ML20236A960

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Proposed Tech Specs,Revising Reactor Trip & ESFAS Instrumentation Trip Setpoints & Allowable Values
ML20236A960
Person / Time
Site: Beaver Valley
Issue date: 03/02/1989
From:
DUQUESNE LIGHT CO.
To:
Shared Package
ML19302D676 List:
References
NUDOCS 8903200235
Download: ML20236A960 (24)
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Text

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ATTACHMENT B 1

Proposed Unit 1 Technical Specification Change No. 1A-156 i Safety Analysis 4 Description of Change: The proposed amendment would revise the  !

Reactor Trip System and Engineered Safety Features (ESF) Actuation System Instrumentation Trip Setpoints and Allowable Values based upon the results of a re-analysis of the instrument channel inaccuracies.

The trip setpoints that would be revised include the Turbine Impulse Chamber Pressure P-13 Interlock, the Refueling Water Storage Tank (RWST) Level-Low and auto QS flow reduction for safety injection l transfer from injection to recirculation, the Containment Pressure High-High, Containment Pressure Intermediate High-High and the Emergency Buses Undervoltage settings for Degraded Voltage. In addition numerous sotpoint Allowable Values would be revised consistent with the calculated inaccuracies. -

Safety Analysis: The setpoints for the various functions in the Reactor Trip System and ESF Actuation System are determined on the basis of the trip settings assumed in the FSAR accident and transient analyses. The required settings correspond to the trip points assumed in these analyses less the required allowance for instrument inaccuracies.

An analysis has been performed to update the calculation of these instrument inaccuracies using a more current methodology for i determining the required trip setting and allowable value limits.

The methodology used is described in detail in Westinghouse WCAP-11419 (proprietary) and WCAP-11420 (non-proprietary). This methodology is the same as that used for Beaver Valley Unit No. 2 (WCAP-11366). In addition to determining the required trip setpoints and Allowable Values, this methodology includes an optional provision for determining the OPERABILITY of a channel when its trip setpoint is found to exceed the Allowable Value (le equation 2.2-1). We have elected not to incorporate this provision into the Unit 1 Technical '

Specifications at this time.

A review of the Unit 1 FSAR was performed to ensure that the 1 safety analysis limits used for generation of the required setpoints in WCAP-11419 is consistent with our accident analyses. FSAR Table 14D-3 lists trip points assumed in the accident analyses. The safety analysis limits used in WCAP-11419 are consistent with the FSAR with the following exceptions listed below:

1. Pressurizer pressure-low reactor trip 1845 psig (FSAR) 1920 psig (WCAP) i 1920 psig was the most limiting value from the LOCA (1845 psig) and non-LOCA (1920 psig) for the setpoint development. The most limiting value is determined by the value closest to the c:n , ting pressure.  ;

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' ATTACHMENT B .

- Page 2:

2. Pressurizer pressure-high reactor trip 2410 psig (FSAR)  :

2436 psig (WCAP) )

The high pressurizer pressure reactor trip is actively credited in the Loss of Load Transient. A safety analysis setpoint value of 2410 psig was assumed for this event. A safety analysis setpoint value of 2436 psig is required in order to maintain the current technical specification setpoint of 2385 psig. Based on a performed safety evaluation, an increase from 2410 psig to 2436 psig will have a-minimal impact on the FSAR analysis results.

3. Steam generator hi-hi level turbine trip 75% (FSAR) 80% (WCAP)

As part of the safety analyses, the 80% value was used in the Feedwater System Malfunction transient event.

4. RCP Undervoltage reactor trip 68% of nominal (FSAR)

No. specific setpoint assumed in the safety analysis (WCAP)

A specific setpoint value is not assumed in the Loss of Flow analysis. The analysis assumes RCP bus' voltage is lost at time zero and RCP begins to coastdown. Reactor trip is assumed to occur on RCP undervoltage following an appropriate delay time. A value greater than 60% of RCP bus voltage is assumed for setpoint development.

This is based on maintaining a minimum voltage for RCP motor. torque and full loop flow.

The following is a discussion on changes to Table 2.2-1 and Table 3.3-4 of the Technical Specifications:

i

1. Containment Pressure High-High and Intermediate High-High The Containment Pressure High-High and Intermediate High-High l safety analysis limits are 10 psig and 5.0 psig respectively. l The current trip settings for these items have not addressed )'

instrument error. The proposed change revises these trip setpoints and allowable values to ensure that when instrument '

channel inaccuracies are considered the safety analysis limits l will not be exceeded. The current Containment Pressure-High trip setting has also not considered instrument error.

However, a safety analysis has been performed which revises the safety analysis limit for Containment Pressure-High from 1.5 psig to 3.5 psig. With this revised safety analysis limit the current trip setpoint of 1.5 psig is adequate to ensure l that with instrument inaccuracies considered the safety analysis limit will not be exceeded.

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ATTACHMENT B Page 3

2. Turbine Impulse Chamber Pressure P-13 Interlock l The proposed change revises the Turbine Impulse Chamber Pressure P-13 Interlock. This change does not change the actual trip setting but simply revises the method of presenting the required setting from impulse pressure in psig to % rated thermal power equivalent.
3. 4KV and 480V Emergency Duses Undervoltage i The proposed change also revises the 4KV and 480V Emergency Buses Undervoltage setting for degraded voltage. The revised setpoints are made to be consistent with the methodology used to calculate instrument ch6nnel inaccuracies and does not impact on the margin to any safety analyses.
4. RWST Level Low and QS Flow Reduction The RWST Level Low and QS Flow Reduction setpoints were revised in WCAP 11419 from 19'2-1/2" i 6" and 11'0" i 3" to 2 19'2-1/2" and 2 11'0" respectively. These setpoints would ensure that the accident analysis requirements for containment depressurization are met. However, as discussed in the BVPS Unit 1 FSAR (Section 6.3.2.1), the RWST Level-Low setpoint also ensures that the containment sump level will be sufficient to provide adequate NPSH for the Low Head Safety Injection (LHSI) Pumps after the transfer to recirculation.

Therefore, this setpoint must also ensure that a minimum amount of water is directed into the containment and sump prior to transfer to recirculation. This setpoint, therefore, has both an upper and lower safety limit. In addition, the RWST Level channel inaccuracies (channel statistical allowance of 2.6% or 17") calculated in WCAP 11419 were greater than the inaccuracies assumed in our current accident analyses (i l' for transfer to recirculation and i 6" for QS flow reduction). The affected accident analyses for containment depressurization and LHSI Pumps NPSH requirements were therefore, re-analyzed using revised safety limits of i 18" for both setpoints. The results of this analysis indicated that the containment depressurization design basis and the LHSI Pumps NPSH requirements continues to be met.

However, to satisfy the analysis requirements it was necessary to lower the RWST Level-Low setpoin' by 6" to 18' 8-1/2" and the RWST Level Auto QS Flow Reduction setpoint by 1 1/2' to 9' 6". With this re-analysis, these setpoints are now within the bounds of our safety limits when the instrument channel inaccuracies calculated by WCAP 11419 are considered. New allowable values were also calculated for these setpoints using the methodology provided in WCAP 11419. The Unit 1 FSAR will be updated to include the revised analysis results.

ATTACHMENT B Page 4 l

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1

5. Tables 2.2-1 and 3.3-4 Allowable Values l Various Allowable Values of Tables 2.2-1 and 3.3-4 are revised in the proposed change. These changes are based on the results of WCAP 11419 and the methods described in that report for calculating Allowable Values. Some are more restrictive and some less restrictive than what are currently in the Technical Specifications. The Allowable Values provided will ensure that if the measured setpoint value is less than the Allowable Value the instrument channel is well within the accuracy allowance.

In summary, the proposed setpoint and Allowable Value changes will ensure that the trip setpoints assumed in the Beaver Valley

~

Unit 1 safety analyses will be valid when the required channel instrument inaccuracies are considered. The method for determining these inaccuracies is consistent with previously approved methods for calculating instrument error. These proposed changes are therefore considered safe.

, ATTACHM_ENT C No Significant Hazard Evaluation Proposed Technical Specification Change No. 1A-156 Basis for Proposed No Significant Hazards Considera' tion Determination: The Commission has provided standards for determining whether a significant hazards consideration exists (10 CFR 50.92(c)). A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.

The proposed change does not involve a significant hazards consideration because: -

1) The basis of the Reactor Trip System and ESF Actuation System trip settings are the values assumed in the Safety Analyses.

The proposed changes to the trip settings and Allowable Values ensures that these safety analysis limits are maintained when the appropriate allowances for instrument channel inaccuracies are considered. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

\

2) The proposed changes are made to ensure that the safety analyses limits assumed in the analysis remain valid by assigning the appropriate values for instrument channel inaccuracies to the trip settings and allowable values. This change does not involve any plant equipment or design change.

Therefore, the probability of an accident or a malfunction of a different type than previously evaluated would not be created.

3) This change will not affect the assumptions or consequences of any safety analysis presented in the FSAR. Therefore, the ,

change will not involve a significant reduction in a margin of l safety.

Based on the above considerations, it is proposed to characterize .

the change as involving no significant hazards consideration.  !

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