ML19321A315

Electrical,Instrumentation & Control Features of Quench Spray Sys Mods - Beaver Valley Nuclear Station,Unit 1.

ML19321A315
Person / Time
Site:	Beaver Valley
Issue date:	05/28/1980
From:	Mays S EG&G IDAHO, INC., EG&G, INC.
To:	Shemanski P Office of Nuclear Reactor Regulation
References
CON-FIN-A-6256 EGG-EA-5174, TAC-7170, NUDOCS 8007230172
Download: ML19321A315 (7)

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EGG-EA-5174 June 1980 ELECTRICAL, INSTRUMENTATION AND CONTROL FEATURES

, OF QUENCH SPRAY SYSTEM MODIFICATIONS - BEAVER t

VALLEY NUCLEAR STATION, UNIT 1 S. E. Mays l

U.S. Department of Energy l Idaho Operations Office

• Idaho National Engineering Laboratory l

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This is an informal report intended for use as a preliminary or working document 1

MC Research anc' iecanical Prepared for the ASSislanCO SOPCII U.S. Nuclear Regulatory Comission g Under DOE Contract No. DE-AC07-761D01570 b b E O idaho FIN No. A6256 Y 8 0 0 7R3 q/72_ ___ _ -_______ . _ .

hEGsG,....,,,e FORM EG%G 398 ee. nie, INTERIM REPORT Accession No.

Report No. EGG-EA-5174 9:ntract Program or Project

Title:

Electrical, Instrumentation, and Control Systems Reviews (On-Call Technical Assistance)

Subject of this Document:

Electrical, Instrumentation, and Control Features of Quench Spray System Modifications Type of Document:

Informal Report Author (s):

S. E. Mays D:ta of Document:

June 1980 Responsible NRC Individual and NRC Office or Division:

. Paul C. Shemanski, NRC-DOR This document was prepared primarily for preliminary or internal use. it has not received full review and approva!. Since there may be substantive changes, this document should not be considered final.

EG&G Idaho, Inc.

Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C.

Under DOE Contract No. DE AC07-761D01570 NRC FIN No. A6256 r .A ,,1 INTERIM REPORTi ', 4!@l 1- w

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TECHNICAL EVALUATION REPORT ELECTRICAL, INSTRUMENTATION, AND CONTROL FEATURES OF QUENCH SPRAY SYSTEM MODIFICATIONS BEAVER VALLEY NUCLEAR STATION UNIT 1 Duquense Light Docket No. 50-334 i

S. E. Mays Reliability and Statistics Branch Engineering Analysis Division EG&G Idaho, Inc.

5/28/80 TAC No. 7170

r TECHNICAL EVALUATION REPORT ELECTRICAL, INSTRUMENTATION, AND CONTROL FEATURES OF QUENCH SPRAY SYSTEM MODIFICATIONS

, BEAVER VALLEY NUCLEAR STATION UNIT 1

1.0 INTRODUCTION

The purpose of this review is to determine whether or not the modifi-cations to the Quench Spray System at Beaver Valley 1 meet the licensing guidelines contained in Standard Review Plant (SRP) 7.3. Specifically, this review will examine the modifications to determine if they are auto-matica11y initiated, are electrically redundant and independent, are in '

compliance with the single failure criteria, and are testable during reac-tor operations.

2.0 CRITERIA

• SRP 7.3 provides guidelines for review of electrical, instrumentation, and control system (EICS) features of Engineered Safety Features (ESF)

Systems. IEEE Standard 279 and Regulatory Guide (RG) 1.53 contain single failure criteria. Redundancy and independence criteria are in IEEE Stan-dard 279 and RC 1.6. Design criteria for thermal overload protection for motor-operated valves are in RG 1.106. Testing requirements are contained in IEEE Standard 279 and RG 1.118, 3.0 DISCUSSION AND EVALUATION r

The modification to the Quench Spray (QS) system at Beaver Valley 1 includes the addition of two chemical injection loops consisting of two ,

positive displacement Chemical Injection Pumps (CIPs) in each loop which take suction on the Chemical Addition Tank (CAT) and discharge to the suc-tion of.the QS system pumps. Each loop has one motor-operated valve (MOV) between the CIPs discharge and the QS system pump suction valve. Figure 1

, is a simplified drawing of this section of the QS system.

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4 One loop of th modification (two CIPs and one MOV) recieves motive and control power :com a bus powered by either offsite power or one of the two emergency diesel generators. The other loop recieves power from an identical redundant bus. The pumps and valves in one loop recieve actu-

, ation signals from sensors and relays which are independent of those used to actuate the other loop. Thus, the two loops are electrically indepen-dent and are redundant. The CIPs start upon receipt of a containment iso-lation phase B (CIB) signal from the ESF actuation system provided that there is sufficient level in the CAT, QS system flow is adequate, and there is no CIP motor overload. The CIPs will automatically stop on low QS sys-tem flow, motor overload, or low CAT level. The capability to manually start or stop the CIPs is bypassed by the CIB signal. One CIP per loop will stop on a signal from the cutback control valve in the QS system loop provided that the other CIP is running and no automatic stop signals, men-tioned above, have occurred'. Pump running or not running indication is provided in the control room. There is no local control station outside the control room for operation of these pumps.

The CIP discharge MOV for each CIP pair will open on receipt of a CIB signal provided that there is sufficient level in the CAT and there is no

, motor overload. The valve will close if the control switch is positioned to close and no CIB signal is present or whenever there is low level in the CAT and no motor overload. The MOV overload protection is not bypassed when a CIB signal is received as required by RG 1.106. A light in the control room indicates whenever the valve is not fully closed. There is no local control station for electrical operation of these valves outside the control room.

3.1 Evaluation. Since only one loop of the chemical injection modi-1 fication is needed to provide the necessary safety function and the two CIP loops are electrically redundant and independent, there are no single fail-ures of EICS featurcs that would render this portion of the QS system inoperable.

Each chemical injection loop is testable during reactor operation by manual positioning of valves to permit the CIPs to discharge back to the 3

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CAT. However, no provisions exist to automatically restore the valve posi-tions to their normal line-up in the event of a CIB signal during testing.

This would allow for a reduced volume of chemical additics os the QS system pumps and does not meet the requirements for testing of ESF systems con-tained in IEEE Standard 279 and RG 1.118. Furthermore, there is no indica-tion, as required by RG 1.47 and BTP ICSB 21, of the system being in this

, condition which bypasses the protective function.

Thermal overloads for the CIPs discharge MOVs are not bypassed upon receipt of a CIB signal as required by RG 1.106.

4.0

SUMMARY

The EICS features of modifications to the QS system at Beaver Valley 1 meet the requirements of SRP 7.3 for being automatically initiated, redun-dant, electrically independent, and single failure free. Bypassing the protective function of the chemical injection loops during periodic testing 4

is not indicated in the control room and the bypassed condition is not automatically removed upon receipt of a CIB signal as required by IEEE Stan-dard 279, RG 1.118, RG 1.47, and BTP ICSB 21. Thermal overloads for the CIPs discharge MOVs are not bypassed upon receipt of a CIB signal as required by RG 1.106.

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5.0 REFERENCES

1. Duotense Light lett>r (Woolever) to NRC (Schwencer), " Revision to NPSH Modifications and Revised Technical Specifications," dated February 27, 1980.

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2. NUREG-75/087, Standard Review Plan 7.3.

3. Beaver Valley 1 Drawings 8700-RE-21N4-0A2; 8700-RE-21N4-1A4; ll700-LSK-29-4A-3A-7, -4B-3A-7, -4C-3A-7, -4D-3A-7.

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