PNP 2014-088, Report to NRC of Changes to Technical Specifications Bases

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Report to NRC of Changes to Technical Specifications Bases
ML14260A013
Person / Time
Site: Palisades Entergy icon.png
Issue date: 09/15/2014
From: Hardy J
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
PNP 2014-088
Download: ML14260A013 (31)
v • d • e


Text

~ Entergy Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant 27780 Blue Star Memorial Highway Ml 49043-9530 Covert, MI Tel 269 764 2000 Jeffery A. Hardy JefferyA.

Regulatory Assurance Manager 201 4-088 PNP 2014-088 September 15, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Report to NRC of Changes to Technical Specifications Bases Palisades Nuclear Plant Docket 50-255 License No. DPR-20

Dear Sir or Madam:

This report is submitted in accordance with Palisades Technical Specification 5.5.12.d, which requires that changes to the Technical Specifications Bases, implemented without prior Nuclear Regulatory Commission (NRC) approval, be provided to the NRC on a frequency consistent with 10 CFR 50.71 (e). Attachment 1 1 provides a listing of all bases changes since issuance of the previous report, dated November 9, 2012, and identifies the affected sections and describes the nature of the changes. Attachment 2 provides page change instructions, and copies of the revised Technical Specifications Bases Title Page, List of Effective Pages, and Technical Specifications Bases sections listed in Attachment 1 1..

Summary of Commitments This letter identifies no new commitments and no revisions to existing commitments.

Sincerely,

/1A jah/jse Attachments: 1. List of Technical Specifications Bases Changes

2. Revised Technical Specifications Bases cc: Ill, USNRC Administrator, Region III, Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC

ATTACHMENT 11 LIST OF TECHNICAL SPECIFICATIONS BASES CHANGES Date Affected Bases Change Description 13, 2013 June 13,2013 Section B 3.0 Revised to implement license amendment number 251 251,, which added Technical Specification LCD 3.0.8 concerning requirements for inoperable snubbers (NRC Safety Evaluation 29, 2013, ADAMS dated March 29,2013, Accession Number ML113064A140).

ML 3064A1 40).

September 15, 2014 Section B 3.7.16 Revised to align with configuration of spent fuel pool following installation of new spent fuel pool racks per license amendment number 250 (NRC Safety Evaluation dated February 28, 2013, ADAMS Accession Number ML113056A514).

ML 3056A51 4).

Page 11 of 1 1

ATTACHMENT 2 REVISED TECHNICAL SPECIFICATIONS BASES Page Change Instructions Title Page List of Effective Pages Technical Specification Bases Section B 3.0 Section B 3.7.16 28 Pages Follow

PALISADES NUCLEAR PALISADES NUCLEAR PLANT PLANT Technical Technical Specifications Specifications Bases Bases September September 15, 15, 2014 2014 Revise your Revise your copy copy of the Palisades of the Palisades Nuclear Nuclear Plant Plant Technical Technical Specifications Specifications BasesBases byby removing removing the pages the pages identified identified below below and and inserting inserting the the revised revised pages.

pages. Vertical Vertical lines lines inin the the margin margin indicate indicate the area of change.

the area of change.

LIST TECHNICAL LIST TECHNICAL SPECIFICATION SPECIFICATION BASES BASES PAGESPAGES REMOVE REMOVE INSERT INSERT Technical Specification Technical Specification Bases Bases Technical Specification Technical Specification Bases Bases Title Page Title Page Title Page Title Page Revised 11/08/2012 Revised 11/08/2012 (1(1 page) page) Revised 09/15/2014 Revised 09/15/2014 (1(1 page)page)

Palisades Tech Palisades Tech Spec Spec Bases Bases Palisades Tech Palisades Tech Spec Spec Bases Bases List of List of Effective Effective Pages Pages List of List of Effective Effective Pages Pages Revised 11/08/2012 Revised 11/08/2012 (3 (3 pages) pages) Revised 09/15/2014 Revised 09/15/2014 (3 (3 pages) pages)

BB 3.0-1 through BB 3.0-16 3.0-1 through 3.0-16 BB 3.0-1 3.0-1 through through BB 3.0-18 3.0-18 Revised 02/24/2005 Revised 02/24/2005 (16 (16 pages) pages) Revised 06/13/2013 Revised 06/13/2013 (18 (18 pages) pages)

BB 3.7.16-1 3.7.16-1 through through BB 3.7.16-5 3.7.16-5 BB 3.7.16-1 3.7.16-1 through through BB 3.7.16-5 3.7.16-5 Amendment 246 Amendment 246 (5(5 pages) pages) Amendment 250 Amendment 250 (5(5 pages) pages)

PALISADES PLANT FACILITY OPERATING LICENSE DPR-20 APPENDIX A TECHNICAL SPECIFICATIONS BASES Revised 09/15/2014

PALISADES TECHNICAL PALISADES TECHNICAL SPECIFICATIONS SPECIFICATIONS BASES BASES 1 LIST LIST OF OF EFFECTIVE EFFECTIVE PAGES PAGES COVERSHEET COVERSHEET Title Page Title Page 250 - Revised 250 - Revised 09/15/14 09/15/14 TABLE OF TABLE OF CONTENTS CONTENTS Pages ii and Pages and iiii Revised 02/19/09 Revised 02/19/09 TECHNICAL SPECIFICATIONS TECHNICAL SPECIFICATIONS BASES BASES Bases2.0 Bases 2.0 Pages BB2.1.1-1 Pages 2.1.1-1 --B2.1.1-4 B 2.1.1-4 Revised 04/14/11 Revised 04/14/11 Pages BB 2.1.2-1 Pages 2.1.2 BB 2.1.2-4

- 2.1.2-4 189 189 Bases 3.0 Bases 3.0 Pages BB 3.0-1 Pages 3.0 BB 3.0-18

- 3.0-18 251 - Revised 251 - Revised 06/13/13 06/13/13 Bases3.1 Bases 3.1 Pages Pages BB3.1.1-1 3.1.1-1 --B 3.1.1-5 B 3.1.1-5 189 189 Pages Pages BB 3.1 3.1.2-1 - 3.1.2-6

.2 BB 3.1.2-6 Revised 09/09/03 Revised 09/09/03 Pages Pages BB 3.1 3.1.3-1

.3 BB 3.1.3-4

- 3.1.3-4 189 189 Pages Pages BB3.1.4-1 3.1.4-1 --B3.1.4-13 B 3.1.4-13 Revised 07/18/07 Revised 07/18/07 Pages Pages B 3.1.5-1 -B3.1.5-7 B 3.1.5 B 3.1.5-7 Revised 07102/04 Revised 07/02/04 Pages Pages BB3.1.6-1 3.1.6-1 --B3.1.6-9 B 3.1.6-9 Revised 07/30103 Revised 07/30/03 Pages Pages BB 3.1.7-1 3.1.7 BB 3.1.7-6

- 3.1.7-6 Revised 05/15/07 Revised 05/15/07 Bases3.2 Bases 3.2 Pages Pages BB3.2.1-1 3.2.1-1 --B3.2.1-11 B 3.2.1-11 Revised 08/06/04 Revised 08/06/04 Pages Pages BB 3.2.2-1 3.2.2-1 - BB 3.2.2-3

- 3.2.2-3 Revised 09/28/01 Revised 09/28/01 Pages Pages 3.2.3-1 BB 3.2.3-1 - BB 3.2.3-3

- 3.2.3-3 Revised 09/28/01 Revised 09/28/01 Pages Pages BB 3.2.4-1 3.2.4-1 - BB 3.2.4-3

- 3.2.4-3 189 - Revised 189 - Revised 08/09/00 08/09/00 Bases 3.3 Bases 3.3 Pages Pages BB 3.3.1-1 3.3.1 BB 3.3.1-35

- 3.3.1-35 Revised 08/30/2011 Revised 08/30/2011 Pages Pages BB 3.3.2-1 3.3.2 BB 3.3.2-10

- 3.3.2-10 189 - Revised 189 - Revised 02/12/01 02/12/01 Pages Pages BB 3.3.3-1 3.3.3 BB 3.3.3-24

- 3.3.3-24 Revised 03/20108 Revised 03/20/08 Pages Pages BB 3.3.4-1 - 3.3.4-12 3.3.4 BB 3.3.4-12 Revised 09/09/03 Revised 09/09/03 Pages Pages BB 3.3.5-1 3.3.5 BB 3.3.5-6

- 3.3.5-6 Revised 11/08/2012 Revised 11/08/2012 Pages Pages 3.3.6 BB 3.3.6-6 BB 3.3.6-1 - 3.3.6-6 Revised 02/12/01 189 - Revised 189 - 02/12/01 Pages Pages BB 3.3.7-1 - 3.3.7-12 3.3.7 BB 3.3.7-12 Revised 11/08/2012 Revised 11/08/2012 Pages Pages B 3.3.8-1 B B 3.3.8 B 3.3.8-6

- 3.3.8-6 Revised 02/24/05 Revised 02/24/05 Pages Pages BB 3.3.9-1 3.3.9 BB 3.3.9-5

- 3.3.9-5 189 - Revised 189 - Revised 08/09/00 08/09/00 Pages Pages BB3.3.10-1 3.3.10-1 --B3.3.10-4 B 3.3.10-4 189 189 Bases 3.4 Bases 3.4 Pages Pages BB 3.4.1-1 3.4.1 BB 3.4.1-4

- 3.4.1-4 Revised 08/24/04 Revised 08/24/04 Pages Pages BB 3.4.2-1 3.4.2 BB 3.4.2-2

- 3.4.2-2 189 189 Pages Pages BB 3.4.3-1 3.4.3 BB 3.4.3-7

- 3.4.3-7 Revised 02/17/12 Revised 02/17/12 Pages Pages BB 3.4.4-1 3.4.4 BB 3.4.4-4

- 3.4.4-4 Revised 09/21/06 Revised 09/21/06 Pages Pages B 3.4.5 BB 3.4.5-5 B 3.4.5-1 - 3.4.5-5 Revised 09/21/06 Revised 09/21/06 Pages Pages BB 3.4.6-1 3.4.6 BB 3.4.6-6

- 3.4.6-6 Revised 07/31/07 Revised 07/31/07 Pages Pages BB 3.4.7-1 3.4.7 BB 3.4.7-7

- 3.4.7-7 Revised 07/31/07 Revised 07/31/07 Pages Pages 3.4.8 BB 3.4.8-5 BB 3.4.8-1 - 3.4.8-5 Revised 07/31/07 Revised 07/31/07 Pages Pages 3.4.9 BB 3.4.9-6 BB 3.4.9-1 - 3.4.9-6 189 189 Pages Pages BB 3.4.10-1 3.4.10-1 --B3.4.10-4 B 3.4.10-4 189 189 Pages Pages B 3.4.11-1 B 3.4.11 B - B 3.4.11-7 3.4.11-7 Revised 02/24/05 Revised 02/24/05 Revised 09/15/2014 Revised 09/15/2014

PALISADES TECHNICAL PALISADES TECHNICAL SPECIFICATIONS SPECIFICATIONS BASES BASES 22 LIST OF LIST OF EFFECTIVE EFFECTIVE PAGESPAGES Bases 3.4 Bases 3.4 Pages Pages BB 3.4.12-1 3.4.12 - BB 3.4.12-13 3.4.12-13 Revised 02/17/12 Revised 02/17/12 (Continues)

(Continues) Pages Pages BB 3.4.13-1 3.4.13 - BB 3.4.13-7 3.4.13-7 Revised 03/20/08 Revised 03/20/08 Pages Pages BB 3.4.14-1 3.4.14 - BB 3.4.14-8 3.4.14-8 189 - Revised 189 - Revised 08/09/00 08/09/00 Pages Pages B 3.4.15 B 3.4.15-1 - B 3.4.15-6 B 3.4.15-6 Revised 02/24/05 Revised 02/24/05 Pages Pages BB 3.4.16-1 3.4.16 - BB 3.4.16-5 3.4.16-5 Revised 02/24/05 Revised 02/24/05 Pages Pages BB 3.4.17-1 3.4.17 - BB 3.4.17-7 3.4.17-7 223 223 Bases3.5 Bases 3.5 Pages Pages BB 3.5.1-1 3.5.1-1 --B3.5.1-5 B 3.5.1-5 189 189 Page Page BB 3.5.1-6 3.5.1-6 191 191 Page Page BB 3.5.1-7 3.5.1-7 189 189 Page Page BB 3.5.1-8 3.5.1-8 191 191 Pages Pages BB 3.5.2-1 3.5.2 BB 3.5.2-12

- 3.5.2-12 228 228 Pages Pages BB 3.5.3-1 3.5.3 BB 3.5.3-4

- 3.5.3-4 Revised 07/22/02 Revised 07/22/02 Pages Pages B 3.5.4 BB 3.5.4-7 83.5.4-1 - 3.5.4-7 227 227 Pages Pages 3.5.5 BB 3.5.5-5 BB 3.5.5-1 - 3.5.5-5 227 227 Bases 3.6 Bases 3.6 Pages Pages BB 3.6.1-1 3.6.1-1 -- BB 3.6.1-4 3.6.1-4 Revised 03/15/12 Revised 03/15/12 Pages Pages B 3.6.2-1 B 3.6.2-1 -- B 3.6.2-8 B 3.6.2-8 Revised 03/15/12 Revised 03/15/12 Pages Pages BB 3.6.3-1 3.6.3-1 -- BB 3.6.3-12 3.6.3-12 Revised 04/14/11 Revised 04/14/11 Pages Pages BB 3.6.4-1 3.6.4-1 -- B 3.6.4-3 83.6.4-3 Revised 03/15/12 Revised 03/15/12 Pages Pages BB 3.6.5-1 3.6.5-1 -- BB 3.6.5-3 3.6.5-3 Revised 03/15/12 Revised 03/15/12 Pages Pages BB 3.6.6-1 3.6.6-1 -- BB 3.6.6-13 3.6.6-13 Revised 03/15/12 Revised 03/15/12 Bases 3.7 Bases 3.7 Pages Pages BB 3.7.1-1 3.7.1 BB 3.7.1-4

- 3.7.1-4 Revised 08/06/04 Revised 08/06/04 Pages Pages BB 3.7.2-1 - 3.7.2-6 3.7.2 BB 3.7.2-6 Revised 12/02/02 Revised 12/02/02 Pages Pages B 3.7.3 83.7.3-5 83.7.3-1 - B 3.7.3-5 12102/02 Revised 12/02/02 Revised Pages Pages BB 3.7.4-1 3.7.4 BB 3.7.4-4

- 3.7.4-4 Revised 07/16/08 Revised 07/16/08 Pages Pages BB 3.7.5-1 3.7.5 BB 3.7.5-9

- 3.7.5-9 Revised 02/24/05 Revised 02/24/05 Pages Pages BB 3.7.6-1 3.7.6 BB 3.7.6-4

- 3.7.6-4 Revised 04/14/11 Revised 04/14/11 Pages Pages BB 3.7.7-1 3.7.7 BB 3.7.7-9

- 3.7.7-9 Revised 06/07/05 Revised 06/07/05 Pages Pages BB 3.7.8-1 3.7.8 BB 3.7.8-8

- 3.7.8-8 Revised 10/29/09 Revised 10/29/09 Pages Pages BB 3.7.9-1 3.7.9 BB 3.7.9-3

- 3.7.9-3 Revised Revised 04/14/11 04/14/1 1 Pages Pages BB 3.7.10-1 3.7.10 B- 3.7.10-8 B 3.7.10-8 230 230 Pages Pages BB3.7.11-1 3.7.11-1 --B3.7.11-5 B 3.7.11-5 189 189 Pages Pages BB 3.7.12-1 3.7.12 B- B 3.7.12-7 3.7.12-7 Revised Revised 07/16/03 07/16/03 Pages Pages BB 3.7.13-1 3.7.13 8B 3.7.13-3

- 3.7.13-3 189 - Revised 189 - Revised 08/09/00 08/09/00 Pages Pages BB 3.7.14-1 3.7.14 BB 3.7.14-3

- 3.7.14-3 Revised 09/09/03 Revised 09/09/03 Pages Pages BB 3.7.15-1 3.7.15 B- B 3.7.15-2 3.7.15-2 236 236 Pages Pages B 3.7.16 B 83.7.16-1 - B 3.7.16-5 3.7.16-5 250 250 - Revised

- Revised 09/15/14 09/15/14 Pages Pages BB 3.7.17-1 3.7.17 B- B 3.7.17-3 3.7.17-3 Revised 04/14/11 Revised 04/14/11 Revised 09/15/2014

PALISADES TECHNICAL PALISADES TECHNICAL SPECIFICATIONS BASES SPECIFICATIONS BASES 33 LIST OF LIST EFFECTIVE PAGES OF EFFECTIVE PAGES Bases 3.8 Bases 3.8 Pages Pages BB 3.8.1-1 3.8.1 BB 3.8.1-24

- 3.8.1-24 Revised 11/08/12 Revised 11/08/12 Pages Pages BB 3.8.2-1 - 3.8.2-4 3.8.2 BB 3.8.2-4 Revised 11/06/01 Revised 11/06/01 Pages Pages BB 3.8.3-1 3.8.3-7 3.8.3 BB 3.8.3-7

- 09/16/1 1 Revised 09/16/11 Revised Pages Pages BB 3.8.4-1 - 3.8.4-9 3.8.4 BB 3.8.4-9 Revised 07/13/06 Revised 07/13/06 Pages Pages BB 3.8.5-1 3.8.5 BB 3.8.5-3

- 3.8.5-3 Revised 11/06/01 Revised 11/06/01 Pages Pages BB 3.8.6-1 3.8.6-6 3.8.6 BB 3.8.6-6

- 189 Revised 08/09/00 189 - Revised 08/09/00 Pages Pages BB 3.8.7-1 - 3.8.7-3 3.8.7 BB 3.8.7-3 189 189 Pages Pages BB 3.8.8-1 3.8.8 BB 3.8.8-3

- 3.8.8-3 Revised 11/06/01 Revised 11/06/01 Pages Pages BB 3.8.9-1 3.8.9-7 3.8.9 BB 3.8.9-7

- Revised 11/06/01 Revised 11/06/01 Pages Pages 3.8.10 BB 3.8.10-3 BB 3.8.10-1 - 3.8.10-3 Revised 11/06/01 Revised 11/06/01 Bases 3.9 Bases 3.9 Pages Pages BB 3.9.1-1 3.9.1-1 - BB 3.9.1-4

- 3.9.1-4 189 - Revised 189 - 08/09/00 Revised 08/09/00 Pages Pages BB 3.9.2-1 3.9.2-1 3.9.2-3

- BB 3.9.2-3

- 189 - Revised 189 - 02/12/01 Revised 02/12/01 Pages Pages B 3.9.3-1 B 3.9.3-1 B 3.9.3-6

- B 3.9.3-6

- Revised 08/09/00 189 - Revised 08/09/00 189 -

Pages Pages BB 3.9.4-1 3.9.4-1 3.9.4-4

- BB 3.9.4-4

- 07/31/07 Revised 07/31/07 Revised Pages Pages BB 3.9.5-1 3.9.5-1 3.9.5-4

- BB 3.9.5-4

- Revised 07/31/07 Revised 07/31/07 Pages Pages BB 3.9.6-1 3.9.6-1 - BB 3.9.6-3

- 3.9.6-3 189 - Revised 189 - Revised 02/27/01 02/27/01 09/15/2014 Revised 09/15/2014 Revised

LCD Applicability LCO B3.0 B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY BASES LCD LCO LCD 3.0.1 through LCO LCO LCD 3.0.8 establish the general requirements applicable to all Specifications and apply at all times unless otherwise stated.

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

Applicability statement of each Specification).

LCD 3.0.2 LCO 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 establish those remedial measures that must be taken within specified Completion Times when the requirements of an LCO LCD are not met. This Specification establishes that:

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

There are two basic types of Required Actions. The first type of Required Action specifies a time limit in which the LCO LCD must be met. This time limit is the Completion Time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits.

If this type of Required Action is not completed within the specified Completion Time, a shutdown may be required to place the plant in a MODE or condition in which the Specification is not applicable. (Whether stated as a Required Action or not, correction of the entered Condition is an action that may may always be considered upon upon entering ACTIONS.)

Palisades Nuclear Nuclear Plant B B 3.0-1 Revised 06/13/2013 06/13/2013

LCO LCO Applicability Applicability BB 3.0 3.0 BASES BASES LCO 3.0.2 LCO 3.0.2 The second The second type of Required type of Required Action specifies specifies the the remedial remedial measures measures that that (continued)

(continued) permit continued operation of permit continued operation of the plant that the plant that is is not not further further restricted restricted by by the the Completion Time.

Completion Time. InIn this case, case, compliance compliance with the Required Required Actions Actions provides an provides an acceptable acceptable levellevel of of safety safety for continued continued operation.

operation.

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

The nature of some Required Actions of some Conditions necessitates that, once the Condition is entered, the Required Actions must be completed even though the associated Conditions no longer exist. The LCOs ACTIONS specify the Required Actions where this is the individual LCO's case. An example of this is in LCO 3.4.3, "PCS PCS Pressure and Temperature (PfT)(PIT) Limits."

Limits.

The Completion Times of the Required Actions are also applicable when a system or component is removed from service intentionally. The reasons for intentionally relying on the ACTIONS include, but are not limited to, performance of Surveillances, preventive maintenance, corrective maintenance, or investigation of operational problems.

Entering ACTIONS for these reasons must be done in a manner that does not compromise safety. Intentional entry into ACTIONS should not be made for operational convenience. Additionally, if intentional entry into ACTIONS would result in redundant equipment being inoperable, alternatives should be used instead. Doing so limits the time both subsystems/trains of a safety function are inoperable and limits the time conditions exist which may result in LCO 3.0.3 being entered. Individual Specifications may specify a time limit for performing an SR when equipment is removed from service or bypassed for testing. In this case, the Completion Times of the Required Actions are applicable when this time limit expires, if the equipment remains removed from service or bypassed.

When a change in in MODE or otherother specified condition is is required to comply with Required Actions, the plant may enter a MODE plant may MODE or other other specified specified condition in which which another Specification becomes applicable.

In In this case, case, the the Completion Times Times of of the the associated associated Required Required Actions Actions would apply from the the point pOint in in time that that the the new new Specification becomes applicable and and the ACTIONS ACTIONS Condition(s) are are entered.

entered.

Palisades Palisades Nuclear Nuclear Plant Plant BB 3.0-2 3.0-2 Revised Revised 06/13/2013 06/13/2013

LCO Applicability LCO Applicability B

B 3.0 3.0 BASES BASES LCO 3.0.3 LCO 3.0.3 LCO 3.0.3 LCO 3.0.3 establishes establishes the the actions actions that that must must be be implemented implemented when when an an LCO is LCO is not not met and:

met and:

a.

a. associated Required An associated Required Action and Completion Time is and Completion is not not met met and no and no other Condition Condition applies; applies; or or b.
b. plant is not specifically addressed by the The condition of the plant associated ACTIONS. This means that no no combination of Conditions stated in the ACTIONS can be made that exactly corresponds to the actual condition of the plant. Sometimes, possible combinations of Conditions are such that entering LCO 3.0.3 is warranted; in such cases, the ACTIONS specifically state a Condition corresponding to such combinations and also that LCO 3.0.3 be entered immediately.

This Specification delineates the time limits for placing the plant in a safe MODE or other specified condition when operation cannot be maintained within the limits for safe operation as defined by the LCO and its ACTIONS. It is not intended to be used as an operational convenience that permits routine voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

Upon entering LCO 3.0.3, 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is allowed to prepare for an orderly shutdown before initiating a change in plant operation. This includes time to permit the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the capabilities of the plant, plant, assuming that only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the Primary Coolant System and the potential for a plant upset that that could challenge safety systems systems under conditions toto which which this this Specification applies. The use use and interpretation of specified times to complete the actions of LCO 3.0.3 are consistent with the discussion of Section Section 11.3,

.3, Completion Times.

Palisades Palisades Nuclear Nuclear Plant Plant BB 3.0-3 3.0-3 Revised 06/13/2013 Revised 06/13/2013

LCO LCO Applicability Applicability BB 3.0 3.0 BASES BASES LCO 3.0.3 LCO 3.0.3 plant shutdown A plant shutdown required required in accordance with LCO in accordance LCO 3.0.3 3.0.3 may may bebe (continued)

(continued) terminated and terminated LCO 3.0.3 and LCO 3.0.3 exited exited ifif any any of following occurs:

of the following occurs:

a.

a. LCO is The LCO is now now met.

met.

b.

b. exists for which the Required A Condition exists Required Actions have have now been been performed.
c. ACTIONS exist that do not have expired Completion Times. These applicable from the point in time that the Completion Times are applicable Condition is initially entered and not from the time LCO 3.0.3 is exited.

The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in MODE 5 when a shutdown is required during MODE 11 operation. If the plant is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE applies. If a lower MODE is reached in less time than allowed, however, the total allowable time to reach MODE 5, or other applicable MODE, is not reduced. For example, if MODE 3 is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then the time allowed for reaching MODE 4 is the next 29 hours3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br />, because the total time for reaching MODE 4 is not reduced from the allowable limit of 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br />. Therefore, if remedial measures are completed that would permit a return to MODE 1, 1, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

In MODES 1, 1, 2, 3, and 4, LCO 3.0.3 provides actions for Conditions not covered in other Specifications. The requirements of LCO 3.0.3 do not apply in MODES 5 and 6 because the plant is already in the most restrictive Condition required by LCO 3.0.3.

The requirements of LCO 3.0.3 do not apply in other specified conditions of the Applicability (unless in MODE 1, 1, 2, 3, or 4) because the ACTIONS of individual individual Specifications Specifications sufficiently definedefine the remedial measures measures to bebe taken. Exceptions Exceptions to LCO 3.0.3 are provided in instances instances where requiring a plant plant shutdown, shutdown, in accordance with LCO LCO 3.0.3, would not not provide provide appropriate appropriate remedial measures measures for the associated associated condition of the plant.

plant.

An An example of of this is is in in LCO LCO 3.7.14, "Spent Fuel 3.7.14, Spent Fuel Pool Pool Water Water Level.

LeveL" Palisades Palisades Nuclear Nuclear Plant Plant BB 3.0-4 3.0-4 Revised Revised 06/13/2013 06/13/2013

LCO LCD Applicability Applicability B 3.0 B3.0 BASES BASES LCD 3.0.3 LCO 3.0.3 LCO 3.7.14 has LCD 3.7.14 an Applicability has an Applicability of of IIDu During movement of ring movement of irradiated irradiated fuelfuel

((continued) continued) assemblies in assemblies in the spent spent fuel fuel pool.lI pool. Therefore, Therefore, thisthis LCO can be applicable LCO can be applicable in any in any or all MODES.

MODES. IfIf the LCO LCD and the Required Actions of the Required of LCO LCO 3.7.14 3.7.14 are not are not met while in MODE while in MODE 1, 1, 2, or or 3, there is 3, there is no no safety benefit benefit to to be be gained by gained by placing the plant in aa shutdown condition.

plant in condition. The The Required Required Action 3.7.14 of "Suspend of LCO 3.7.14 Suspend movement movement of irradiated irradiated fuel assemblies assemblies in pool is the appropriate Required spent fuel pooll! Required Action to complete complete in in lieu lieu of of the actions of LCO LCD 3.0.3. These exceptions are are addressed in in the individual Specifications.

LCO 3.0.4 LCD 3.0.4 establishes limitations on changes in MODES or other LCO specified conditions in the Applicability when an LCO is not met. It allows placing the plant in a MODE or other specified condition stated in that Applicability (e.g., the Applicability desired to be entered) when plant conditions are such that the requirements of the LCO LCD would not be met, in accordance with LCO 3.0.4.a, LCO 3.0.4.b, or LCO LCD 3.0.4.c.

LCD 3.0.4.a allows entry into a MODE or other specified condition in the LCO Applicability with the LCO not met when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. Compliance with Required Actions that permit continued operation of the plant for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the plant before or after the MODE change.

Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Actions.

LCD LCO 3.0.4.b allows entry into a MODE or other specified condition in the Applicability with the LCD LCO not met after performance of a risk assessment addressing inoperable inoperable systems and components, consideration of the results, determination determination of the the acceptability of entering entering thethe MODE MODE or other other specified specified condition in in the Applicability, and establishment of of risk management actions, if appropriate.

The The risk assessment assessment may may useuse quantitative, quantitative, qualitative, qualitative, oror blended blended approaches, approaches, and and the risk assessment assessment will be be conducted using using the plant plant program, program, procedures, and and criteria in in place place to implement 10 10 CFR5O.65(a)(4),

CFR50.65(a)(4), which requires that that risk impacts impacts of of maintenance maintenance activities to be assessed and activities to be assessed and managed. managed. The The risk risk assessment, assessment, for for purposes purposes of LCO 3.0.4.b, of LCO 3.0.4.b, must must take into account take into account allall inoperable inoperable Technical Specification Specification equipment equipment regardless regardless of of whether whether the the equipment equipment is is included included in the normal in the normal 10 10 CFR CFR 50.65(a)(4) 50.65(a)(4) riskrisk assessment assessment scope.scope.

Palisades Palisades Nuclear Nuclear Plant Plant BB 3.0-5 3.0-5 Revised Revised 06/13/2013 06/13/2013

LCO Applicability LCO Applicability B

B 3.0 3.0 BASES BASES LCO 3.0.4 LCO 3.0.4 The risk The risk assessments assessments will will be be conducted conducted using using the the procedures procedures and and (continued)

(continued) guidance endorsed guidance endorsed by Regulatory Regulatory Guide Guide 1.182, 1.182, "Assessing Assessing and and Managing Risk Managing Risk Before Before Maintenance Maintenance Activities Activities at at Nuclear Nuclear Power Power Plants."

Plants.

Regulatory Guide Regulatory Guide 1.182 1.182 endorses endorses the the guidance guidance in in Section Section 11 11 of of NUMARC 93-01, NUMARC 93-01, "Industry Industry Guideline Guideline for for Monitoring Monitoring the the Effectiveness Effectiveness ofof Maintenance at Maintenance Nuclear Power at Nuclear Power Plants."

Plants. These These documents documents address address general guidance for conduct of the risk risk assessment, quantitative and management actions, and qualitative guidelines for establishing risk management example risk management actions. These include include actions to plan and conduct other activities in a manner that controls overall risk, increased risk awareness by shift and management personnel, actions to reduce the duration of the condition, actions to minimize the magnitude of risk increases (establishment of backup success paths or compensatory measures), and determination that the proposed MODE change is acceptable. Consideration should also be given to the probability of completing restoration such that the requirements of the LCO would be met prior to the expiration of ACTIONS Completion Times that would require exiting the Applicability.

LCO 3.0.4.b may be used with single, or multiple systems and components unavailable. NUMARC 93-01 provides guidance relative to consideration of simultaneous unavailability of multiple systems and components.

The results of the risk assessment shall be considered in determining the acceptability of entering the MODE or other specified condition in the Applicability, and any corresponding risk management actions. The LCO 3.0.4.b risk assessments do not have to be documented.

The Technical Specifications allow continued operation with equipment unavailable in in MODE 11 for the duration of the Completion Time. Since this is allowable, and since in general the risk impact in that particular MODE bounds the risk of transitioning into and through the applicable MODES MODES or other specified conditions in in the Applicability of the LCO, LCO, the use of the LCO use LCO 3.0.4.b allowance should be generally acceptable, as long as the risk isis assessed assessed and managed as stated above. However, there is is a small small subset of of systems and components that have been determined to have been be more be more important important toto risk and and use use of of the the LCO LCO 3.0.4.b 3.0.4.b allowance allowance isis prohibited. The LCOs LCOs governing these systemsystem and and components contain Notes prohibiting Notes prohibiting the use use ofof LCO LCO 3.0.4.b 3.0.4.b byby stating that that LCO LCO 3.0.4.b 3.0.4.b is is not not applicable.

applicable.

Palisades Palisades Nuclear Nuclear Plant Plant BB 3.0-6 3.0-6 Revised Revised 06/13/2013 06/13/2013

LCO LCO Applicability Applicability BB 3.0 3.0 BASES BASES LCO 3.0.4 LCO 3.0.4 LCO 3.0.4.c allows LCO 3.0.4.c allows entry entry into into aa MODE MODE or or other other specified specified condition condition in in the the

((continued) continued) Applicability with the Applicability the LCO LCO not not met met based based on on aa Note Note in in the the Specification Specification which states LCOLCO 3.0.4.c is is applicable. These These specific allowances allowances permit permit into MODES entry into MODES or or other other specified specified conditions conditions inin the the Applicability Applicability when associated ACTIONS to the associated to be be entered entered dodo not provide for continued not provide continued operation for an operation unlimited period an unlimited period of time time and a risk risk assessment has has not not been performed. This allowance may may apply to all the ACTIONS or to a specific Required Action of a Specification. The risk assessments performed to justify the use of LCO LCO 3.0.4.b usually only consider systems and components. For this reason, LCO 3.0.4.c is typically applied to Specifications which describe values and parameters (e.g., primary coolant system specific activity), and may be applied to other Specifications based on NRC plant-specific approval.

The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

The provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any plant shutdown. In this context, a plant shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

Upon entry into a MODE or other specified condition in the Applicability with the LCO not met, LCO 3.0.1 and 3.0.2 require entry into the applicable applicable Conditions and Required Actions until until the Condition is is resolved, until the LCO is met, or until the plant is not within the Applicability of the Technical Specification.

Surveillances do do not have have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by by SR 3.0.1. Therefore, utilizing utilizing LCO 3.0.4 is is not a violation of of SR 3.0.1 3.0.1 or SR 3.0.4 SR 3.0.4 for any Surveillances that for any that have have not not been been performed performed on on inoperable inoperable equipment.

equipment. However, However, SR5 SRs must must bebe met met toto ensure ensure OPERABILITY prior prior to declaring the associated equipment equipment OPERABLE OPERABLE (or (or variable within within limits) and restoring compliance limits) and compliance with with the the affected affected LCO.

LCO.

Palisades Palisades Nuclear Nuclear Plant Plant BB 3.0-7 3.0-7 Revised 06/13/2013 Revised 06/13/2013

LCO LCO Applicability Applicability B

B 3.0 3.0 BASES BASES LCO 3.0.5 LCO 3.0.5 LCO 3.0.5 LCO 3.0.5 establishes establishes the allowance for the allowance for restoring restoring equipment equipment to to service service under administrative controls under administrative controls when when it has been been removed removed from service service or or declared inoperable declared inoperable to comply comply with with ACTIONS.

ACTIONS. The The sole purpose purpose of of this this Specification isis to to provide provide an exception exception to LCO 3.0.2 to LCO 3.0.2 (e.g.,

(e.g., to to not not comply comply with the applicable applicable Required Required Action(s)) to allow the performance performance of of required testing to demonstrate:

required demonstrate:

a. OPERABILITY of the equipment being returned The OPERABILITY returned to service; or
b. The OPERABILITY of other equipment.

The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the required testing to demonstrate OPERABILITY. This Specification does not provide time to perform any other preventive or corrective maintenance.

An example of demonstrating the OPERABILITY of the equipment being returned to service is reopening a containment isolation valve that has been closed to comply with Required Actions and must be reopened to perform the required testing.

An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of required testing on another channel in the other trip system. A similar example of demonstrating the OPERABILITY OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of required testing on another channel in the same trip system.

LCO 3.0.6 3.0.6 LCO 3.0.6 3.0.6 establishes establishes an an exception exception to LCOLCO 3.0.2 3.0.2 for supported systems that have have a support support system system LCO specified in in the Technical Specifications (TS). This exception exception is provided because LCO 3.0.2 would require that the Conditions Conditions and Required Actions of the associatedassociated inoperable supported system supported system LCO beLCO entered be entered solely due to solely due to the the inoperability of of the the support support system.

system. This exception exception isis justified justified because because the the actions actions that areare required required toto ensure the the plant plant is is maintained maintained in in aa safe safe condition areare specified in in the support system LCO's Required system LCOs Required Actions.

Actions. These These Required Required Actions may include may include entering entering the the supported supported systems system's Conditions and and Required Actions oror may may specify specify other other Required Required Actions.

Palisades Palisades Nuclear Nuclear Plant Plant BB3.0-8 3.0-8 Revised Revised 06/13/2013 06/13/2013

LCO Applicability LCO Applicability B

B 3.0 3.0 BASES BASES LCO 3.0.6 LCO 3.0.6 When aa support When support system system is is inoperable inoperable and and there there is is an an LCO LCO specified specified for itit (continued)

(continued) in the in TS, the the TS, the supported supported system(s) system(s) areare required required toto be declared inoperable be declared inoperable ifif determined determined to to be inoperable as be inoperable result of as aa result of the the support system system inoperability. However, inoperability. However, itit isis not not necessary necessary to enter intointo the supported supported systemsl Conditions systems Conditions and and Required Required Actions unless unless directed directed toto do do so so by by the the systems Required support system's Required Actions. The The potential confusion and and inconsistency of inconsistency of requirements requirements related to the entry into multiplemultiple support and supported systems systemsl LCO's LCOs Conditions and Required Required Actions are eliminated by providing all the actions that are necessary to ensure the plant is maintained in in a safe condition in the support system's systems Required Actions.

However, there are instances where a support system's systems Required Action may either direct a supported system to be declared inoperable or direct entry into Conditions and Required Actions for the supported system.

This may occur immediately or after some specified delay to perform some other Required Action. Regardless of whether it is immediate or after some delay, when a support system's systems Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

Specification 5.5.13, IISafetySafety Functions Determination Program (SFDP),II (SFDP),

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

Cross train checks to identify a loss of safety function for those support systems that support multiple and redundant safety systems are required.

The cross train check verifies that the supported systems of the redundant OPERABLE support system are OPERABLE, thereby ensuring ensuring safety function is is retained.

IfIf this evaluation determines determines that aa loss loss of of safety function exists, the appropriate appropriate Conditions Conditions and and Required Actions of the LCO LCO in in which the loss loss of safety of safety function function exists exists are are required required to to be be entered.

entered.

Palisades Palisades Nuclear Nuclear Plant Plant BB3.0-9 3.0-9 Revised Revised 06/13/2013 06/13/2013

SSR Applicability R Applicability B 3.0 B3.0 BASES BASES LCO 3.0.7 LCO 3.0.7 Special tests Special tests and and operations operations areare required required at various times at various times over over the the plant's plants life life to demonstrate to demonstrate performance performance characteristics, characteristics, to perform maintenance to perform maintenance activities, and activities, and to perform special to perform special evaluations.

evaluations. Because Because TS TS normally normally preclude these tests and preclude and operations, Special Special Test Exceptions Exceptions (STEs)

(STEs) allow specified requirements allow requirements to to be changed or be changed or suspended suspended underunder conditions. STEs controlled conditions. STEs are included included in applicable applicable sections sections ofof the the Specifications. UnlessUnless otherwise specified, specified, all all other TS requirements remain unchanged and in effect as as applicable. This will ensure that all appropriate requirements of the MODE or other specified condition not directly associated with or requiredrequired to be changed or suspended to perform the special test or operation will remain in in effect.

The Applicability of an STE LCO represents a condition not necessarily in compliance with the normal requirements of the TS. Compliance with STE LCO is optional.

A special test may be performed under either the provisions of the appropriate STE LCO or the other applicable TS requirements. If it is desired to perform the special test under the provisions of the STE LCO, the requirements of the STE LCO shall be followed. This includes the SRs specified in the STE LCO.

Some of the STE LCO require that one or more of the LCO for normal operation be met (Le., (i.e., meeting the STE LCO requires meeting the specified normal LCO). The Applicability, ACTIONS, and SRs of the specified normal LCO, however, are not required to be met in order to meet the STE LCO when it is in effect. This means that, upon failure to meet a specified normal LCO, the associated ACTIONS of the STE LCO apply, in lieu of the ACTIONS of the normal LCO. Exceptions to the above do exist. There are instances when the Applicability of the specified normal LCO must be met, met, where its ACTIONS must be be taken, where certain of its Surveillances must be performed, or where all of these requirements must be met concurrently with the requirements of the STE LCO.

Unless the SRs of the specified normal LCO are suspended or changed by the special test, those SRs SRs that that are are necessary to meetmeet the specified normal LCO must be met normal LCO must be met prior to prior to performing performing the special special test.

test. During During thethe conduct conduct of the the special test, those Surveillances Surveillances needneed not be be performed unless specified specified by the ACTIONS ACTIONS or or SRs of the STE LCO.

ACTIONS for STE STE LCOLCO provide provide appropriate appropriate remedial measures measures uponupon failure failure to to meet meet the the STE STE LCO.

LCO. Upon Upon failure to to meet meet these these ACTIONS, ACTIONS, suspend suspend the the performance performance of of the the special test and special test enter the and enter the ACTIONS ACTIONS for for all LCOs that all LCOs that are are then then notnot met.

met. Entry Entry into into LCO LCO 3.0.3 3.0.3 may may possibly possibly bebe required, required, but this determination but this determination should should not be made not be made by by considering considering onlyonly the the failure failure to to meet meet the the ACTIONS ACTIONS of of the the STE STE LCO.

LCO.

Palisades Palisades Nuclear Nuclear Plant Plant BB 3.0-10 3.0-10 Revised Revised 06/13/2013 06/13/2013

S R Applicability SR Applicability B

B 3.0 3.0 BASES BASES LCO 3.0.8 LCO 3.0.8 LCO 3.0.8 LCO 3.0.8 establishes establishes conditions conditions under under which which systems systems are are considered considered to to remain remain capable of of performing performing their their intended intended safety safety function function when when associated associated snubbers snubbers are not capable are not capable of providing providing their associated associated support support function(s).

function(s). This LCO LCQ states that states that the the supported supported system system is is not not considered considered to to be be inoperable inoperable solely solely due to one or one or more more snubbers snubbers notnot capable capable of of performing performing their their associated support support function(s). This is is appropriate appropriate because because aa limited limited length length of time is is allowed allowed for maintenance, testing, or repair maintenance, repair of one one or more snubbers snubbers not not capable of performing their associated support function(s) and appropriate compensatory measures are specified in the snubber requirements, which are located outside of the Technical Specifications (TS). The snubber requirements requirements do not meet the criteria in 1010 CFR 50.36(c)(2)(ii), and, as such, are appropriate for administrative control.

If the allowed time expires and the snubber(s) are unable to perform their associated support function(s), the affected supported system's systems LCO(s) must be declared not met and the Conditions and Required Actions entered in accordance with LCO 3.0.2.

Every time that the provisions of LCO 3.0.8 are applied it is required to confirm that at least one train (or subsystem) of systems supported by the inoperable snubbers would remain capable of performing their required safety or support functions for postulated design loads other than seismic loads. LCO 3.0.8 does not apply to non-seismic snubbers (Le., (i.e., seismic vs non-seismic), implementation of this restriction, and the associated plant configuration shall be available on a recoverable basis for NRC staff inspection. SEP-SNB-PLP-001SEP-SNB-PLP-001,, "SnubberSnubber Examination and Testing Program," Program, may be used as a reference for application of LCO 3.0.8 to site specific snubbers.

LCO 3.0.8.a applies when one or more snubbers are not capable of providing their associated support function(s) to a single train or subsystem sUbsystem of a multiple train or subsystem supported system system or to aa single train or subsystem supported system. LCO 3.0.8.a allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the snubber(s) before declaring declaring the supported system inoperable. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable based on on the low probability of a seismic event event concurrent with with an an event event that would require operation of of the supported system occurring while the snubber(s) are not not capable capable of of performing their associated support function and due due to the availability of of the redundant train of of the supported system.

system.

When applying applying LCO LCO 3.0.8.a 3.0.8.a at at least least one AFW AFW train (including (including aa minimum minimum set set of of supporting supporting equipment required for its its successful operation),

operation), or or some some alternative alternative means means of of core cooling, cooling, not not associated associated with with the the inoperable inoperable snubber(s),

snubber(s), mustmust be be available. Implementation Implementation of this restriction of this restriction and and the the associated associated plant plant configuration configuration shall be available shall be available on on aa recoverable basis for for NRC NRC staff staff inspection.

inspection.

LCO LCO 3.0.8.b 3.0.8.b applies applies when when one one oror more more snubbers snubbers areare not not capable capable of of providing providing their associated their associated support support function(s) function(s) to to more more than one train than one train or or subsystem subsystem of of aa multiple multiple train train or or subsystem subsystem supported supported system.

system. LCO LCO 3.0.8.b 3.0.8.b allows allows 1212 hours0.014 days <br />0.337 hours <br />0.002 weeks <br />4.61166e-4 months <br /> hours toto restore the snubber(s) restore the snubber(s) before before declaring declaring the the supported supported system system inoperable.

inoperable. The The 1212 Palisades Nuclear Plant Palisades Nuclear Plant BB 3.0-1 3.0-111 Revised Revised 06/13/2013 06/13/2013

SR SR Applicability Applicability B

B 3.0 3.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> Completion hour Completion Time Time is reasonable based is reasonable based on on the low probability the low probability ofof aa seismic seismic event concurrent event concurrent with with an event that an event would require that would require operation operation of the supported of the supported system occurring system occurring while while the the snubber(s) snubber(s) areare not not capable capable ofof performing performing theirtheir support function.

associated support When applying When applying LCO LCO 3.0.8.b 3.0.8.b at least least one one AFW train (including (including a minimum minimum set set of supporting equipment required supporting equipment required for its its successful operation) not not associated with inoperable snubber(s), or some alternative the inoperable alternative means means of core cooling cooling (e.g.,

(e.g., F&B, F&B, fire water system oror "aggressive aggressive secondary cooldown" cooldown using using the steam must be generators) must be available. Implementation of this restriction restriction and the plant configuration shall be available on a recoverable basis for NRC associated plant NRC staff inspection.

LCO 3.0.8 requires that risk be assessed and and managed. Industry and NRC guidance on the implementation of 10 CFR 50.65(a)(4) (the Maintenance Rule) does not address seismic risk. However, use of LCO 3.0.8 should be considered with respect to other plant maintenance activities, and integrated into the existing Maintenance Rule process to the extent possible so that maintenance on any unaffected train or subsystem is properly controlled, and emergent issues are properly addressed. The risk assessment need not be quantified, but may be a qualitative awareness of the vulnerability of systems and components when one or more snubbers are not able to perform their associated support function.

Palisades Palisades Nuclear Nuclear Plant Plant BB 3.0-12 3.0-12 Revised Revised 06/13/2013 06/13/2013

SR SR Applicability Applicability B

B 3.0 3.0 B 3.0 SURVEILLANCE B 3.0 SURVEILLANCE REQUIREMENT REQUIREMENT (SR) (SR) APPLICABILITY APPLICABILITY BASES BASES SRs SRs SR 3.0.1 through SR through SRSR 3.0.4 establish establish the general general requirements requirements applicable applicable to all Specifications and to and apply at all times, unless unless otherwise otherwise stated.

SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must must be met met during during the MODES or other specified conditions in the Applicability for which the MODES requirements of the LCO LCO apply, unlessunless otherwise specified in the individual SRs. This Specification is is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and 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. Additionally, the definitions related to instrument testing (e.g., CHANNEL CALIBRATION) specify that these tests are performed by means of any series of sequential, overlapping, or total steps.

Systems and components are assumed to be OPERABLE when the associated SRs have been met. Nothing in this Specification, however, is to be construed as implying that systems or components are OPERABLE when:

a. The systems or components are known to be inoperable, although still meeting the SRs; or
b. The requirements of the Surveillance(s) are known to be not met between required Surveillance performances.

Surveillances do not have to be performed when the plant is is in a MODE MODE or other specified condition for which the requirements of the associated LCO are are not applicable, applicable, unless unless otherwise otherwise specified. The The SRs associated with a Special Test Exception (STE) (STE) are onlyonly applicable when the STE is is used as as anan allowable exception to the requirements of of aa Specification.

Unplanned Unplanned events events may may satisfy satisfy thethe requirements (including (including applicable applicable acceptance acceptance criteria) for aa given given SR.SR. InIn this this case, case, the unplanned unplanned event may may be be credited credited asas fulfilling the performance performance of of the the SR.

SR. This This allowance allowance includes includes thosethose SRsSRs whose performance is whose performance is normally normally precluded precluded in in aa given given MODE MODE or or other other specified specified condition.

condition.

Surveillances, Surveillances, including including Surveillances Surveillances invoked invoked by by Required Actions, Actions, dodo not have not have to be performed to be performed on on inoperable inoperable equipment equipment because because the the ACTIONS ACTIONS define define the the remedial remedial measures measures that that apply.

apply. Surveillances Surveillances havehave to to bebe met met andand performed performed in in accordance accordance with with SR 3.0.2, prior SR 3.0.2, prior to to returning returning equipment equipment to to OPERABLE OPERABLE status. status.

Palisades Palisades Nuclear Nuclear Plant Plant BB 3.0-13 3.0-13 06/13/2013 Revised 06/13/2013 Revised

SR SR Applicability Applicability B

B 3.0 3.0 BASES BASES SR 3.0.1 SR 3.0.1 Upon completion of Upon completion of maintenance, maintenance, appropriate appropriate post post maintenance maintenance testing testing (continued)

(continued) is required is declare equipment required to declare equipment OPERABLE.

OPERABLE. This This includes includes ensuring applicable Surveillances applicable Surveillances are are not not failed and their most and their most recent recent performance performance is in accordance is accordance with SR 3.0.2. Post Post maintenance maintenance testing may may not not be possible in the current MODE possible MODE or other other specified conditions in in the Applicability due to to the necessary plant parameters not having been been established. In these situations, the equipment may established. may bebe considered considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.

An example of this process is:

a. High Pressure Safety Injection (HPSI) maintenance during shutdown that requires system functional tests at a specified pressure. Provided other appropriate testing is satisfactorily completed, startup can proceed with HPSI considered OPERABLE.

This allows operation to reach the specified pressure to complete the necessary post maintenance testing.

SR 3.0.2 SR 3.0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a once "once per.

per ... interval.

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

activities).

The The 25% 25% extension extension does not not significantly Significantly degrade degrade the reliability that results from performing the Surveillance at at its specified specified Frequency. This is is based based on on the the recognition recognition that that the most most probable result of probable result of any any particular particular Surveillance Surveillance being performed is is the the verification verification of of conformance with the SRs.

SRs. The The exceptions to SR SR 3.0.2 3.0.2 are are those Surveillances Surveillances for whichwhich the 25% extension of 25% extension the interval of the interval specified specified in in the the Frequency Frequency doesdoes not not apply.

apply. TheseThese exceptions exceptions are are stated stated inin the the individual individual Specifications.

Specifications. An An example example of of where where SR 3.0.2 does SR 3.0.2 does not apply is not apply is the the Containment Containment Leak Leak Rate Rate Testing Testing Program.

Program.

Palisades Palisades Nuclear Nuclear Plant Plant BB 3.0-14 3.0-14 Revised 06/13/2013 Revised 06/13/2013

SR Applicability SR Applicability B 3.0 B 3.0 BASES BASES SR 3.0.2 SR 3.0.2 As stated As stated in in SR 3.0.2, the SR 3.0.2, the 25%

25% extension extension allowed allowed by SR 3.0.2 by SR 3.0.2 may may bebe (continued)

(continued) applied toto Required Required Actions whose whose Completion Completion Time is is stated stated as as "once once per..

per however, the

... " however,

. 25% extension the 25% extension does does not not apply apply to to the initial initial performance of performance of aa Required Required Action Action with aa periodic periodic Completion Completion Time Time that that requires performance requires performance on a "once once per per.... basis.

. II

. basis. The The 25%

25% extension applies to to each each performance of of the Required Required Action after the initial the initial performance. The performance. The initial initial performance of of the Required Required Action, whether it is is a particular Surveillance or some other remedial action, is is considered a single action with a single Completion Time. One reason for not allowing 25% extension to this Completion Time is that such an action usually the 25%

verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.

The provisions of SR 3.0.2 are not intended to be used repeatedly merely as an operational convenience to extend Surveillance intervals (other than those consistent with refueling intervals) or periodic Completion Time intervals beyond those specified.

SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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.

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

The The basis for this delay period includesincludes consideration of plant plant conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in in completing the required Surveillance, Surveillance, andand the recognition that that the most probable result of of any particular Surveillance Surveillance being being performed is is the the verification verification of of conformance with with the requirements requirements..

Palisades Palisades Nuclear Nuclear Plant Plant BB 3.0-15 3.0-15 Revised Revised 06/13/2013 06/13/2013

SR SR Applicability Applicability BB 3.0 3.0 BASES BASES SR 3.0.3 SR 3.0.3 When aa Surveillance When Surveillance with with aa Frequency Frequency based based not not onon time time intervals, intervals, but but (continued)

(continued) upon specified unit upon specified unit conditions, conditions, operating operating situations, situations, or requirements of or requirements of regulations (e.g.,

regulations prior to (e.g., prior entering MODE to entering MODE 11 after after each each fuel loading, loading, or or in in accordance with accordance with 1010 CFR CFR 50, 50, Appendix Appendix J, J, as modified by as modified by approved exemptions, etc.)

exemptions, etc.) isis discovered discovered to not have to not have been been performed performed when specified, SR specified, SR 3.0.3 3.0.3 allows for the the full delay period period ofof up to to the the specified Frequency to perform the Surveillance. However, However, since there is not a time interval specified, the missed interval missed Surveillance should be be performed at the first reasonable opportunity.

SR 3.0.3 provides a time limit for, and allowances for the performance performance of, Surveillances that become applicable as a consequence of MODE changes imposed by Required Actions.

Failure to comply with specified Frequencies for SRs is expected to be an infrequent occurrence. Use of the delay period established by SR 3.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Surveillance intervals.

While up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 consideration of the impact on plant risk (from delaying the Surveillance as well as any plant configuration changes required or shutting the plant down to perform the Surveillance) and impact on any analysis assumptions, in addition to unit conditions, planning, availability of personnel, and the time required to perform the Surveillance. This risk impact should be managed through the program in place to implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC Regulatory 10 Guide 11.182,

.182, Assessing "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants. Plants." This Regulatory Guide addresses consideration of temporary and aggregate risk impacts, impacts, determination of risk management management action thresholds, and risk management action up to and including plant shutdown. The missed Surveillance should be treated as an emergent condition as discussed in the Regulatory Guide.

as Guide. The risk evaluation may may use quantitative, quantitative, qualitative, qualitative, oror blended methods.

methods. The degree degree of depth depth and and rigor of of the the evaluation evaluation should be be commensurate commensurate with with the importance the importance of of the component.

component. MissedMissed Surveillances Surveillances for for important important components shouldshould be be analyzed analyzed quantitatively.

quantitatively. IfIf the results of of the the risk evaluation evaluation determine determine the risk increase increase is is significant, this this evaluation evaluation should should be used to be used to determine determine the the safest safest course course of of action.

action. All missed missed Surveillances Surveillances will will be placed in be placed the licensees in the licensee's Corrective Corrective Action Action Program.

Program.

Palisades Nuclear Plant Palisades Nuclear Plant BB 3.0-16 3.0-16 Revised Revised 06/13/2013 06/13/2013

SR SR Applicability Applicability BB 3.0 3.0 BASES BASES SR 3.0.3 SR 3.0.3 IfIf aa Surveillance Surveillance is is not not completed completed withinwithin the the allowed allowed delay delay period, period, then then

((continued) continued) equipment is the equipment is considered considered inoperable inoperable or or the the variable is considered variable is considered outside the specified outside specified limits limits and the Completion Times of the Completion of the the Required Required Actions for the Actions applicable LCO the applicable LCO Conditions begin begin immediately immediately upon upon expiration of expiration of the delay delay period.

period. IfIf aa Surveillance Surveillance is is failed failed within the the delay delay period, then period, then the the equipment is is inoperable, inoperable, or the the variable is is outside outside the specified limits and and the Completion Times Times of Required Actions for the of the Required applicable LCO applicable LCO Conditions begin begin immediately immediately uponupon the failure of the Surveillance.

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

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

This Specification ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the plant.

The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability. A provision is included to allow entry into a MODE or other specified condition in the Applicability when an LCO is not met due to Surveillance not being met in accordance with LCO 3.0.4.

However, in certain circumstances, failing to meet an SR will not not result in SR 3.0.43.0.4 restricting a MODE change or other specified condition change. When aa system, system, subsystem, division, division, component, device, device, or variable is inoperable or outside its specified specified limits, the associated associated SR(s) are not required to be be performed, performed, per SR SR 3.0.1, which states that that surveillances do do not not have have to be performed on inoperable equipment. equipment.

When equipment equipment is is inoperable, inoperable, SR 3.0.4 does SR 3.0.4 does not not apply apply toto the associated SR(s)

SR(s) since the requirement for the the SR(s)

SR(s) to be be performed is is removed.

Therefore, failing failing to to perform perform the Surveillance(s) within the specified specified Frequency Frequency does does notnot result in in an an SR 3.0.4 restriction SR 3.0.4 to changing restriction to changing MODES MODES or other specified conditions or other specified conditions of of the the Applicability.

Applicability. However, However, since since the LCOLCO is is notnot met met inin this this instance, instance, LCO 3.0.4 will govern LCO 3.0.4 govern anyany restrictions restrictions thatthat may may (or (or may may not) not) apply apply to to MODE MODE or or other other specified specified condition condition changes.

changes.

Palisades Palisades Nuclear Nuclear Plant Plant BB 3.0-17 3.0-17 Revised 06/13/2013 Revised 06/13/2013

SR Applicability SR Applicability B 3.0 B 3.0 BASES BASES SR 3.0.4 SR 3.0.4 SR 3.0.4 does SR 3.0.4 does not not restrict restrict changing changing MODES MODES or or other other specified specified conditions conditions (continued)

(continued) of the of when aa Surveillance the Applicability when Surveillance hashas not not been been performed performed within within the the specified Frequency, specified Frequency, providing providing the requirement requirement toto declare declare the the LCO not LCO not met has met has been been delayed in in accordance withwith SR SR 3.0.3.

3.0.3.

The provisions of The provisions of SR SR 3.0.4 shall shall not not prevent prevent changes changes in MODES MODES or or other conditions in specified conditions in the Applicability that are required required to comply with ACTIONS. In In addition, the provisions provisions of of SR 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any plant shutdown. In In this context, a plant shutdown is defined as a change in MODE or specified condition in the Applicability associated with transitioning from MODE 11 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

The precise requirements for performance of SRs are specified such that exceptions to SR 3.0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) specified in a Surveillance procedure require entry into the MODE or other specified condition in the Applicability of the associated LCO prior to the performance or completion of a Surveillance. A Surveillance that could not be performed until after LCOs Applicability, would have its Frequency specified such entering the LCO's that it is not "due" due until the specific conditions needed are met.

Alternately, the Surveillance may be stated in the form of a Note as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of SRs SRs' an notation is found in Section 1 annotation 1 .4, Frequency.

Palisades Palisades Nuclear Nuclear Plant Plant BB 3.0-18 3.0-18 Revised Revised 06/13/2013 06/13/2013

Spent Fuel Pool Storage B 3.7.16 B 3.7 PLANT SYSTEMS B 3.7.16 Spent Fuel Pool Storage BASES BACKGROUND The fuel storage facility is designed to store either new (nonirradiated) nuclear fuel assemblies, or used (irradiated) fuel 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 II and Region II per Figure B 3.7.16-1. The racks are designed as a Seismic Category II structure able to withstand seismic events.

Region II 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 II 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 1 1 D and 11 E. The Region 11 Metamic equipped racks are 235 only restricted by maximum planar U 235 U enrichment. The Region II 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, "DesignDesign Features."

Features. These limitations (e.g., enrichment, burnup, loading patterns) are sufficient to maintain a keff of S 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 flux trap" 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 "Guidance Fuel Storage at Light-Water Reactor Power Plants", 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. 2Q7, 2G, 23e, 236, 249, 246, 250

Pool Storage Spent Fuel Pool B 3.7.16 BASES APPLICABLE established the requirements for use of soluble boron to maintain SAFETY ANALYSES 0.95.

keff ~0.95.

((continued) continued)

The spent fuel pool storage satisfies Criterion 2 of 10 CFR 50.36(c)(2).

LCO LCD The restrictions for the Region I Carborundum equipped storage rack in Specification 4.3.1.1 on fuel assembly enrichment and the storage pool loading patterns, and on the placement of non-fissile bearing components, ensure that the keff of the spent fuel pool will always remain S 0.95, assuming the pool to be flooded with water borated to 850 ppm, and << 1.0 if fully flooded with unborated water. Non-fissile bearing components shall be stored in accordance with Specification 4.3.1 .lm.

4.3.1.1 m. The restrictions are consistent with the criticality safety analyses performed for the spent fuel pool.

The restrictions for the Region I Metamic equipped storage racks in Specification 4.3.1.2 on fuel assembly enrichment ensure that the keff ke of the spent fuel pool will always remain s 0.95, assuming the pool to be flooded with water borated to 850 ppm, and << 1.0 if fully flooded with unborated water.

The restrictions for Region II in Table 3.7.16-1, in the accompanying LCO, on fuel assembly enrichment and minimum burnup combinations, LCD, ensure that the keff of the spent fuel pool will always remain ~ 0.95, assuming the pool to be flooded with water borated to 850 ppm, and

<1.0

< 1.0 if fully flooded with unborated water. The restrictions are consistent with the criticality safety analyses performed for the spent fuel pool according to Table 3.7.16-1, in the accompanying LCD. LCO. Fuel assemblies not meeting the criteria of Table 3.7.16-1 shall be stored in accordance with Specification 4.3.1.1 or 4.3.1.2.

Specification 4.3.1 .1 describes U-235 enrichment restrictions for fuel 4.3.1.1 assemblies stored in the Region II Carborundum equipped storage rack based on maximum nominal planar average U-235 enrichment. The term nominal "nominal" describes the design deSign enrichment specified for an assembly. The criticality calculations that support the Region II storage requirements include a manufacturers manufacturer's fuel enrichment tolerance of

+/-0.05 weight percent U-235. Specification 4.3.1.1 does not include the manufacturers manufacturer's fuel enrichment enrichment tolerance.

The term maximum "maximum" refers to an assemblys assembly's limiting nominal planar average U-235 U-235 enrichment. Palisades Palisades' fuel assembly design may have several distinct axial planar regions, and each region may have a different different nominal planar average U-235 U-235 enrichment. Additionally, fuel Palisades Nuclear Plant BB 3.7.16-2 3.7.16-2 Amendment No. 2.O, 23&, 24, 2Q7, 2, 246, 250

Fuel Pool Spent Fuel Pool Storage B 3.7.16 BASES LCO assembly enrichments may vary from pin to pin within a given axial

((continued) continued) planar region. The criticality analysis conservatively assumes each pin is loaded with the nominal enrichment for that planar region. The highest nominal planar average enrichment of the distinct axial planar regions is considered to be the maximum nominal planar average enrichment for that assembly. This value is used to verify that storage requirements have been met. The manufacturer's manufacturers fuel enrichment tolerance of +/-0.05 weight percent is excluded from this value.

Sub-Regions 11 D & 11 E in Region 11 can be distributed in any manner providing that any 2-by-2 grouping of cells and the assemblies in them 4.3.1.lj or 4.3.1.1 meet the requirements of 4.3.1.1j 4.3.1.1kk for the number of cells occupied. For example, for a 4-by-4 group of cells, all of the following 2-by-2 configurations must be examined against the above requirements:

HHHHHH HHHHHHH H1HHHH APPLICABILITY This LCO applies whenever any fuel assembly or non-fissile bearing component is stored in the spent fuel pool or the north tilt pit.

Palisades Nuclear Plant B B 3.7.16-3 Amendment No. 2O, 2Q7, 236, 2de, 246 246, 250

Pool Storage Spent Fuel Pool B 3.7.16 83.7.16 BASES 8ASES ACTIONS The ACTIONS are modified by a Note indicating that LCO 3.0.3 does not apply.

If moving irradiated fuel assemblies while in MODE 5 or 6, LCO 3.0.3 would not specify any action. If moving irradiated fuel assemblies while in MODE 1, 2, 3, or 4, the fuel movement is independent of reactor operation. Therefore, in either case, inability to move fuel assemblies is not sufficient reason to require a reactor shutdown.

When the configuration of fuel assemblies or non-fissile bearing components stored in the spent fuel pool is not in accordance with the storage requirements, immediate action must be taken to make the necessary movement(s) to bring the configuration into compliance with the requirements.

SURVEILLANCE SR 3.7.16.1 REQUI REMENTS REQUIREMENTS This SR verifies by administrative means that the combination of fuel assembly maximum nominal planar average enrichment and proposed fuel assembly placement is in accordance with Specification 4.3.1.1 prior to placing the assembly in a Region II Carborundum equipped storage location. This SR also verifies by administrative means that non-fissile bearing component storage will be in accordance with Specification 4.3.1.lm 4.3.1.1 m prior to placing the component in a Region II Carborundum storage location.

This SR also verifies by administrative means that the nominal planar average enrichment is in accordance with Specification 4.3.1.2 prior to placing the assembly in a Region II Metamic equipped storage location.

This SR also verifies by administrative means that the combination of maximum nominal planar average U-235 enrichment, burnup and decay time of the fuel assembly is in accordance with Tables 3.7.16-1 through 3.7.16-5, as appropriate, in the accompanying LCO prior to placing the fuel assembly in a storage location in the Region II Carborundum equipped rack or the Region II racks.

REFERENCES REFERENCES None Nuclear Plant Palisades Nuclear B 3.7.16-4 83.7.16-4 Amendment No. 2Q7, 236, No. 2O, a4S, 250 239, 246,

Spent Spent Fuel Pool Storage Storage B 3.7.16 BASES N

N 'l

~ 465.00 465.001 Ref.

I' '1 I r I

I RegIon II II ReglOn II I 11 x 11 11 x 11 178.00 176.00" I IV-l W-2 Ref.

I

.I I RegIon II RegIon II I 7 x 11 7 x 11 I \01-4 I \01-3 II MAIN MlN POOL RegIon II RegIon II Region II of the north tilt pit is 60.00" comprised of Sub-Regions 1 1DD Gx 7 Gx G Ref. W-5 W-6 and 11 E. These Sub-Regions L

~~==~~~~==~ are defined in Specification 4.3.1.1 and are not related to North Tilt Nor-tb TIlt Pit Plt I the rack.

252.00 Ref.

252.001

--J Figure B B 3.7.16-1 3.7.16-1 (page 11 of 1) 1)

Spent Fuel Pool Arrangement Palisades Nuclear Nuclear Plant B 3.7.16-5 B Amendment No. 2-7,207, 6, 239, 246, a4e, 250250

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