ML20085K310
| ML20085K310 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/08/1995 |
| From: | Kennedy J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20085K314 | List: |
| References | |
| NUDOCS 9506230283 | |
| Download: ML20085K310 (7) | |
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION o
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wa:HINGTON D.C. 30646-0001
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4 CONSUMERS POWER COMPANY a
DOCKET NO. 50-255 4
PALISADES PLANT AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 167 i
License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company -(the j
licensee) dated January 13, 1995, as supplemented April 12 and 27, 1995, complies with the standards and requirements of the Atomic i
Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 1
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; l
C.
There is reasonable assurance (1) that the activities authorized by this amer.dment can be conducted without endangering the health and l
safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
j 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 4
4 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 the license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-20 is hereby amended to read as follows:
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Technical Soecifications The Technical Specifications contained in Appendix A, as revised tbough Amendment No.167, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of. issuance.
FOR THE NUCLEAR REGULATORY COMMISSION d.# td b.
U I
Janet L. Kennedy, Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 8, 1995 l
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l ATTACHMENT TO LICENSE AMENDMENT NO. 167 FACILITY OPERATING LICENSE NO. DPR-20.
DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by i
amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT i
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3-24 3-24a 3-24b 3-25 3-25
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PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION DESCRIPTION PAGE NO 1.0 DEFINITIONS 1-1 1.1 OPERATING CONDITIONS 1-1 1.2 MISCELLANEOUS DEFINITIONS 1-5 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1 2.1 SAFETY LIMITS - REACTOR CORE 2-1 2.2 SAFETY LIMITS - PRIMARY COO! ANT SYSTEM PRESSURE 2-1 2.3 LIMITING SAFETY SYSTEM SETTINGS - RPS 2-1 l
Table 2.3.1 Reactor Protective System Trip Setting Limits 2-2 B2.1 Basis - Reactor Core Safety Limit B2-1 B2.2 Basis - Primary Coolant System Safety Limit-82-2 B2.3 Basis - Limiting Safety System Settings B2-3 3.0 LIMITING CONDITIONS FOR OPERATION 3-1 3.0 APPLICABILITY 3-1 3.1 PRIMARY COOLANT SYSTEM 3-lb 3.1.1 Operable Components 3-lb i
Figure 3-0 Pressure - Tempera function ASI Limit for Tw 3-3a 3.1.2 ture Limits 3-4 Figure 3-1 Pressure - Temperature Limits for Heatup 3-5 Figure 3-2 Pressure - Temperature Limits for Cooldown 3-6 3.1.3 Minimum Conditions for Criticality 3-12 3.1.4 Maximum Primary Coolant Radioactivity 3-17 i
3.1.5 Primary Coolant System Leakage Limits 3-20 3.1.6 Maximum PCS 0xygen and Halo en Concentration 3-23 3.1.7 Primary and Secondary Safet Valves 3-24a l*
3.1.8 Over Pressure Protection Sy tems 3-25a Figure 3-4 LTOP Limit Curve 3-25c 3.1.9 Shutdown Cooling 3-25h 3.2 CHEMICAL AND VOLUME CONTROL SYSTEM 3-26 i
3.3 EMERGENCY CORE COOLING SYSTEM 3-29 3.4 CONTAINMENT COOLING 3-34 3.5 STEAM AND FEEDWATER SYSTEMS 3-38 3.6 CONTAINMENT SYSTEM 3-40 i
Table 3.6.1 Containment Penetrations and Valves 3-40b 3.7 ELECTRICAL SYSTEMS 3-41 3.8 REFUELING OPERATIONS 3-46 3.9 Deleted 3-49 1
Amendment No, 162, 163. 167
j 3.1.7 Primary and Secondary Safety Valves Specification j
3.1.7.1 The pressurizer raJety valves shall be operable as specified in i
Table 3.1.7-1.
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Ano11cability I
Specification 3.1.7.1 is applicable when the plant is operating above COLD SHUTDOWN.
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With one or more pressurizer safety valves inoperable, 1
a.
The reactor shall be placed in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, I
and b.
The reactor shall be placed in COLD SHUTDOWN within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
i Table 3.1.7-1 s
Pressurizer Safety Valve lift Settings Valve Number Lift Setting
- l RV-1039 2580 psia i 3%
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RV-1040 2540 psia i 3%
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RV-1041 2500 psia i 3%
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- After testing or valve maintenance which could affect the setting, 3
it shall be reset to within 1% of the nominal setpoint prior to i
being returned to service.
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l 3-24a i
Amendment No. 118, 167
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l 3.1.7 Primary and Secondary Safety Valves (continued)
Specification 3.1.7.2 A minimum of 23 main steam safety valves shall be operable as specified i
in Table 3.1.7-2.
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Acolicability I
S>ecification 3.1.7.2 is applicable when the plant is operating i
a >ove COLD SHUTDOWN.
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Action i
j With more than one main steam safety valve inoperable, 3
a.
The reactor shall'be placed in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and l
b.
The reactor shall be placed in COLD SHUTDOWN within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
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Table 3.1.7-2 j
Main Steam Safety Valve Lift Settings l
l Valve Number Lift Setting
- l RV-0701, RV-0702 l
RV-0703, RV-0704 RV-0705, RV-0706 1025 E8ig i 3%
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RV-0707, RV-0708 I
RV-0709, RV-0710 RV-0711, RV-0712 RV-0713, RV-0714 1005 psig i 3%
RV-0715, RV-0716 RV-0717, RV-0718 i
RV-0719, RV-0720 RV-0721, RV-0722 985 psig i 3%
RV-0723, RV-0724 1
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- After testing or or valve maintenance which could affect the j
setting, it shall be reset to within 1% of the nominal setpoint i
prior to being returned to service.
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l 3-24b Amendment No.716.
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167
5 3.1.7 Primary and Secondary Safety Valves (continued) i Basis:
The primary and secondary safety valves provide overpressure protection for the primary coolant system and the secondary system. The r: 1..ints and relief capacities of these safety valves limit the primary " i secondary system pressures to 110% of design.
A complete loss of turbine generator load is the limiting transient for challenging the overpressure protection for the prinary and secondary.
systems. The analysis performed to support these specifications assumed complete loss of turbine generator load, withoug8 simultaneous reactor trip on turbine trip, while operating above rated power. The only pressure 4
relieving systems assumed in the analysis were the primary and secondary safety valves. The analysis was performed with parameters and equipment operational states selected to maximize the system pressures, including a
..eam generator tube plugging level of 25%.
The transient analyses and the overpressurization analysis support the primary safety valve specification with the specified tolerance and lift pressure, and with expected accumulation.
The overpressurization analysis also supports the specified secondary safety valve lift pressures and 4
tolegggce including an inoperable secondary safety valve in any one setpoint bank Following valve testing or reinsta11ation after removal for valve maintenance which could affect the valve setting, the tolerance for the safety valve lift pressure is more restrictive to allow for drift. ASME B&PV Code, 1986 edition,Section XI, subsection IWV-3500, specifies ANSI /ASME OM-1-1981 requirements which allow the specified tolerances in the lift pressures of the primary and secondary safety valves.
References (1)
EMF-93-086(P)
(2)
Letter from HG Shaw (SPC) to RJ Gerling (CPCo) dated July 26, 1993.
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J 3-25 i
Amendment No. 34, 446, 448, t
167
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