ML20217E865
| ML20217E865 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/02/1997 |
| From: | Robert Schaaf NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217E870 | List: |
| References | |
| NUDOCS 9710070259 | |
| Download: ML20217E865 (5) | |
Text
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NUCLEAR REGULATORY COMMISSION
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CONSUMERS ENERGY COMPANY DOCKET NO. 50-255 PAllSADES PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.178 License No. DPR 20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Energy Company (the licensee) dated December 6,1995, as supplemented October 18,1996, and June 27, 1
1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted viithout endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C,(2) of Facility Operating License No. DPR 20 is hereby amended to read as follows:
9710070259 971002 ADOCK0500g5 PDR P
2 Technical SDecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.178, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. Consumers Energy Company shall opera'.e the facility in eccordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION k)*
Robert G. Schaaf, Project Manager Project Directorate lll 1 Division of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: &toler 2,197/
l ATTACHMENT TO LICENSE AMENDMENT NO.178 FACILITY OPERATING LICENSE NO. DPR 20 I
QQCKET NO. 50 255 i
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
l REMOVE JNSERT I
il ll 340 3-80 341 342 3 83 i
i 7
PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION Qfji. CPU.Il0N PAGE NO 3.0 LIMITING CONDITIONS FOR OP[ RATION (continued) 31 3.10 CONTROL ROD AND POWER DISTRIBUTION LIMITS 3 50 3.10.1 Shutdown Margin Requirements 3 50 3.10.2 Deleted 3-51 3.10.3 Part Length Control Rods 3 51 3.10.4 Misaligned or Inoperable Rod 3 52 3.10.5 Regulating Group Insertion Limits 3 52 3.10.6 Shutdown Rod Limits 3 53 3.10.7 Low Power Physics Testing 3 53 3.11 POWER DISTRIBUTION INSTRUMENTATION 3 56 3.11.1 Incore Detectors 3 56 3.11.2 Excore Power Olstribution Monitoring System 3 57 Figure 3.11 1 Axial Variation Bounding Condition 3 59 3.12 MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY 3-60 3.13 Deleted 3 60 3.14 CONTROL ROOM VENTILATION 3 61 3.15 REACTOR PRIMARY SHIELD COOLING SYSTEM 3 62 1
3.16 ESF SYSTEM INITIATION INSTRUMENTATION SETTINGS 3 63 -
Table 3.16.1 ESF System initiation Instrument Setting Limi',s 3-63 C3.16 Basis ESF System Instrumentation Settings B 3.16 1 3.17 INSTRUMENTATION AND CONTROL SYSTEMS 3 64 3.17.1 Reactor Protective System Instruments 3 64 Table 3.17.1 Instrument Requirement: for RPS 3 65 3.17.2 Engineered Safety Features Instraments 3 66 Table 3.17.2 Instrument Requirements for ESF Systems 3 67 3.17.3 Isolation Functions Instruments 3 68 Table 3.17.3 Instrument Requirements Isolation Functions 3 69 3.17.4 Accident Monitoring Instruments 3 70 t
Table 3.17.4 Instrument Requirements for Accident Monitoring 3 71 3.17.5 Alternate Shutdown System Instruments 3-72 Table 3.17.5 Instruments for the Alternate Shutdown System 3 73 3.17.6 Other Safety Feature Instruments 3-74 Table 3.17.6 Instruments for Other Safety Features 3 77 B3.17 Basis - Instrumentation Systems B 3.17-1 3.18 Deleted 3-79 3.19 IODINE REMOVAL SYSTEM 3-79 3.20 SHOCKSUPPRESSORS(Snubbers) 3-80 l
3.21 Deleted 3 80 3.22 Deleted 3 84 3.23 POWER DISTRIBUTION LIMITS 3 84 3.23.1 Linear Heat Rate 3-84 3.23.2 Redial Peaking Factors 3 86 3.23.3 Quadrant Power Tilt - Tq 3 87 Table 3.23 3 Power Distribution Measurement Uncertainty 3 88 11 Amendment No.jer
- 13. RG~ 178
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3e20 SHDCK SUPPRESSORS (Soubbers)
Anolicability Applies to the o>erating status of the safety related piping shock supprassors(snuabers). The only snubbers excluded from th<s j
requirement are those installed on non safety related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety related system.
Obiettive To minimize the possibility of unrestrained pipe motion as might occur during an earthquake or severe transient.
l Soecification 3.20.1 When systems associated with snubbers in Specification 3.20 are required l
to be OPERABLE, the snubbers in those systems shall be OPERABLE except as noted below:
t 1
a.
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubbers to OPERABLE status and )erform an engineering evaluation per Specification 4.16.1.c. on tie supported component or declare the system inoperable.
BAlii Snubbers are required to be OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.
3.21 Deleted (Next Page is 3 84) l Amendment No. H, 69. M7, ME,178 3-80
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