ML18067A816

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Proposed Tech Specs Converting to Improved Ts,Consistent W/ NUREG-1432,Rev 1.Includes Vols 1-20
ML18067A816
Person / Time
Site: Palisades Entergy icon.png
Issue date: 01/26/1998
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18067A815 List:
References
RTR-NUREG-1432 NUDOCS 9802100037
Download: ML18067A816 (25)
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I liMPROVED I liECHNICAL SPECIFICATIONS i

ALI SADES UC LEAR LANT 980210A-oDg~~ 6~8b~~;;-----:

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SUMMARY

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11 ATTACHMENT 1 l

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CONSUMERSENERGYCOMPANY PALISADES PLANT DOCKET 50-255

  • PALISADES ITS SUBMITTAL CONTENT AND ORGANIZATION 2 Pages
  • ATTACHMENT 1 Palisades ITS Submittal Content and Organization The Palisades Request for Conversion to ITS consists of the submittal letter, four attachments to the submittal letter (of which this is Attachment 1) and one enclosure which consists of 20 volumes.

The enclosure consists of 20 volumes - each of which (except Volumes 1 & 2), describe and justify the changes to one chapter or one section of the ITS in accordance with the guidance of NEI 96-06 and NRC Administrative Letter 96-04. The content of each volume is described below.

Vol. 1 Copy of the Submittal Letter Including Attachments Vol. 2 Complete Set of Marked up CTS pages in CTS Order Vol. 3 Chapter 1.0 Use and Application Vol. 4 Chapter 2.0 Safety Limits

  • VoJ.

Vol.

Vol.

Vol.

Vol.

5 6

7 8&9 10 & 11 Chapter 3.0 Section 3.1 Section 3.2 Section 3.3 Section 3.4 Applicability Reactivity Control Systems Power Distribution Limits Instrumentation Primary Coolant System (PCS)

Vol. 12 Section 3.5 Emergency Core Cooling Systems (ECCS)

Vol. 13 Section 3.6 Containment Systems Vol. 14 & 15 Section 3. 7 Plant Systems Vol. 16 & 17 Section 3.8 Electrical Power Systems Vol. 18 Section 3.9 Refueling Operations Vol. 19 Chapter 4.0 Design Features Vol. 20 Chapter 5.0 Administrative Controls Each volume (Vol. 3 - Vol. 20, except Volumes 9, 11, 15 and 17 which are continuations of the preceding volume) consists of an introduction letter and six attachment sections. Volumes 16 & 17, which contain Section 3.8, the Electrical Section, have-additional attachment sections which are explained in the introduction for that section.

The introduction for each volume explains how the Palisades design and licensing basis affects that chapter or section .

  • 1

The attachments in each volume (except the Electrical Section) contain the s.ame type of*information. Therefore, each volume contains an introduction and six attachments.

The attachments are:

Attachment 1 Proposed ITS pages.

Attachment 2 Proposed Bases pages.

Attachment 3 Marked-up CTS pages and Discussion of Changes (DOCs) that show how the requirements and information contained in the CTS will be dispositioned after the ITS are implemented, and the justification for the changes and i i

classifications. *

  • I' Attachment 4 No Significant Hazard Considerations for each change described in Attachment 3.

Attachment 5 NUREG-1432 pages for that section marked up to show changes in the proposed ITS and associated Bases that deviate from NUREG-1432.

Attachment 6 Justifications For Deviations (JFDs) for the deviations

  • shown in Attachment 5.

The Electrical Section has nine attachments since ,as explained in the Section*3.8 introduction, it is based on a pending Technical Specification Change Request that is all-encompassing and closely resembles the ISTS.

Each volume is contained in a Palisades ITS-identified hardcover loose-leaf notebook.

  • 2

ATTACHMENT 2 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 PENDING CTS TECHNICAL SPECIFICATION CHANGE REQUESTS

  • 1 Page

ATIACHMENT 2 PENDING CTS TECHNICAL SPECIFICATION CHANGE REQUESTS CTSCRs)

TAC NO SUBMITTAL DATES TSCR TITLE ITS SECTIONS NOTES AFFECTED M-94287 12/11/95 ADM\NISTRATIVE CONTROLS 3.4 TSCR Changes:

01/18/96 I 5.0 Revision of CTS 4.3f. RHX surveillance interval to 10 years 09103196 Partial Issue 10/31/96 Relocate Procedure Control details. 6.4.2 &6.4.3. to CPC-2A 10/02/96 (Amendment 174) Revise ODCM &Rad Effluent Program to refer to new 10 CFR 20 10/18/96 Relocate Review and Audit. 6.8. to CPC-2A 10/25/96 Affected CTS Pages:

03128197 4-16. 6-4. 6-5. &6-7 revised; 06127197 6-24 -> 6-31 deleted M-94378 12/27/95 ELECTRICAL 3.1 Rewrites*the Electrical CTS (LCOS AND SRs) to emulate STS.

09106196 3.3 Affected CTS Pages:

11/26/96 3.4 3-41 -> 3-45b Replaced by new 3-41 -> 3-45g 06127197 3.5 3-66. 3-67. B 3.17-15. B 3.17-16. B 3.17-17. 4-11. revised 11/21/97 3.7 4-42. 43. 43a replaced by new 4-42 -> 4-43d 3.9 4-77. 6-16 revised

" 5.0 M-98291 03/26/97 CONTAINMENT 1.0 TSCR revises section 3.6 &4.5.

3.6 Reduces Cont pressure limit to 1.5# Rx SD or 1# Rx Crit.

3.9 Adds new LCO for containment temperature 5.0 Adds a note to allow entry through a locked airlock door Affected CTS Pages:

1-2. 3-40. 3-40a. &4-20 -> 4-23a revised:

4-23b added 3-40b -> 3-40g deleted M-94567 01/18/96 PCP FLYWHEEL 5.0 TSCR requests extension of flywheel testing SR to 10 years.

10/01/97 Affected CTS Pages: 6-8 revised

  • M-99651 09103197 CONTROL ROOM HVAC 3.3 Revises CTS 3 ..14 to emulate STS requirements for CR-HVAC 3.7 Two LCOs: CRHVAC-Filtration &CRHVAC-Cooling Affected CTS Pages:

3-61. 3-62. 3-64. 4-14. 4-76. B 3.17-5. B 3.17-7. B 3.17-35 M-99656 09103197 SNUBBERS None Relocates CTS Snubber requirements 3.20 i 4.16 to ORM.

Affected CTS Pages: 3-79b. 3-80. 3-84. &4 4-74a 1

ATTACHMENT 3 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 GENERIC CHANGES 5 Pages

  • ATTACHMENT 3 GENERIC CHANGES This attachment lists: (1) the Technical Specifications Task Force (TSTF) generic changes that have been approved by the NRC (as of October 15, 1997) that impact NUREG-1432, Revision l; and (2) the TSTF recommended changes that were not yet approved by the NRC that were incorporated.

This attachment is provided in two tables.

Table 1 is sorted by Section, then by TSTF, and by Justification For Difference (JFD).

Table 2 is identical data sorted by TSTF, tlien by Section, and by JFD.

A. designation of NYA in the TSTF column indicates that this incorporated generic change was Not Yet Approved (as of October 15, 1997).

  • A listing of NA-Digital in the JFD column indicates that this generic change is not applicable since the change affects only the digital Specifications of NUREG-143 2 and Palisades instrumentation is analog rather than digital.

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  • 1
  • ATTACHMENT 3 GENERIC CHANGES TABLE. I (Sorted by Section/TSTF/JFD)

TSTF Section JFD TSTF Section JFD 40 I 1.0-12 172 3.1 3. l.04-12 47 I 1.0-11 193 3. l 3.105-25 67 I 1.0-13 194 3.1 3. l.08-06 5, RI 2 2.0-08 77 3.2  :\..\-Di~ital 144 2 2.0-06 136 3.2 3.2.0l-l l

8. R2 3.0 3.0-07 149 3.2 \'..\-Digital 52 NYA 3.0 3.0-08 150 3.2  :\'..\-Digital 71, RI 3.0 3.0-14 69 3.3 NA-Digital 103 NYA 3.0 3.0-06 72 3.3 NA-Digital 104 3.0 3.0-13 73 3.3 '.'/.-\-Digital .

122 3.0 3.0-12 74 3.3 N..1..-Digital 165 3.0 3.0-10 75 3.3 NA-Digital 166 3.0 3.0-11 76, Rl 3.3 NA-Digital

. 9, RI 3.l 3.1.01-09 79, Rl 3.3 3.J.03-08 67 3.l 3.1.01-14 80, Rl 3.3 3.3.01~23 .

67 3.l 3. !.05-23 81 3.3 3.3.01-23 67 3.l 3.1.06-\6 82,Rl 3.3 3.3.02-06 <

67 3.l 3.1.07-15 83 3.3 3.3.03-IO 67 3.l 3.1.09-17 84 3.3 3.3.09-06 127, RI 3.l 3.1.05-03 85, Rl 3.3 3.3.01-08 127, RI 3.1 3.1.05-06 130, Rl 3.3 '.'/.-\-Digital 136 3.1 . 3.1.01-07 132 3.3 \'.-\-Digital 136 3.1 3.1.02-06 136 3.3 3.3.13-12 136 3.1 . 3.1.03-12 148 3.3. ~.-\-Digital 136 3.1 3.1.04-10 170 3.3 3.3.03-i l 136 3.1 3.1.05-24 178 3.3 3.3.01-25 136 3.1 3.1.06-15 - 179 3.3 3.3.0 l-26

. 136 3.1 3.1.07-14 180 3.3 3.3.02-06 136

-- 3.1 3.1.09-16 !81 3.3 3.3.03-12 141 3.1 3.1.03-13 182 3.3 3.3.03-14 142 3.1 3.1.03-07 184 3.3 3.3.07-09 143 3.1 3.1.05-07 185 3.3 3.3.07-09 154, Rl NYA 3.1 3.1.09-10 186 . 3.3 3.3.07-!0

  • 2
    • ATTACHMENT 3 GENERIC CHANGES TABLE 1 (Sorted by Section/TSTF/JFD)

TSTF Section JFD TSTF Section JFD 187 3.3 3.3.05-12 133, RI 3.5 3.5.05-09 187 3.3 3.3.09-06 17, RI 3.6 3.6.02-08 188 3.3 3.3.11-12 30,R2 3.6 3.6.03-13 189 3.3 3.3.01-27 45. RI 3.6 3.6.03-08 192 3.3 3.3.03-08 46, RI 3.6 3.6 03-09 26 3.4 3.4.02-07 52 NYA 3.6 3.6.01-06 27, R2 NYA 3.4 3.4.02-06 52NYA 3.6 3.6.02-06 28 3.4 3.4.16-07 52NYA 3.6 3.6.02-10 53, RI 3.4 3.4.11-20 78 3.6 3.6.068-09 54, RI 3.4 3.4.13-10 70, RI 3.7 3.7.17-06 55 3.4 3.4.12-14 100 3.7 3.7.04-12 56 3.4 3.4.11-14 IOI 3.7 3.7.05-11 .

57 3.4 3.4.10-09 139, RI 3.7 3.7.16-08 60 3.4 3.4.15-07 140 3.7 3. 7.06-10 61 3.4 3.4.13-07 173 3.7 3.7.19-06 62 3.4 3.4.01-08 174 3.7 3.7.06-09 63 3.4 3.4.07-14 175 3.7 3.7.08-06 66 3.4 3.4.16-06 8, R2 - 3.8 3.8.01-12 93, R3 3.4 3.4.09-16 8, R2 3.8 3.8.04-06 94, RI 3.4 3.4.09-05 8, R2 3.8 3.8.B-06 105 ~YA 3.4 3.4.01-09 38 3.8 3.8.04-07 114 3.4 3.4.07-08 38 3.8 3.8.B-09 129 3.4 3.4.01-05 20 3.9 3.9.06-08 136 3.4 3.4.01-15 21, RI 3.9 3.9.05-10 137 3.4 3.4.16-09 21 3.9 3.9.05-10 153 3.4 .. 3.4.05-06 96 3.9 3.9.02-06 153 3.4 3.4.06-06

.. 136 3.9 3.9.01-07 153 3.4 3.4.07-06 146 3.9 3.9.04-06 153 3.4 3.4.08-06 153 3.9 3.9.04-12 177 3.4 3.4.05-09 52NYA 5 5.0-19 195 3.4 3.4.06-13 106, Rl 5 5.0-05 78 3.5 3.5.02-09 118 5 5.0-24 128, RI 3.5 3.5.05-07 152 5 5.0-25

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  • ATTACHMENT 3 .

GENERIC CHANGES TABLE 2 (Sorted by TSTF/Section/JFD)

TSTF Section JFD. TSTF Section JFD 5, RI 2 2.0-08 63 3.4 3.4.07-14 8, R2 3.0 3.0-07 66 3.4 J.4.16-06 .

8. R2 3.8 3.8.0I-I2 67 I l.0-13 8, R2 3.8 3.8.04-06 67 3.1 3.l.Ol-14
8. R2 3.8 3.8.B-06 67 3.1 J. l.05-23 9, Rl 3.I 3.l.OI-09 67 3. I 3.1.06-16 17, RI 3.6 3.6.02-08 67 3.I 3.1.07-15 20 3.9 3.9.06-08 67 3.1 3. l.09-I 7 21, RI 3.9 3.9.05-10 69 3.3 NA-Digital 2I 3.9 3.9.05-IO 70, Rl 3.7 3.7. I 7-06 26 3.4 3.4.02-07 7I, RI 3.0 3.0-I4 27, R2 NYA 3.4 3.4.02-06 72 3.3 NA-Digital 28 3.4 3.4. I6-07 73 3.3 NA-Digital
30. R2 3.6 3.6.03-I3 74 3.3 N.-\-DigitaI 38 3.8 3.8.04-07 75 3.3 . NA-Digital 38 3.8 H.B..Q9 76, RI 3.3  :'-iA-Digital 40 I 1.0-I 2 77 3.2 NA,Digital 45, Rl J.6 3.6.03-08 78 3.5 J,5.02-09 46, RI 3.6 3.6.03-09 78 3.6 J.6.068-09 47 1 1.0-I l 79. RI 3.3 J.3.0J-08 52 NYA 3.0 3.0-08 80, RI 3.3 3.3.0I-28 52NYA 3.6 3.6.01-06 81 3.3 3.3.0I-23 52NYA 3.6 3.6.02-06 82, RI 3.3 3.3.02-06 52NYA 3.6 3.6.02-IO 83 3.3 3.3.03-IO 52NYA s *5.0-19 84 3.3 3.3.09-06 53,Rl 3.4 3.4. I I-20 85, RI 3.3 3.3.0I-08.

54,Rl 3.4 3.4.13-10

.. 93, R3 3.4 3.4.09-I6 SS 56

- 3.4 3.4 3.4. I2-14 3.4.11-I4 94, RI 96 3.4 3.9 3.4.09-05 3.9.02-06 57 3.4 3.4.10-09 100 3.7 3.7.04-I2 60 3.4 3.4.I5..Q7 101 3.7 3.7.05-I l 61 3.4 3.4.I3-07 I03 NYA 3.0 3.0-06 62 3.4 3.4.01-08 104 3.0 3.0-13

  • 4
      • ATTACHMENT 3 GENERIC CHANGES TABLE 2 (Sorted by TSTF/Section/JFD)

TSTF Section

  • JFD TSTF Section .JFD 105 '.\'YA 3.4 3.4.01-09 149 3.2  :-IA-Digital 106, RI 5 5.0-05 150 3.2  ;-;A-Digital 114 3.4 3.4.07-08 152 5 5.0-25 118 5 5.0-24 153 3.4 3.4.05-06 122 3.0 3.0-12 153 3.4 3.-to6*06 127, RI* 3.1 3.1.05-03 153 3.4 3.4.07-06 127, RI 3.1 3.1.05-06 153 3.4 3.4.08-06 128, RI 3.5 3.5.05-07 153 3.9 3.9.04-12 129 3.4 3.4.01-05 154,Rl NYA 3.1 3.1.09-10 130, RI 3.3 NA-Digital 165 3.0 3.0-10 132 3.3 NA-Digital 166 3.0 3.0-11 133, RI 3.5 3.5.05-09 170

3.3 3.3.03-11 136 3.1 3.1.01-07 172 3.1 3.1.04-12 136 3.1 3.1.02-06 173 3.7 3.7.19-06 136 3.1 3.1.03-12 174 3.7 3. 7.06-09 136 3.1 3.1.04-10 175 3.7 3.7.08-06 136 3.1 3.1.05-24 177 3.4 3.4.05-09 136 3.1 3.1.06-15 178 3.3 3.3.01-25 136 3.1 3.1.07-14 179 3.3 3.3.01-26 136 3.1 3.1.09-16 180 3.3 3.3.02-06 136 3.2 3.2.1-11 181 3.3 3.3.03-12 136 3.3 3.3.13-12 182 3.3 3.3.03-14 136 3.4 3.4.01-15 184 3.3 3.3.07-09 136 3.9 3.9.01-07 185 3.3 3.3.07-09 137 3.4 3.4.16-09 186 3.3 3.3.07-10 139, RI 3.7 .. 3.7.16-08 187 3.3 3.3.05-12 140 3.7 3.7.06-10 - 187 3.3 3.3.09-06 141 3.1 3.1.03-13 188 3.3 3.3.11-12 142 3.1 3.1.03-07 189 3.3 3.3.01-27 143 3.1 3.1.05-07 192 3.3 3.3.03-08 144 2 2.0-06 193 3.1 3.1.05-25 146 3.9 3.9.04-06 194 3.1 3.1.08-06 NA-Digital 3.4 3.4.06-13 148 3.3 195 5

  • ATTACHMENT 4 CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET 50-255 APPLICATION OF SELECTION CRITERIA TO THE PALISADES CTS .*

12 Pages

INTRODUCTION The requirements in the Palisades Current Technical Specifications (CTS) were evaluated to determine if they met any of the four criteria of 10 CFR 50.36. As part of that evaluation, each requirement which was determined to be a candidate for relocation was reviewed by the Palisades Probabilistic Safety Assessment (PSA)

Section to determine if its removal had a significant risk impact. -consumers Energy has determined the relocation of the identified requirements is neither risk significant, nor expected to have an impact on the PSA.

The results of the evaluation are provided in the summary disposition matrix and include a reference to the Discussion of Change which justifies the relocation of those requirements which do not meet any of the four criteria of 10 CFR 50.36 .

  • I

CURRENT CURRENT NEW TS

SUMMARY

DISPOSITION MATRIX .JR PALISADES NUCLEAR PLANT RETAINED-CRITERION TS TITLE/SUBJECT NUMBER FOR INCLUSION NOTES 1.0 DEF IN IT IONS 1.1 Yes-N/A This section provides definitions for severd l defined terms used throughout the remainder of the Technical Speci ficdt ions (TS). They dre provided to improve the medning of certdin terms. As such, direct application of ihe TS selection*

1 criteria is not appropridte. However, only those definitions for defined terms that remain dS a result of application of the selection criteria, wi 11 remdin as definitions in' th{s section of TS.

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM 2.0 SETTINGS (LSSS) 2.1 Reactor Core 2.1.1 Yes-N/A Application of TS selection criteria is not appropriate.

However, Safety Limits will be included in TS as required by 10 CFR 5Q.36.

2.2 Primdry Coolant System Pressure 2.1.2 Yes-N/A Application of TS selection criteria is not appropriate.

However,* Safety Limits will be included in TS as requ i r.ed by 10 CFR 50.36.

2.3 Redctor Protective System Trip Setting 3.3.1 Yes-3 The application of TS selection criteria is not appropridte .

.'limits However, the RPS LSSS hdve been included dS part of the RPS instrumentdtion specification, which has been retained since Functions either actuate to mitigate conseque~ces of Design Basis Accidents (OBA) and transients or are retained ds directed by the NRC as the Functions are part of the RPS 3.0 APPLICABILITY 3.0 3.0.1 Operational Conditions LCO 3.0.l Yes-N/A This Specification provides generic guiddnce applicable to one or.more Specifications. The information is provided to fdcilitate understanding of Limiting Conditions for Operdtions. As such, direct application of the TS selection criteria is not appropridte. However, the generdl requirements of 3.0 will be retained in TS, as modi tied consistent with NUREG-1432, Rev. 1.

3.0.2 Noncompliance LCO 3.0.2 Yes-N/A Same as dbove.

3.0.3 Generic Actions LCO 3.0.3 Yes-N/A* Same as dbove.

3.0.4 Entry into Operational Modes LCO 3.0.4 Yes-N/A Same as above.

3.0.5 Operability Exception LCO 3.0.5 Yes-N/A Sdme dS dbove.

2

CURRENT

SUMMARY

DISPOSITION MATRIX .JR PALISADES NUCLEAR PLANT CURRENT NEW TS RETAINED-CRITERION TS TITLE/SUBJECT NUMBER FOR INCLUSION NOTES 4.0 SURVEILLANCE REQUIREMENTS SR 3.0 4.0.1 Operc1t i ona I Conditions SR 3.0.1 Yes-N/A This Specification provides generic guidance applicable lo one I or more Specifications. The information is provided to j facilitate understanding of Surveillance Requirements. As such, direct .application of the TS selection criteria is not ilppropriate. However, the general requirements of 4.0 will be retilined in TS, as modified consistent with NUREG-1432, Rev.

l.

4.0.2: Time of.Performance SR 3.0.2 Yes-N/A Same as above.

4.0.3 Non comp Ii ance SR 3.0.3 Yes-N/A Silme as above.

4.0.4 Entry into Operational Hodes SR 3.0.4 Yes-N/A Same as above.

4.0.5 Deleted in CTS 3.1 PRIMARY COOLANT SYSTEM (PCS) 3.1.la PCS flow requi,reme'nts for bora ti on 3.4.5 Yes-3 3.4.6 Yes-4

" 3.4.7 Yes-4 3.4.8 Yes-4 3.1. lb Primary Coolant Pump (PCP) requirements 3.4.4 Yes-2, 3

> 525°F 3.1.lc PCS flow Requirements 3.4.1 Yes-2 3.1. ld Steam generator requirements > 300°F 3.4.4 Yes-2, 3 3.4.5 Yes-3 3.1. le AXIAL Shape Index (ASI) requirements and 3.2.4 Yes-2 actions 3.1.lf-g PCS pressure/temperature requirements ilnd 3.4.1 Yes-2 actions 3 .1. lh PCP starting requirements 3.4.5 Yes-3 3.4.6 Yes-4 3.4.7 Yes-4 3.1.1 i PCP operation requirements < 300°F 3.4.6 Yes-4 3.4.7 Yes-4

3. l. lj PZR he'ater requirement and actions J.4.9 Yes-4 3

CURRENT CURRENT NEW TS

SUMMARY

DISPOSITION MATRIX .JR PALISADES NUCLEAR PLANT RETAINED-CRITERION TS TITLE/SUBJECT NUMBER FOR INCLUSION NOTES 3.1.2 PCS P/T LCO requirements 3.4.3 Yes-2

3. l.2a PCS H/U & C/D curves 3.4.3 Yes-2 J. l.2b 1~ZR H/U & C/D rates Relocated No* See Section 3.4 Discussion of Change R.l J. l. 2c PCS H/U & C/D rates 3.4.J Yes-2 J.l.J MINIMUM CONDITIONS FOR CRITICALITY J. l.Ja: Minimum temperature for criticality (Low 3.1.7 Yes-N/A power physics.test exception) J.4.2 Yes-2
3. l.3b Minimum te11perature for criticality J.1.7 Yes-N/A J. l.Jc Reactivity requirements below minimum 3.4~2 Yes-2 temperature in J.l.3a above J. l.3d--e Reactivity requirements without steam bubble 3.4.9 Yes-2, 4 in PZR '

J.l.4 MAXIMUM PRIMARY 1 COOLANT RADIOACTIVITY J. l.4a-e PCS specific activity requirements and 3.4.16 Yes-2 actions J.1.5 PRIMARY COOLANT SYSTEM LEAKAGE LIMITS 3.l.5a, b Identified & unidentified PCS leakage limits 3.4.13 Yes-2 and actions J. l. 5c Secondary specific activity limits and 3.7.17 Yes-2 actions J. l.5d Primary to secondary leakage limits 3.4.13 Yes-2 3.1.6 MAXIMUM PRIMARY COOLANT OXYGEN AND HALOGENS CONCENTRATION 3.l.6a-e Primary chemistry limits and actions Relocated No See Section J.4 niscussion of Chdnye R.Z 3.1.7 PRIMARY and SECONDARY SAFETY VALVES 3.1.7 .1 Primary setpoints and actions 3.4.10 Yes-3 3.1.7 .2 Secondary setpoints and actions 3. 7 .1 Yes-3 3.1.8 OVERPRESSURE PROTECTION SYSTEMS 4

CURRENT CURRENT NEW TS

SUMMARY

DISPOSITION MATRIX .JR PALISADES NUCLEAR PLANT RETAINED-CRITERION, TS TITLE/SUBJECT NUMBER FOR INCLUSION NOTES 3.1.8.1 PZR PORVs requirements and actions (~ 430°F) 3.4; 11 Ves-4 3.1.8.2 PZR PORVs requirements and actions (< 430°F) 3.4.12 Ves-2 3.1.9 1 ~SHUTDOWN COOLING 3.1.9.1 Requirements and actions (> 200"F ~ 300°F) 3.4.6 Ves-4 3.1.9.2 Requirements and action with loops filled 3.4.7 Yes-4

(< ZOO"F) 3.1.9.3 Requirements and actions with loops not 3.4.8 Yes-4 filled.(< 200°F) 3.9.4 3.9.5 3.2 CHEMICAL ANO VOLUME CONTROL SYSTEM 3.2.l,. Charging pump/flow path/and boric acid pump Relocated No See Section *3.1 ~iscussion of Change R.l 3.2.2, and concentration requirements and actions 3.2.3 3.3 EMERGENCY CORE, COOLING SYSTEM (ECCS) 3.3.l ECCS applicability 3.5.l Ves-3 3.5.2 3.5.4 3.7.7 3.3.la SIRW tank requirements 3.5.4 Yes-3 3.3.lb Safety injection tank requirements 3.5.1 Yes-3 3.3.lc-d Safety injection pump requirements 3.5.2 Yes-3 3.3.le Heat exchanger requirements (SOC & CCW) 3 ..5.2 Yes-3 3.7.7 3.3. lf-j ~iping and valve requirements 3.5.1 . Ves-3 I 3.5.2 3.3.2 ECCS/CCW actions 3.5.l Ves-3 3.5.2 3.7.7 3.3.2a ECCS requirements (tank) 3.5.1 Ves-3 3.3.2b, c ECCS requirements (pump) J.5.2 Yes-3

.5

CURRENT

  • CURRENT NEW TS

SUMMARY

DISPOSITION MATRIX ,JR PALISADES NUCLEAR PLANT RETAINED-CRITERION TS TITLE/SUBJECT NUMBER FOR INCLUSION NOTES 3.3.2d ECCS/CCW requirements (HX's) 3.5.2 Yes-3 3.7.7 3.3.2e-f ECCS valve ~nd piping requirements 3.5.2 Yes-3 3.3.3 PIV requirements and actions 3.4.14 Yes-2 3.3.4 ECCS pump and requirements > 325°F 3.5.2 Yes-3 3.3.5 ECCS pump requirements < 300°F 3.4.12 Yes-2 3.4 CONTAINMENT COOLING 3.4.1 Pump/air cooler requirements for containment 3.6.6 Yes-3 cooling, pump/HX requirements for CCW and 3 .7 .7 Service Water 3. 7 .8 3.4.2 Actions 3.4.3 Actions with a 11 owances 3.4.4 Equipment required to.~e operable in system 3.4.5 3.5 STEAM AND FEEDWATER SYSTEMS 3.5.la AFW component requirements 3.7.5 Yes-3

3. 7 .6 3.5.lb-d AFW component requirements 3.7.5 Yes-3 3.5.le Condensate storage volume requirements 3.7.6 Yes-3 3.5.lf Main steam isolation valve requirements 3.7 .2 Yes-3 3.5.2a, b Auxiliary feedwater pump inoperability 3.7.5 Yes-3 allowance 3.5.2c, d AFW backup condensate supply requirements 3. 7 .6 Yes-3 3.5.2e AFW system component requirements 3.7.5 Yes-3 3.5.3 MSIV/AFW/Condensate inoperability actions 3.7.2 Yes-3 3.7.5
3. 7. 6 3.5.4 AFW pump inoperability actions 3. 7 :5 Yes-3 6

SUMMARY

DISPOSITION MATRIX .JR PALISADES NUCLEAR PLANT

  • CURRENT CURRENT NEW TS RETAINED-CRIT~RION i ..

TS TITLE/SUBJECT NUMBER FOR INCLUSION NOTES 3.6 CONTAINMENT SYSTEM 3.6.la-c Applicability and containment isolation 3.6.1 Yes-3 valve~*inoperability actions 3.6.2 Yes-3 II 3.6.3 Yes-3 3.9.3 Yes-4 3.6.2 Containment pressure requirements and .3.6.4 Yes-2 actions 3.6.3 Containment temperature requirements and 3.6.5 Yes-2 actjons 3.6.4 Hydrogen recombiner requirements and actions 3.6.7 Yes-3 3.6.5 Containment purge isolation valve 3.6.3 Yes-3 requirements and actions 3.7 ELECTRICAL SYSTEMS 3.7.1 AC sources - op,ratfng specification 3.8.1 Yes-3 3.8.3 3.7.2 AC sources - Shut~own specificatio~ 3.8.2 Yes-3

3. 7 .3 DG fuel oil and lube oil speci fi cation 3.8.3 Yes-3
3. 7 .4 DC sources - Operating specification 3.8.4 Yes-3 3.7.5 DC sources - Shutdown specification 3.8.5 Yes-3 3.7.6 Battery specification 3.8.6 Yes-3 3.7.7 Inverters - Operating specification 3.8. 7 Yes-3 3.7.8 Inverters - Shutdown specification 3.8.8 Yes-3 3.7.9 Distribution systems - Operating 3.8.9 Yes-3 s pee ifi cat ilin 3.7.10 Distribution systems - Shutdown 3.8.10 Yes-3 specification 3.8 REFUELING OPERATIONS 3.8.la-c Component requirements 3.3.6 Yes-4 3.7 .12 Yes-3 3.9.3 Yes-4 7

SUMMARY

DISPOSITION MATRIX .JR PALISADES NUCLEAR PLANT CURRENT

  • CURRENT NEW TS RETAINED-CRITERION ...

TS TITLE/SUBJECT NUMBER FOR INCLUSION NOTES 3.8.ld Radiation level monitoring requirements Relocated No See Section 3.3 Discussion of Change R.l, and Section 3.9 Discussion of Change R.l 3.8.le Neutron fl~x monitoring requirements 3.9.2 Yes-3 I

3.8.lf Shutdown cooling requirements 3.9.4 Yes-4 3.8.lg Refueling boron sampling requir~ments 3.9.1 Yes-2 3.8 .. lh Co11111unication requirements Relocated No See Section 3.9 Discussion of Change R.2 3.8.2 Actions , 3.3.6 Yes-4 3.9.1 Yes-2 3.9.2 Yes-3 3.9.3 Yes-4 3.9.4 Yes-4 3.8.3 Time limit for co11111encement of refueling Relocated No See Section 3.9 Discussion of Change R.3 operations 3.8.4 Fuel handling build~ng ventilation 3.7 .12 Yes-3 requi remen'ts and actions 3.8.5 Tilt pit water temperature monitoring Relocated No See Section 3.9 Discussion of Change R.4 requirements 3.9 Deleted in CTS 3.10 CONTROL ROD AND POWER DISTRIBUTION LIMITS 3.10.la-c Shutdown margin requirements 3.1.1 Yes-2 3.4.6 Yes-4 .

3.4.7 Yes-4 3.4.8 Yes-4 3.10. ld-e Control rod drop time 3.1.4 Yes-2, 3 '

3.10.2 Deleted in CTS 3.10.3 Part-length control rod restrictions 3.1. 5 Yes-2 3.10.4 Misaligned or inoperable control rod or 3.1.4 Yes-2.* 3 .;.

part-length rod specifications 3.10.5. Regulating group insertion limits 3.1.6 Yes-2 3.10.6 Shutdown rod limits 3:1. 5 Yes-2 8

CURRENT CURRENT NEW TS

SUMMARY

DISPOSITION MATRIX .JR PALISADES NUCLEAR PLANT RETAINED-CRITERION TS TITLE/SUBJECT NUMBER FOR INCLUSION NOTES 3.10.7 Low power p~ysics testing/CROM exercising 3.1. l Yes-2 allowances 3.1.4 Yes-2, 3 3.1.5 Yes-2 3.1.6 . Yes-2

~ 3.1. 7 Yes-N/A 3.11.1 lncore detectors specification Relocated No See Section 3.2 Discussion of Change R.l 3.11.2 Excore power distribution monitoring Relocated No See Section 3.2 Discussion.of Change R.l specification 3.12 Moderator tempera~ure coefficient of 3.1.3 Yes-2 reactivity s*peci fi cation 3.13 Deleted in CTS 3.14 CONTROL ROOM VENTILATION 3.14.l Filtration specification 3.7.10 Yes-3 3.14.2 Cooling ~pecification 3. 7 .11 Yes-3 3.15 Deleted in CTS 3.16 ENGINEERED SAFETY FEATURES (ESF) SYSTEM INSTRUMENTATION SETTINGS 3.16.l ESF instrumentation specification 3.3.3 Yes-3 3.3.10 3.17 INSTRUMENTATION SYSTEMS 3.17 .1 Reactor Protection System (RPS) 3.3.l Yes-3 speci fi cation 3.3.2 3 .17. 2 ESF logic instrumentati~n specification 3.3.3 Yes-3 3.3.4 3.17 .3 ESF isolation function specification 3.3.3 Yes-3 3.3.4 3.3.10 3.17.4 Accident monitoring instrumentation 3.3.7 Yes-3

  • 3 .17. 5 Alternate Shutdown Instrumentation 3.3.8 Yes-4 speci fi cation 9.

SUMMARY

DISPOSITION MATRIX .JR PALISADES NUCLEAR PLANT

  • CURRENT CURRENT *NEW TS RETAINED-CRITERION .

TS TITLE/SUBJECT NUMBER FOR INCLUSION NOTES 3.17 .6 Sdfety function instrumentation 3.1.4 " Yes-2, 3 specification 3.3.6 Yes-4 3.3.9 Yes-3 I 3.9.2 .Yes-3 I

3.17.6.1 Neutron 'flux monitoring requirements and 3.3.9 Yes-3 actions 3.9.2 3.17.6°.2 Rod posit ion indication requirements and .. 3.1.4 Yes- 2, 3 actions 3.17 .6.3 Safety function instrument requirements and Relocated No See Section 3.3 Discussion of Change R.2 actions 3.17 .6.4 3.17.6.5 3.17 .6.6.1.

3.17 .6.6.2 3.17.6.7.1 '

Leak detection instrument requirements and 3.4.15 Yes-1 actions 3.17.6.7.2 3.17 .6.8 Valve position indicatio~ (safety valve, PZR Relocated No See Section 3.3 Discussion of Change R.3 PORV) requirements and actions 3.17.6.9 3.17 .6.10 3.17.. 6.11 Service Water Break Detection Actions Relocated* No Se~* Section 3.3 Discussion of Change R.3 3.17.6.12.1 t.T flux channel requ.irements and actions 3.3.1 Yes-3 3.17.6.12.2 3.17.6.13 Rod *group sequence channel requirements and 3.1.6 Yes-2 actions 3.17 .6.14 Boric acid* tank level alarm requirements and . Relo.cated No Se~ Section 3.1 Discussion of Change R.l actions 3.17.6.15 Excore and axial shape alarm requirements Relocated No See Sec ti on 3.2 Discussion of Change R.l and actions 3.17 .6.16 10

CURRENT CURRENT NEW TS

SUMMARY

DISPOSITION MATRIX .JR PALISADES NUCLEAR PLANT RETAINED-CRITERION TS Till E/ SUBJECT' NUMBER FOR INCLUSION NOTES 3.17 .6.17 SOC suction valve interlock requirements and 3.4.14 Yes-2 actions 3.17 .6.18 Power dependent insertion alarm requirements *. 3.1.6 Yes-2 and actions 3.17 .6.19 Fuel pool area radiation monitoring Relocated* No See Section 3.3 Discussion of Change R.4 requirements and actions 3;17.6.20 Containment refueling radiation monitor 3.3.6 Yes-4

requirements and actions 3.17 .6.21 Safety function insirumentation actions 3.1.4 Yes-2, 3 3.1.6 Yes-2 3.4.14 Yes-2 3.4.15 Yes-1 Table 3.17 .6 Instrumentation Relocated No See Section 3.3 Discussion o.f Chilnge R.2
  • Items 3, 4, 5, 6 Table 3.17.6 lnstrifuientation Relocdted No See Section 3.3 Oiscu.ssion of Change R.3 Items 8, 9, 10, 11, Table 3.17 .6 Instrumentiltiori Relocilted No See Section 3.1 Discussion *f Change R.l
  • Item 14

. Table 3.17 .6 Instrumentation Relocated No See Section 3.2 Discussion of Chilnge R.l Items 15, 16 Table 3.17.6 Instrumentation ReloCilted No s.ee *Section,*3.. 3 Discussion of Ch<1nye R.4 Item 19 3.18 Deleted in CTS 3.19 Iodl ne removal system specification 3.5.5 Yes-3 3.20 Deleted in CTS 3.21 Deleted in CTS 3.22 Deleted in CTS 3.23 POWER DISTRIBUTION LIMIT.S 11

SUMMARY

DISPOSITION MATRIX FOR PALISADES NUCLEAR PLANT

.CURRENT CURRENT NEW TS RETAINED-CRITERION TS TITLE/SUBJECT NUMBER FOR INCLUSION NOTES. .

  • 3.23.1 Li near Heat Rate (LHR) specifi cat i.on 3.2.1 Yes-2 3.23.2 Radial peaking factors specification 3.2.2 Yes-2
  • 3.23.3 Quadrant Power Tilt 3.2.3 Yes-2 Table 4.2.2 Refueling System Interlocks Relocated No See *section J.9 Discus*sion of Change R.5
  • Item 5 4.12 Augmented Ins.ervice Inspection Program for Relocated No See Section 3.7 Discussion of Change R.1 High Energy Line Breaks Outside of Containment 5.0 DESIGN FEATURES 4.0 Yes-N/A Application of Technical Specification selection criteria is not appropriate. However, specific portions of Design Features* will be in.eluded in Technical Specifications as required by 10 CFR 50.36. The confent of this section has been revised to be con_sistent with Rev. 1 of NUREG-1432.

6.0 ADMINISTRATIVE CONTROLS 5.0 Yes-N/A Application of TS selection criteria is not appropriate.

  • However, specific portions of Administrative Control_s will be included in TS as re qui red by 10 CFR_ 50 .36.

12

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