8.1

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion Time of Condition A, B, C, AND D, or E not met.

F.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

G. Three or more AC sources G.1 Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.8.1.1 Verify correct breaker alignment and voltage for In accordance with each offsite circuit. the Surveillance Frequency Control Program

SR 3.8.1.2 Verify each DG starts from standby conditions and In accordance with achieves: the Surveillance Frequency Control

a. In 10 seconds, ready-to-load status; and Program

b. Steady state voltage 2280 V and 2520 V, and frequency 59.5 Hz and 61.2 Hz.

Palisades Nuclear Plant 3.8.1-4 Amendment No. XXX AC Sources - Operating 3.8.1

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.8.1.3 -----------------------------NOTES---------------------------

1. Momentary transients outside the load range do not invalidate this test.

2. This Surveillance sh all be conducted on only one DG at a time.

3. This Surveillance shall be preceded by and immediately follow without shutdown a successful performance of SR 3.8.1.2.

Verify each DG is synchronized and loaded, and In accordance with operates for 60 minutes: the Surveillance Frequency Control

a. For 15 minutes loaded to greater than orProgram equal to peak accident load; and

b. For the remainder of the test at a load 2300 kW and 2500 kW.

SR 3.8.1.4 Verify each day tank contains 2500 gallons of In accordance with fuel oil. the Surveillance Frequency Control Program

SR 3.8.1.5 Verify each DG rejects a load greater than or equal In accordance with to its associated single largest post-accident load, the Surveillance and: Frequency Control Program

a. Following load rejection, the frequency is 68 Hz;

b. Within 3 seconds following load rejection, the voltage is 2280 V and 2640 V; and

c. Within 3 seconds following load rejection, the frequency is 59.5 Hz and 61.5 Hz.

Palisades Nuclear Plant 3.8.1-5 Amendment No. XXX AC Sources - Operating 3.8.1

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.8.1.6 Verify each DG, operating at a power factor 0.9, In accordance with does not trip, and voltage is maintained 4000 V the Surveillance during and following a load rejection of 2300 kW Frequency Control and 2500 kW. Program

SR 3.8.1.7 -----------------------------NOTE-----------------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify on an actual or simulated loss of offsite In accordance with power signal: the Surveillance Frequency Control

a. De-energization of emergency buses; Program

b. Load shedding from emergency buses;

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in 10 seconds,

2. energizes auto-connected shutdown loads through automatic load sequencer,

3. maintains steady state voltage 2280 V and 2520 V,

4. maintains steady state frequency 59.5 Hz and 61.2 Hz, and

5. supplies permanently connected loads for 5 minutes.

Palisades Nuclear Plant 3.8.1-6 Amendment No. XXX

AC Sources - Operating 3.8.1

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.8.1.10 -----------------------------NOTE-----------------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify the time of each sequenced load is within In accordance with

+/- 0.3 seconds of design timing for each automatic the Surveillance load sequencer. Frequency Control Program

SR 3.8.1.11 -----------------------------NOTE-----------------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify on an actual or simulated loss of offsite In accordance with power signal in conjunction with an actual or the Surveillance simulated safety injection signal: Frequency Control Program

a. De-energization of emergency buses;

b. Load shedding from emergency buses;

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in 10 seconds,

2. energizes auto-connected emergency loads through its automatic load sequencer,

3. achieves steady state voltage 2280 V and 2520 V,

4. achieves steady state frequency 59.5 Hz and 61.2 Hz, and

5. supplies permanently connected loads for 5 minutes.

Palisades Nuclear Plant 3.8.1-8 Amendment No. XXX AC Sources - Shutdown 3.8.2

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

A. (continued) A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND

A.2.3 Initiate action to Immediately suspend operations involving positive reactivity additions.

AND

A.2.4 Initiate action to restore Immediately required offsite power circuit to OPERABLE status.

B. The required DG B.1 Suspend CORE Immediately inoperable. ALTERATIONS.

AND

B.2 Suspend movement of Immediately irradiated fuel assemblies.

AND

B.3 Initiate action to Immediately suspend operations involving positive reactivity additions.

AND

B.4 Initiate action to restore Immediately required DG to OPERABLE status.

Palisades Nuclear Plant 3.8.2-2 Amendment No. XXX Diesel Fuel, Lube Oil, and Starting Air 3.8.3

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

E. Both fuel transfer systems E.1 Restore one fuel 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable. transfer system to OPERABLE status.

F. Fuel oil properties other F.1 Restore stored fuel oil 30 days than viscosity, and water properties to within and sediment, not within limits.

limits.

G. Required Action and G.1 Declare associated Immediately associated Completion DG(s) inoperable.

Time not met.

OR

Stored diesel fuel oil, lube oil, or starting air subsystem not within limits for reasons other than Condition A, B, or F.

Palisades Nuclear Plant 3.8.3-2 Amendment No. XXX DC Sources - Operating 3.8.4

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND

C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.8.4.1 Verify battery terminal voltage is 125 V on float In accordance with charge. the Surveillance Frequency Control Program

SR 3.8.4.2 Verify no visible corrosion at battery terminals and In accordance with connectors. the Surveillance Frequency Control OR Program

Verify battery connection resistance is 50 ohm for inter-cell connections, 360 ohm for inter-rack connections, and 360 ohm for inter-tier connections.

SR 3.8.4.3 Inspect battery cells, cell plates, and racks for In accordance with visual indication of physical damage or abnormal the Surveillance deterioration that could degrade battery Frequency Control performance. Program

Palisades Nuclear Plant 3.8.4-2 Amendment No. XXX DC Sources - Operating 3.8.4

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.8.4.4 Remove visible terminal corrosion and verify In accordance with battery cell to cell and terminal connections are the Surveillance coated with anti-corrosion material. Frequency Control Program

SR 3.8.4.5 Verify battery connection resistance is In accordance with 50 ohm for inter-cell connections, 360 ohm the Surveillance for inter-rack connections, and 360 ohm for Frequency Control inter-tier connections. Program

SR 3.8.4.6 Verify each required battery charger supplies In accordance with 180 amps at 125 V for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . the Surveillance Frequency Control Program

SR 3.8.4.7 -----------------------------NOTES---------------------------

1. The modified performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7.

2. This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify battery capacity is adequate to supply, and In accordance with maintain in OPERABLE status, the required emergency loads for the design duty cycle when the Surveillance subjected to a battery service test. Frequency Control Program

Palisades Nuclear Plant 3.8.4-3 Amendment No. XXX DC Sources - Operating 3.8.4

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.8.4.8 -------------------------------NOTE---------------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

Verify battery capacity is 80% of the In accordance with manufacturer's rating when subjected to a the Surveillance performance discharge test or a modified Frequency Control performance discharge test. Program

AND

12 months when battery shows degradation or has reached 85% of the expected life with capacity < 100% of manufacturer's rating

AND

24 months when battery has reached 85% of the expected life with capacity 100% of manufacturer's rating

Palisades Nuclear Plant 3.8.4-4 Amendment No. XXX DC Sources - Shutdown 3.8.5

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

A. (continued) A.2.4 Initiate action to restore Immediately required DC electrical power source(s) to OPERABLE status.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.8.5.1 For DC sources required to be OPERABLE, the In accordance with following SRs are applicable: applicable SRs

SR 3.8.4.1 SR 3.8.4.3 SR 3.8.4.5 SR 3.8.4.2 SR 3.8.4.4 SR 3.8.4.6.

Palisades Nuclear Plant 3.8.5-2 Amendment No. XXX Battery Cell Parameters 3.8.6

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

B. Required Action and B.1 Declare associated Immediately associated Completion battery inoperable.

Time of Condition A not met.

OR

One or more batteries with average electrolyte temperature of the representative cells

< 70qF.

OR

One or more batteries with one or more battery cell parameters not within Category C limits.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.8.6.1 Verify battery cell parameters meet Table 3.8.6-1 In accordance with Category A limits. the Surveillance Frequency Control Program

SR 3.8.6.2 Verify average electrolyte temperature of In accordance with representative cells is 70qF. the Surveillance Frequency Control Program

Palisades Nuclear Plant 3.8.6-2 Amendment No. XXX Battery Cell Parameters 3.8.6

SURVEILLANCE REQUIREMENTS FRQWLQXHG

SURVEILLANCE FREQUENCY

SR 3.8.6.3 Verify battery cell parameters meet Table 3.8.6-1 In accordance with Category B limits. the Surveillance Frequency Control Program

Palisades Nuclear Plant 3.8.6-3 Amendment No. XXX Distribution Systems - Operating 3.8.9

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND

D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

E. Two or more inoperable E.1 Enter LCO 3.0.3. Immediately distribution subsystems that result in a loss of function.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.8.9.1 Verify correct breaker alignments and voltage to In accordance with required AC, DC, and Preferred AC bus electrical the Surveillance power distribution subsystems. Frequency Control Program

Palisades Nuclear Plant 3.8.9-2 Amendment No. XXX Distribution Systems - Shutdown 3.8.10

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

A. (continued) A.2.4 Initiate actions to restore Immediately required AC, DC, and Preferred AC bus electrical power distribution subsystems to OPERABLE status.

AND

A.2.5 Declare associated Immediately required shutdown cooling train inoperable and not in operation.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.8.10.1 Verify correct breaker alignments and voltage to In accordance with required AC, DC, and Preferred AC bus electrical the Surveillance power distribution subsystems. Frequency Control Program

Palisades Nuclear Plant 3.8.10-2 Amendment No. XXX SDC and Coolant Circulation - High Water Level 3.9.4

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

A. (continued) A.3 Suspend loading Immediately irradiated fuel assemblies in the core.

AND

A.4 Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.9.4.1 Verify one SDC train is in operation and circulating In accordance with primary coolant at a flow rate of t 1000 gpm. the Surveillance Frequency Control Program

Palisades Nuclear Plant 3.9.4-2 Amendment No. XXX SDC and Coolant Circulation - Low Water Level 3.9.5

ACTIONSFRQWLQXHG

CONDITION REQUIRED ACTION COMPLETION TIME

B. No SDC train OPERABLE B.1 Suspend operations Immediately or in operation. involving a reduction in primary coolant boron concentration.

AND

B.2 Initiate action to restore Immediately one SDC train to OPERABLE status and to operation.

AND

B.3 Initiate action to close Immediately all containment penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.9.5.1 Verify one SDC train is in operation and In accordance with circulating primary coolant at a flow rate of the Surveillance t 1000 gpm. Frequency Control Program

SR 3.9.5.2 Verify correct breaker alignment and indicated In accordance with power available to the required SDC pump that is the Surveillance not in operation. Frequency Control Program

Palisades Nuclear Plant 3.9.5-2 Amendment No. XXX Programs and Manuals 5.5

5.5 Programs and Manuals

5.5.4 Radioactive Effluent Controls Program (continued)

g. Limitations on the annual and quarterly doses to a member of the public from Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each plant to areas beyond the site boundary conforming to 10 CFR 50, Appendix I,

h. Limitations on the annual doses or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR 190.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

5.5.5 Containment Structural Integrity Surveillance Program

This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Containment Structural Integrity Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWE and IWL.

If, as a result of a tendon inspection, corrective retensioning of five percent (8) or more of the total number of dome tendons is necessary to restore their liftoff forces to within the limits, a dome delamination inspection shall be performed within 90 days following such corrective retensioning. The results of this inspection shall be reported to the NRC in accordance with Specification 5.6.7, Containment Structural Integrity Surveillance Report.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Containment Structural Integrity Surveillance Program inspection frequencies.

5.5.6 Primary Coolant Pump Flywheel Surveillance Program

a. Surveillance of the primary coolant pump flywheels shall consist of a 100% volumetric inspection of the upper flywheels each 10 years.

b. The provisions of SR 3.0.2 are not applicable to the Flywheel Testing Program

Palisades Nuclear Plant 5.0-9 Amendment No. 272, XXX Programs and Manuals 5.5

5.5 Programs and Manuals

5.5.8 Steam Generator (SG) Program

d. Provisions for SG tube inspections. (continued)

location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.

1. Inspect 100% of the tubes in each SG during the first refueling outage following SG replacement.

2. Inspect 100% of the tubes at sequential periods of 60 effective full power months. The first sequential period shall be considered to begin after the first inservice inspection of the SGs. No SG shall operate for more than 24 effective full power months or one refueling outage (whichever is less) without being inspected.

3. If crack indications are found in any SG tube from 12.5 inches below the bottom of the hot-leg expansion transition or top of the hot-leg tubesheet, whichever is lower, to 13.67 inches below the bottom of the cold-leg expansion transition or top of the cold-leg tubesheet, whichever is lower, then the next inspection for each SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever is less). If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.

4. When the alternate repair criteria of TS 5.5.8c.1 are implemented, inspect 100% of the inservice tubes to the hot-leg tubesheet region with the objective of detecting flaws that may satisfy the applicable tube repair criteria of TS 5.5.8c.1 every 24 effective full power months, or one refueling outage, whichever is less.

e. Provisions for monitoring operational primary to secondary LEAKAGE.

Palisades Nuclear Plant 5.0-12 Amendment No. XXX Programs and Manuals 5.5

5.5 Programs and Manuals

5.5.9 Secondary Water Chemistry Program

A program shall be established, implemented and maintained for monitoring of secondary water chemistry to inhibit steam generator tube degradation and shall include:

a. Identification of a sampling schedule for the critical variables and control points for these variables,

b. Identification of the procedures used to measure the values of the critical variables,

c. Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage,

d. Procedures for the recording and management of data,

e. Procedures defining corrective actions for all off-control point chemistry conditions, and

f. A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective actions.

5.5.10 Ventilation Filter Testing Program

A program shall be established to implement the following required testing of Control Room Ventilation (CRV) and Fuel Handling Area Ventilation (FHAV) systems at the frequencies specified in Regulatory Guide 1.52, Revision 2 (RG 1.52), and in accordance with RG 1.52 and ASME N510-1989, at the system flowrates and tolerances specified below*:

a. Demonstrate for each of the ventilation systems that an inplace test of the High Efficiency Particulate Air (HEPA) filters shows a penetration and system bypass < 0.05% for the CRV system and < 1.00% for the FHAV system when tested in accordance with RG 1.52 and ASME N510-1989:

Ventilation System Flowrate (CFM)

FHAV (single fan operation) 7300 +/- 20%

FHAV (dual fan operation) 10,000 +/- 20%

CRV 3,200 +10% -5%

Palisades Nuclear Plant 5.0-13 Amendment No. XXX Programs and Manuals 5.5

5.5 Programs and Manuals

5.5.11 Fuel Oil Testing Program

A fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling requirements, testing requirements, and acceptance criteria, based on the diesel manufacturers specifications and applicable ASTM Standards. The program shall establish the following:

a. Acceptability of new fuel oil prior to addition to the Fuel Oil Storage Tank, and acceptability of fuel oil stored in the Fuel Oil Storage Tank, by determining that the fuel oil has the following properties within limits:

1. API gravity or an absolute specific gravity,

2. Kinematic viscosity, and

3. Water and sediment content.

b. Other properties of fuel oil stored in the Fuel Oil Storage Tank, specified by the diesel manufacturers or specified for grade 2D fuel oil in ASTM D 975, are within limits.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Fuel Oil Testing Program.

5.5.12 Technical Specifications (TS) Bases Control Program

This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the license; or

2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

Palisades Nuclear Plant 5.0-15 Amendment No. 272, XXX Programs and Manuals 5.5

5.5 Programs and Manuals

5.5.12 Technical Specifications (TS) Bases Control Program (continued)

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.

d. Proposed changes that meet the criteria of Specification 5.5.12.b. above shall be reviewed and approved by the NRC prior to implementation.

Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

5.5.13 Safety Functions Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6. The SFDP shall contain the following:

a. Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

b. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

c. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d. Other appropriate limitations and remedial or compensatory actions.

A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to system(s) supported by the inoperable support system is also inoperable; or

b. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or

c. A required system redundant to support system(s) for the supported systems (a) and (b) above is also inoperable.

Palisades Nuclear Plant 5.0-16 Amendment No. 272, XXX Programs and Manuals 5.5

5.5 Programs and Manuals

5.5.13 Safety Functions Determination Program (SFDP) (Continued)

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

5.5.14 Containment Leak Rate Testing Program

a. A program shall establish the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with NEI 94-01, Revision 2-A, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J, dated October 2008, with the following exceptions:

1. Leakage rate testing is not necessary after opening the Emergency Escape Air Lock doors for post-test restoration or post-test adjustment of the air lock door seals. However, a seal contact check shall be performed instead.

Emergency Escape Airlock door opening, solely for the purpose of strongback removal and performance of the seal contact check, does not necessitate additional pressure testing.

2. Leakage rate testing at Pa is not necessary after adjustment of the Personnel Air Lock door seals. However, a between-the-seals test shall be performed at t 10 psig instead.

3. Leakage rate testing frequency for the Containment 4 inch purge exhaust valves, the 8 inch purge exhaust valves, and the 12 inch air room supply valves may be extended up to 60 months based on component performance.

b. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pa, is 54.2 psig. The containment design pressure is 55 psig.

c. The maximum allowable containment leakage rate, La, at Pa, shall be 0.1% of containment air weight per day.

Palisades Nuclear Plant 5.0-17 Amendment No. XXX Programs and Manuals 5.5

5.5 Programs and Manuals

5.5.14 Containment Leak Rate Testing Program (Continued)

d. Leakage rate acceptance criteria are:

1. Containment leakage rate acceptance criteria is d 1.0 La. During the first plant startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and Type C tests and d 0.75 La for Type A tests.

2. Air lock testing acceptance criteria are:

a) Overall air lock leakage is d 1.0 La when tested at t Pa and combined with all penetrations and valves subjected to Type B and C tests. However, during the first unit startup following testing performed in accordance with this program, the leakage rate acceptance criteria is < 0.6 La when combined with all penetrations and valves subjected to Type B and C tests.

b) For each Personnel Air Lock door, leakage is d 0.023 La when pressurized to t 10 psig.

c) For each Emergency Escape Air Lock door, a seal contact check , consisting of a verification of continuous contact between the seals and the sealing surfaces, is acceptable.

e. Containment OPERABILITY is equivalent to "Containment Integrity" for the purposes of the testing requirements.

f. The provisions of SR 3.0.3 are applicable to the Containment Leak Rate Testing Program requirements.

g. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.

Palisades Nuclear Plant 5.0-18 Amendment No. XXX Programs and Manuals 5.5

5.5 Programs and Manuals

5.5.16 Control Room Envelope Habitability Program

A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Ventilation (CRV) Filtration, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem whole body or its equivalent to any part of the body for the duration of the accident. The program shall include the following elements:

a. The definition of the CRE and the CRE boundary.

b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CRV Filtration, operating at the flow rate required by the Ventilation Filter Testing Program, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.

e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.

The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

Palisades Nuclear Plant 5.0-20 Amendment No. XXX Programs and Manuals 5.5

5.5 Programs and Manuals

5.5.17 Surveillance Frequency Control Program

This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

Palisades Nuclear Plant 5.0-21 Amendment No. XXX Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS

5.6 Reporting Requirements

The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 (Deleted)

5.6.2 Radiological Environmental Operating Report

The Radiological Environmental Operating Report covering the operation of the plant during the previous calendar year shall be submitted before May 15 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

5.6.3 Radioactive Effluent Release Report

The Radioactive Effluent Release Report covering operation of the plant in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant.

The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual and Process Control Program, and shall be in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

5.6.4 (Deleted)

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

3.1.1 Shutdown Margin 3.1.6 Regulating Rod Group Position Limits 3.2.1 Linear Heat Rate Limits 3.2.2 Radial Peaking Factor Limits 3.2.4 ASI Limits 3.4.1 DNB Limits

Palisades Nuclear Plant 5.0-22 Amendment No. 261, 272, XXX Reporting Requirements 5.6

5.6 Reporting Requirements

5.6.5 COLR (Continued)

b. The analytical methods used to determine the core operating limits shall be those approved by the NRC, specifically those described in the latest approved revision of the following documents:

1. EMF-96-029(P)(A) Volumes 1 and 2, Reactor Analysis System for PWRs, Siemens Power Corporation.

(LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

2. ANF-84-73 Appendix B (P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation. (Bases report not approved) (LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

3. XN-NF-82-21(P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations,"

Exxon Nuclear Company.

(LCOs 3.2.1, 3.2.2, & 3.2.4)

4. EMF-84-093(P)(A), Steam Line Break Methodology for PWRs, Siemens Power Corporation.

(LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

5. XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company. (Bases document not approved)

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

6. EMF-2310 (P)(A), Revision 0, Framatome ANP, Inc., May 2001, SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

7. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, & 3.2.2)

8. ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

9. EMF-92-153(P)(A) and Supplement 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation. (LCOs 3.2.1, 3.2.2, & 3.2.4)

Palisades Nuclear Plant 5.0-23 Amendment No. XXX Reporting Requirements 5.6

5.6 Reporting Requirements

5.6.5 COLR (Continued)

10. XN-NF-621(P)(A), Exxon Nuclear DNB Correlation for PWR Fuel Designs, Exxon Nuclear Company. (LCOs 3.2.1, 3.2.2, & 3.2.4)

11. XN-NF-82-06(P)(A) and Supplements 2, 4, and 5, Qualification of Exxon Nuclear Fuel for Extended Burnup, Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

12. ANF-88-133(P)(A) and Supplement 1, Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWD/MTU, Advanced Nuclear Fuels Corporation. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

13. XN-NF-85-92(P)(A), Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results, Exxon Nuclear Company. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

14. EMF-92-116(P)(A), Generic Mechanical Design Criteria for PWR Fuel Designs, Siemens Power Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

15. EMF-2087(P)(A), SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications, Siemens Power Corporation.

(LCOs 3.1.6, 3.2.1, & 3.2.2)

16. ANF-87-150 Volume 2, Palisades Modified Reactor Protection System Report: Analysis of Chapter 15 Events, Advanced Nuclear Fuels Corporation. [Approved for use in the Palisades design during the NRC review of license Amendment 118, November 15, 1988] (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.4.1)

17. EMF-1961(P)(A), Revision 0, Siemens Power Corporation, July 2000, Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors. (LCOs 3.1.6, 3.2.1, 3.2.2, 3.2.4, &

3.4.1)

18. EMF-2328 (P)(A), Revision 0, Framatome ANP, Inc., March 2001, PWR Small Break LOCA Evaluation Model, S-RELAP5 Based.

(LCOs 3.1.6, 3.2.1, & 3.2.2)

19. BAW-2489P, Revised Fuel Assembly Growth Correlation for Palisades. (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

20. EMF-2103(P)(A), Realistic Large Break LOCA Methodology for Pressurized Water Reactors. (LCOs 3.1.6, 3.2.1, & 3.2.2)

Palisades Nuclear Plant 5.0-24 Amendment No. XXX Reporting Requirements 5.6

5.6 Reporting Requirements

5.6.5 COLR (Continued)

21. BAW-10240(P)-A, Incorporation of M5 Properties in Framatome ANP Approved Methods. (LCOs 3.1.6, 3.2.1, 3.2.2, 3.2.4, & 3.4.1)

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any mid cycle revisions or supplements, shall be provided, upon issuance for each reload cycle, to the NRC.

5.6.6 Post Accident Monitoring Report

When a report is required by LCO 3.3.7, "Post Accident Monitoring Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to OPERABLE status.

5.6.7 Containment Structural Integrity Surveillance Report

Reports shall be submitted to the NRC covering Prestressing, Anchorage, and Dome Delamination tests within 90 days after completion of the tests.

5.6.8 Steam Generator Tube Inspection Report

A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.8, Steam Generator (SG) Program. The report shall include:

a. The scope of inspections performed on each SG,

b. Active degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism,

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e. Number of tubes plugged during the inspection outage for each active degradation mechanism,

Palisades Nuclear Plant 5.0-25 Amendment No. XXX Reporting Requirements 5.6

5.6 Reporting Requirements

5.6.8 Steam Generator Tube Inspection Report (continued)

f. Total number and percentage of tubes plugged to date,

g. The results of condition monitoring, including the results of tube pulls and in-situ testing, and

h. The effective plugging percentage for all plugging in each SG.

i The results of monitoring for tube axial displacement (slippage). If slippage is discovered, the implications of the discovery and corrective action shall be provided.

Palisades Nuclear Plant 5.0-26 Amendment No. XXX HDI PNP 2024-027

Enclosure Attachment 3

Updated Proposed Technical Specifications Bases Changes

(for information only)

Only replacement pages are provided. Please replace the affected pages from Reference 1 with the attached pages.

7 pages follow

LCO Applicability B 3.0 BASES

B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY through BASES 9

LCO LCO 3.0.1 and LCO 3.0.2 establish the general requirements applicable to all Specifications and apply at all times unless otherwise stated.

LCO 3.0.1 LCO 3.0.1 establishes the Applicability statement within each individual Specification as the requirement for when the LCO is required to be met (i.e., when the facility is in the specified conditions of the Applicability statement of each Specification). MODES or other

_____ \\ ________.=j ~ 1----=plant1 ============~ -

LCO 3.0.2 LCO 3.0.2 establishes that upon discovery of a failure to meet an LCO, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions , unless establish those remedial measures that must be taken within specified Completion Times when the requirements of an LCO are not met. This otherwise Specification establishes that: specified

a. Completion of the Required Actions within the specified Completion Times constitutes compliance with a Specification; and LCO 3.0.2 INSERT b. Completion of the Required Actions is not required when an LCO is met within the specified Completion Time, unless otherwise specified.

Completing the Required Actions is not required when an LCO is met or is no longer applicable, unless otherwise stated in the individual Specifications.

Palisades Nuclear Plant B 3.0-1 Amendment No. 272 Revised 06/15/2022 LCO Applicability B 3.0 BASES

B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY

BASES

SRs SR 3.0.1 through SR 3.0.4 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated. SR MODES or other 3.0.2 and SR 3.0.3 apply in Chapter 5 only when invoked by a Chapter 5 specification. the OPERABILITY of systems and components, and SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during the specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify that variables are within specified limits. Failure to meet a Surveillance within the specified Frequency, in accordance with SR 3.0.2, constitutes a failure to meet an LCO. Surveillances may be performed by means of any series of sequential, overlapping, or total steps provided the entire Surveillance is performed within the specified Frequency. INSERT SR 3.0.1.A

The LCO is assumed to be met when the SRs have been met. Nothing in this Specification, however, is to be construed as implying that the LCO is met when the Surveillance(s) are known to be not met between MODE or other Surveillance performances. plant

, unless otherwise specified Surveillances do not have to be performed when the facility is in a specified condition for which the requirements of the associated LCO are not applicable. ~~~~ INSERT SR 3.0.1.B

INSERT SR 3.0.1.C Surveillances do not have to be performed on variables that are outside

.._____--~-------their specified limits because the ACTIONS define the remedial measures that apply. Surveillances have to be met and performed in accordance with SR 3.0.2, to restore variables within their specified limits.

SR 3.0.2 SR 3.0.2 establishes the requirements for meeting the specified Frequency for Surveillances.

plant operating SR 3.0.2 permits a 25% extension of the interval specified in the Frequency. This extension facilitates Surveillance scheduling and considers facility conditions that may not be suitable for conducting the Surveillance (e.g., ongoing Surveillance or maintenance activities).

.-------------, and any Required Action with a Completion transient conditions or other Time that requires the periodic performance of the Required Action on a "Once per . . ."

interval Palisades Nuclear Plant B 3.0-2 Amendment No. 272 Revised 06/15/2022 LCO Applicability B 3.0 BASES

SR 3.0.2 When a Section 5.5, Programs and Manuals, specification states that (continued) the provisions of SR 3.0.2 are applicable, a 25% extension of the testing interval, whether stated in the specification or incorporated by reference, is permitted.

The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified Frequency. This is based on the recognition that the most probable result of any particular INSERT SR 3.0.2.A (other than those consistent withSurveillance being performed is the verification of conformance with the

,______~ SRs.

The provisions of SR 3.0.2 are not intended to be used repeatedly to refueling intervals)

extend Surveillance intervals or periodic Completion Time intervals beyond those specified. affected equipment inoperable or

SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring an affected variable outside the specified limits when a Surveillance has not been performed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater, applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was not met.

When a Section 5.5, Programs and Manuals, specification states that the provisions of SR 3.0.3 are applicable, it permits the flexibility to defer declaring the testing requirement not met in accordance with SR 3.0.3 when the testing has not been completed within the testing interval (including the allowance of SR 3.0.2 if invoked by the Section 5.5 specification).

This delay period provides an adequate time to perform Surveillances that have been missed. This delay period permits the performance of a Surveillance before complying with Required Actions or other remedial measures that might preclude performance of the Surveillance.

Palisades Nuclear Plant B 3.0-3 Amendment No. 272 Revised 06/15/2022 LCO Applicability B 3.0 BASES plant

SR 3.0.3 The basis for this delay period includes consideration of facility (continued) conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in

, operating situations, or completing the required Surveillance, and the recognition that the most unit requirements of probable result of any particular Surveillance being performed is the regulations (e.g., prior to verification of conformance with the requirements. When a Surveillance entering MODE 1 after with a Frequency based not on time intervals, but upon specified facility each fuel loading, or in conditions, is discovered to not have been performed when specified, SR accordance with 10 CFR 3.0.3 allows for the full delay period of up to the specified Frequency to 50, Appendix J, as perform the Surveillance. However, since there is not a time interval modified by approved specified, the missed Surveillance should be performed at the first exemptions, etc.) reasonable opportunity.

equipment is OPERABLE or that SR 3.0.3 is only applicable if there is a reasonable expectation the associated variables are within limits, and it is expected that the SR 3.0.3 provides a time Surveillance will be met when performed. Many factors should be INSERT limit for, and allowances considered, such as the period of time since the Surveillance was last SR 3.0.3.A for the performance of, performed, or whether the Surveillance, or a portion thereof, has ever Surveillances that been performed, and any other indications, tests, or activities that might become applicable as a support the expectation that the Surveillance will be met when performed.

consequence of MODE Failure to comply with specified Frequencies for SRs is expected to be an changes imposed by infrequent occurrence. Use of the delay period established by SR 3.0.3 is Required Actions. a flexibility which is not intended to be used repeatedly to extend Surveillance intervals. plant plant

While up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or the limit of the specified Frequency is provided to perform the missed Surveillance, it is expected that the missed Surveillance will be performed at the first reasonable opportunity. The determination of the first reasonable opportunity should include unit consideration of the impact on facility risk (from delaying the Surveillance as well as any facility configuration changes required to perform the Surveillance) and impact on any analysis assumptions, in addition to facility conditions, planning, availability of personnel, and the time required to perform the Surveillance. All missed Surveillances will be placed in the licensee's Corrective Action Program. INSERT SR 3.0.3.B equipment is considered

..__________.I\\ inoperable or the If a Surveillance is not completed within the allowed delay period, then the variable is considered outside the specified limits and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon expiration of the delay period. If a Surveillance is failed within the delay period, then the variable is outside the specified limits and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon the failure of the Surveillance.

--J equipment is inoperable, or the

Palisades Nuclear Plant B 3.0-4 Amendment No. 272 Revised 06/15/2022 system and component OPERABILITY requirements and LCO Applicability B 3.0 BASES

SR 3.0.3 Completion of the Surveillance within the delay period allowed by this (continued) Specification, or within the Completion Time of the ACTIONS, restores compliance with SR 3.0.1.

MODE or other

SR 3.0.4 SR 3.0.4 establishes the requirement that all applicable SRs must be met MODES or other systemsbefore entry into a specified Condition in the Applicability.

This Specification ensures that variable limits are met before entry into and specified conditions in the Applicability for which these variables ensure components INSERT SR 3.0.4.A safe handling and storage of spent fuel. ensure safe

,______~--

The provisions of this Specification should not be interpreted as operation of endorsing the failure to exercise the good practice of restoring variables the plant within specified limits before entering an associated specified condition in system, subsystem, the Applicability.

division, component, inoperable or However, in certain circumstances, failing to meet an SR will not result in device, or SR 3.0.4 restricting a MODE change or other specified condition change. When a variable is outside its specified limits, the associated SR(s) are not required to be performed, per SR 3.0.1, which states that surveillances do not have to be performed on variables that are outside their specified limits. When a variable is outside its specified limit, SR 3.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specified Frequency does not result in an SR 3.0.4 restriction to changing specified conditions of the Applicability.

However, since the LCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may (or may not) apply to specified condition changes.

equipment is inoperable SR 3.0.4 does not restrict changing specified conditions of the Applicability when a Surveillance has not been performed within the specified Frequency, providing the requirement to declare the LCO not met has been delayed in accordance with SR 3.0.3.

inoperable equipment MODES or other

MODES or other MODE or other

INSERT SR 3.0.4.B

Palisades Nuclear Plant B 3.0-5 Amendment No. 272 Revised 06/15/2022 INSERT Bases 3.1.3 MTC B 3.1.3

BASES

LCO LCO 3.1.3 requires the MTC to be < 0.5 E-4 $ /qF at d 2 % R T P t o ensure the core operates within the assumptions of the accident analysis. During the reload core safety evaluation, the MTC is analyzed to determine that its values remain within the bounds of the original accident analysis during operation. The limit on a positive MTC ensures that core overheating accidents will not violate the accident analysis assumptions.

MTC is a core physics parameter determined by the fuel and fuel cycle design and cannot be easily controlled once the core design is fixed.

During operation, therefore, the LCO can only be ensured through measurement. The surveillance check at BOC on the MTC provide confirmation that the MTC is behaving as anticipated, so that the acceptance criteria are met.

APPLICABILITY In MODE 1, the MTC must be maintained to ensure that any accident initiated from THERMAL POWER operation will not violate the design assumptions of the accident analysis. In MODE 2, the limits must also be maintained to ensure startup and subcritical accidents, such as the uncontrolled full-length control rod or group withdrawal, will not violate the assumptions of the accident analysis. The measurement of MTC in MODE 2 prior to exceeding 2% RTP is used to confirm that the core is behaving as analyzed. This ensures that the MTC will remain within the analyzed range while operating in MODES 1 and 2. In MODES 3, 4, 5, and 6, this LCO is not applicable, since no Design Basis Accidents (DBAs) using the MTC as an analysis assumption are initiated from these MODES. However, the variation of the MTC, with temperature in MODES 3, 4, and 5, for DBAs initiated in MODES 1 and 2, is accounted for in the subject accident analysis. The variation of the MTC, with temperature assumed in the safety analysis, is accepted as valid once the BOC measurement is used for normalization.

Palisades Nuclear Plant B 3.1.3-3 Amendment No. 189 Spent Fuel Pool Storage PLANT B 3.7.16

B 3.7 FACILITY SYSTEMS either new (nonirradiated)

B 3.7.16 Spent Fuel Pool Storage nuclear fuel assemblies, or BASES BACKGROUND The fuel storage facility is designed to store used (irradiated) fuel w assemblies in a vertical configuration underwater. The storage pool is sized to store 892 fuel assemblies, which includes storage for failed fuel canisters. The fuel storage racks are grouped into two regions, Region I and Region II per Figure B 3.7.16-1. The racks are designed as a Seismic Category I structure able to withstand seismic events.

Region I contains Metamic equipped racks in the spent fuel pool having a 10.25 inch center-to-center spacing and a single Carborundum equipped rack in the north tilt pit having an 11.25 inch by 10.69 inch center-to-center spacing. The Region I Carborundum equipped rack has restrictive loading patterns to address degradation of neutron absorbing material in the rack. The loading patterns accommodate some face-adjacent fuel assemblies with consideration of burnup credit in Sub-Regions 1D and 1E. The Region 1 Metamic equipped racks are only restricted by maximum planar U235 enrichment. The Region I Carborundum equipped rack also has provisions for storing non-fissile bearing components.

Region II contains racks in both the spent fuel pool and the north tilt pit having a 9.17 inch center-to-center spacing. Because of the smaller spacing and an analyzed solid poison concentration of zero (Boraflex),

Region II also has limitations for fuel storage. Further information on limitations can be found in Section 4.0, Design Features. These limitations (e.g., enrichment, burnup, loading patterns) are sufficient to maintain a keff of 0.95 when flooded with borated water and keff < 1.0 when flooded with unborated water.

APPLICABLE The fuel storage facility was originally designed for noncriticality by use SAFETY ANALYSES of adequate spacing, and "flux trap" construction, whereby the fuel assemblies are inserted into neutron absorbing stainless steel cans.

The current criticality calculations also take credit for soluble boron to prevent criticality.

The spent fuel pool storage meets the requirements specified in Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light-Water Reactor Power Plants, Laurence I. Kopp, U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Reactor Systems Branch, February 1998. This document

Palisades Nuclear Plant B 3.7.16-1 Amendment No. 272 Revised 06/15/2022

PNP 2024-027, Supplement to License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations

Contents

Text

Reference:

Subject:

Enclosure:

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