ML18064A736

Proposed Tech Specs,Supporting Action Statements for Inoperable Safety Valves in Proposed Specs 3.1.7 of TS Change Request of 950103

ML18064A736
Person / Time
Site:	Palisades
Issue date:	04/27/1995
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18064A735	List: ML18064A734 ML18064A736
References
NUDOCS 9505050215
Download: ML18064A736 (5)

Text

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ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 SAFETY VALVE SETTING LIMITS TECHNICAL SPECIFICATIONS CHANGE REQUEST Proposed Technical Specification Pages April 27, 1995 4 Pages f - --- - -- -- - -

9505050215 950427 PDR ADOCK 05000255 P - PDR

PA~ADES PLANT TECHNICAL SPECIFICA~NS 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 COOLANT SYSTEM PRESSURE 2-1 2.3 LIMITING SAFETY SYSTEM SETTINGS - RPS 2-1 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 B2-2 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 3-1 b 3.1.1 Operable Components 3-lb Figure 3-0 AS I Limit for Tinlet function 3-3a 3.1.2 Pressure - Temperature 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 3.1.5 Primary Coolant System Leakage Limits 3-20 3.1.6 Maximum PCS Oxygen and Halogen Concentration 3-23 3.1. 7 Primary and Secondary Safety Valves 3-24a 3.1.8 Over Pressure Protection Systems 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 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 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 i

Amendment No.

3.-1.7 e

Primary and Secondary Safety Valves Specification 3.1.7.1 The pressurizer safety valves shall be operable as specified in Table 3.1.7-1.

Applicability Specification 3.1.7.1 is applicable when the plant is operating above COLD SHUTDOWN.

Action With one or more pressurizer safety valves inoperable,

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

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 />.

Table 3.1.7-1 pressurizer Sfa et y Va1ve L'ft l Sett'ings Valve Number Lift Setting*

RV-1039 2580 psia +/- 3%

RV-1040 2540 psia +/- 3%

RV-1041 2500 psia +/- 3%

• After testing or valve maintenance which could affect the setting, it shall be reset to within 1% of the nominal setpoint prior to being returned to service.

3-24a Amendment No.

3 .~I. 7 Primary and S~ndary Safety Valves (continue~

Specification 3.1.7.2 A minimum of 23 main steam safety valves shall be operable as specified in Table 3.1.7-2.

Applicability Specification 3.1.7.2 is applicable when the plant is operating above COLD SHUTDOWN.

Action With more than one main steam safety valve inoperable,

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

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 />.

Table 3.1.7-2

• St earn Sf Mam a et y Va1ve L'ft 1 Sett'rngs Valve Number Lift Settinq*

RV-0701, RV-0702 RV-0703, RV-0704 1025 psig +/- 3%

RV-0705, RV-0706 RV-0707, RV-0708 RV-0709, RV-0710 RV-0711, RV-0712 1005 psig +/- 3%

RV-0713, RV-0714 RV-0715, RV-0716 RV-0717, RV-0718 RV-0719, RV-0720 985 psig +/- 3%

RV-0721, RV-0722 RV-0723, RV-0724

• After testing or or valve maintenance which could affect the setting, it shall be reset to within 1% of the nominal setpoint prior to being returned to service.

3-24b Amendment No.

,3."l. 7 Primary and S~ndary Safety Valves (continue~

Basis:

The primary and secondary safety valves provide overpressure protection for the primary coolant system and the secondary system. The setpoints and relief capacities of these safety valves limit the primary and 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 primary and secondary systems. The analysis performed to support these specifications assumed complete loss of turbine generator load, without111 simultaneous reactor trip on turbine trip, while operating above rated power

• The only pressure 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 steam 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 tolerance including an inoperable secondary safety valve in any one setpoint banknri 21

• Following valve testing or reinstallation 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 ffG Shaw (SPC} to RJ Gerling (CPCo} dated July 26, 1993.

3-25 Amendment No. 3-J., -l+e, -l-18,