ML18064A584

Proposed Tech Specs Addresing Required Settings & Allowable as Found & as Left Tolerances for Primary & Secondary Safety Valves

ML18064A584
Person / Time
Site:	Palisades
Issue date:	01/13/1995
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18064A583	List: ML18064A582 ML18064A584 ML18064A590
References
NUDOCS 9501300187
Download: ML18064A584 (9)

Text

I, PALISADES PLANT TECHNICAL SPECIFICATIONS II I

TABLE OF CONTENTS

• SECTION 1.0 1.1

1.2 DESCRIPTION

DEFINITIONS OPERATING CONDITIONS MISCELLANEOUS DEFINITIONS PAGE NO 1-1 1-1 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-lb 3 .1.1 Operable Components 3-lb Figure 3-0 ASI Limit for Tinlet Function 3-3a 3 .1. 2 Heatup and Cooldown Rates 3-4 Figure 3-1 Pressure - Temperature Limits for Heatup 3-9 Figure 3-2 Pressure - Temperature Limits for Cooldown 3-10 Figure 3-3 Pressure - Temperature Limits for Hydro 3-11 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 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 Amendment No.

~501300187 950113 I PDR ADOCK 05000255 v p PDR

3".1. 7 Primary and Secondary Safety Valves Speci fi cation 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 Safety Valve Lift Settin s Valve Number Lift Settin

• RV-1039 2580 sia +/- 3%

RV-1040 2540 sia +/- 3%

RV-1041 2500 sia +/- 3%

• If a safety valve is removed from the piping for valve maintenance or testing, it shall be reset to within 1% of the nominal setting prior to being returned to service .

• 3-24a Amendment No.

3.1.7 Primary and Secondary Safety Valves (continued)

Specification 3.1.7.2 A minimum of 23 main steam safety valves s~all 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 />.

Tab 1e 3 . 1. 7-2 Mam

. St earn Sf a et y Va1ve L'ftl Se tt'rngs Valve Number Li ft Setting*

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 I

• If a safety valve is removed from the piping for valve maintenance I or testing, it shall be reset to within 1% of the nominal setting I prior to being returned to service.

3-24b Amendment No.

Primary and Secondary Safety Valves (continued)

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 bank 11 H21

• Following reinstallation after removal for valve testing or 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 RG Shaw (SPC) to RJ Gerling (CPCo) dated July 26, 1993.

3-25 Amendment No. 3-1:-, !-&, -!+8,

ATTACHMENT 2 Consumers Power Company Pali sades Pl ant Docket 50-255 SAFETY VALVE SETTING LIMITS TECHNICAL SPECIFICATIONS CHANGE REQUEST Existing Page to be Replaced by Proposed Pages 1 Page

THIS PAGE TO BE REPLACED BY PROPOSED PAGES 3-24a, 3-24b, & 3-25 3.1. 7 Primary and Secondary Safety Valves

• Specifications

a. The reactor shall not be made critical unless all three pressurizer safety valves are operable with their lift settings maintained between 2500 psia and 2580 psia (+/- 1%).

b. A minimum of one operable safety valve shall be installed on the pressurizer whenever the reactor head is on the vessel.

c. Whenever the reactor is in power operation, a minimum of 23 secondary system safety valves shall be operable with their lift settings between 985 psig (+/- 30 psig).and 1025 (+/- 3%) psig.

The primary and secondary safety valves pass sufficient steam to limit the primary system pressure to 110 percent of design (2750 psia) following a complete loss of turbine generator load without simultaneous reactor trip while operating at 2650 MWt.! 11 The reactor is assumed to trip on a "High Primary Coolant System Pressure" signal. To determine the maximum steam flow, the only other pressure relieving system assumed operational is the secondary system safety valves.

Conservative values for all system parameters, delay times and core moderator coefficient are assumed. Overpressure protection is provided to the portions of the primary coolant system which are at the highest pressure considering pump head, flow pressure drops and elevation heads.

If no residual heat were removed by any of the means available, the amount of steam which could be generated at safety valve lift pressure would be less than half of one valve's capacity. One valve, therefore, provides adequate defense against overpressurization when the reactor is subcritical.

The total relief capacity of the 24 secondary system safety valves is 11.7 x 10 6 lb/h. This is based on a steam flow equivalent to an NSSS power level of 2650 MWt at the nominal 1000 psia valve lift pressure.

At the power rating of 2530 MWt, a relief capacity of less than 11.2 x 10 6 lb/h is required to prevent overpressurization of the secondary system of loss of load conditions, and 23 valves provide relieving capability of 11.2 x 10 6 l b/h. (1 *21 The overpressurization analysis for the loss of load event ~ 1 supports the specified secondary safety valve lift pressure tolerance. 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 safety valves.

References

{1) Updated FSAR, Section 4.3.4 and 4.3.9.4

{2) ANF-87-150(NP), Volume 2, Section 15.2.1

• 3-25 Amendment No. pJ, 1J%, 118 November 15, 1988

• ATTACHMENT 5 Consumers Power Company Pali sades Pl ant Docket 50-255 SAFETY VALVE SETTING LIMITS TECHNICAL SPECIFICATIONS CHANGE REQUEST Siemens Power Corporation letter; H.G. Shaw (SPC) to R.J. Gerling (CPCo), July 26, 1993 .

2 Pages

.l,_'

SIEMENS

• July 26, 1993 HGS:268:93 Mr. R. J. Gerling, Manager Reactor & Safety Analysis Consumers Power Company Palisades Nuclear Power Plant 27780 Blue Star Memorial Highway Covert, Ml 49043

Subject:

Impact of an Inoperable Secondary Safety Valve on the Palisades Loss of Load Analysis *

Reference:

"Palisades Loss of Load Analysis," EMF-93-0SS(P), April 1993 Palisades Technical Specification 3.1. 7.c. states that operation with a minimum of 23 secondary system safety valves operable is permissible. The loss of load analysis report (Reference) was performed with all 24 secondary system safety valves operable. The purpose of this letter is to demonstrate that operation with 1 secondary system valve out of service will not significantly impact the loss of load analysis* results.

The reference analysis results indicate that the capacity of the 1030.0 psia setpoint safety valve banks is enough to limit the secondary pressure to significantly less than 110% of design pressure (1100 psia). Therefore, the analysis results remain unchanged for an inoperable valve in the banks with setpoints of 1050.6 psia and 1071.2 psia.

An inoperable vaJve in one of the lowest setpoint banks would result in a secondary pressure slightly higher than the 1040.B psia recorded in the referenced analysis report. At most, the maximum possible secondary pressure would be approximately 1051 psia which corresponds to the next vaJve bank setpoint. It is concluded that adequate relieving capacity exists to maintain the secondary pressure below 11 O percent of design pressure when 23 secondary safety valves are operable.

• Siemens Power Corporation Nuclear Division - Headquarters 155 108th Avenue NE, PO Box 90777 Bellevue, WA 98009-0777 Tel: (206) 453-4300 Fax: (206) 453-4446

fl06D Mr. R. J. Gerling

• July 26, 1993 Page 2' SPC concludes- that operation with one secondary safety valve out of service is acceptable. If you have any questions concerning the impact of an Inoperable secondary safety valve on the loss of load analysis results, feel free to contact our Mr. Jim Hulsman at 206-453-4358.

~u~.

H. G. Shaw Contract Administrator sm cc: Mr. TC Berdine (CPCo, Jackson)

Mr. TC Duffy (CPCo, Patfsadest* I Mr. PJ Kluskowski (CPCo, Palisades)

Mr. SF Pierce (CPCo, Palisades)

Mr. JW Hulsman (SPC)