ML20052C518
| ML20052C518 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 03/31/1982 |
| From: | Farmer F EG&G, INC. |
| To: | Scholl R Office of Nuclear Reactor Regulation |
| References | |
| CON-FIN-A-6425-1, TASK-06-07.C3, TASK-6-7.C3, TASK-RR EGG-EA-5802, NUDOCS 8205050075 | |
| Download: ML20052C518 (7) | |
Text
EGG-EA-5802 March 1982 A)ke feSedre auskf0fYCbnCob SS'S fasce f/o$
fpg SYSTEMATIC EVALUATION PROGRAM, TOPIC VI-7.C.3, PWR Appg ef LOOP ISOLATION VALVES POWER AND CONTROL SYSTEM AS/6 DESIGN, HADDAM NECK m
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I This is an informal report intended for use as a preliminary or working document Prepared for the U.S. Nuclear Regulatory Comission Under DOE Contract No. DE-AC07-761001570 FIN No. A6425-1 EGnGw n.
9 8205050075 820331 PDR RES 8205050075 PDR
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FORM EGSG-398
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- INTERIM REPORT Accession No.
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EGG-EA-5802 Report No.
Contract Program or Project
Title:
Electrical, Instrumentation, and Control Systems Support for the Systematic Evaluation Program (II) o Subject of this Document:
Systematic Evaluation Program, Topic VI-7.C.3, PWR Loop Isolation Valves Power and Control System Design, riaddam Neck Type of Document:
Informal Report Author (s):
F. G. Farmer Date of Document:
March 1982 Responsible NRCIDOE Individual and NRCIDOE Office or Division:
Ray F. Scholl, Division of Licensing, NRC This document was prepared primarily for preliminary or internat use. it has not received full review and approval. Since there may be substantive changes, this document should not be considered final.
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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.
A6425-1 l
j INTERIM REPORT l
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1 0191J SYSTEMATIC EVALUATION PROGRAM TOPIC VI-7.C.3 PWR LOOP ISOLATION VALVES POWER AND CONTROL SYSTEM DESIGN HADDAM NECK Docket No. 50-213 March 1982 F. G. Farmer EG&G Idaho, Inc.
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3-2-82
ABSTRACT This SEP Technical Evaluation, for the Haddam Neck Plant, reviews the primary loop isolation valve power and control system design.
FOREWORD This report is supplied as part of the " Electrical, Instrunentation, and Control Systems Support for the Systematic Evaluation Program (II)"
being conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Licensing by EG&G Idaho, Inc.,
Reliability & Statistics Branch.
The U.S. Nuclear Regulatory Commission funded the work under the authorization B&R 20-10-02-05, FIN A6425-1.
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i SYSTEMATIC EVALUATION PROGRAM TOPIC VI-7.C.3 PWR LOOP ISOLATION VALVES POWER AND CONTROL SYSTEM DESIGN HADDAM NECK "0
INTRODUCTION The objective of this review is to determine if the primary loop iso-lation valve power and control system is in compliance with current licens-ing criteria.
The specific requirements for loop isolation valve power and control system design derive from IEEE 279-1971, which states that the bypass of a protective function will be removed automatically whenever permissive con-ditions are not met and which also assures that a single electrical failure or operator error will not result in lgss of capability of the protection systemtoperformitssafetyfunctiag.
The criteria are further defined in Branch Technical Position ICSB 18.
2.0 CRITERIA Current licensing criteria from ICSB 18 are:
1.
Failures in both the " fail to function" sense and the
" undesirable function" sense of components in electri-cal systems including valves and other fluid system components should be considered in designing against a single f ailure, even though the valve or other fluid system component may not be called upon to function in a given safety operational sequence.
2.
Where it is determined that failure of an electrical system component can cause undesired mechanical motion of a valve or other fluid system component and this motion results in loss of the system safety function, it is acceptable, in lieu of design changes that also may be acceptable, to disconnect power to the electric l
systems of the valve or other fluid system component.
i The plant Technical Specifications should include a list of all electrically-operated valves, and the l.
required positions of these valves, to which the I
requirement for removal of electric power is applied in order to satisfy the single failure criterion.
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l 3.
Electrically-operated valves that are classified as l
" active" valves, i.e., are required to open or close in various safety system operational sequences, but are manually-controlled, should be operated from the main i
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t control room. Such valves may not be included among those valves from which power is removed in order to-
. meet the single f ailure criterion unless (a) electrical power can be restored to the valves from the main con-trol room, (b) valve operation is not necessary for at least ten minutes following occurrence of the event requiring such operation, and (c) it is demonstrated that there is reasonable assurance that all necessary operator actions will be performed within the time shown to be adequate by the analysis..The plant Tech-nical Specifications should include a list of the required positions of manually-controlled, electrically-operated valves and should identify those valves-to which the requirement for removal of electric power is applied in order to satisfy the single failure criterion.
4.
When the single failure criterion is satisfied by removal of electrical power from valves described in 2.
and 3. above, these valves should have redundant posi-tion indication in the main control room and the posi-tion indication system should, itself, meet the single
.L failure criterion.
5.
The phrase, " electrically-operated valves," includes both valves operated directly by an electrical device (e.g., a motor-operated valve or a solenoid-operated i
valve) and those valves operated indirectly by an elec-trical device (e.g., an air-operated valve whose air supply is controlled by an' electrical solenoid valve).
3.0 DISCUSSION AND EVALUATION which has two motor-operated loop isolation valves.glant loops, each of 3.1 Discussion. Haddam Neck has four main co Plant Technical Specifications require at least one loop operating above 1% power, at least 65% power.g operating above 10% power, ar.J all four loops operating above three loop The Technical Specifications do not require power to be i
removed from the loop isolation valves. No interlocks or adninistrative procedures exist to prevent inadvertent closure of loop isolation valves i
during power operation. Additionally, each valve operate switch uses only a singlesetofcontactstoinitiatevalveclosure,andgs,therefore,poten-tially subject to a failure which would close a valve.
The steam line break detection logic will not be compromised by isolation of any loop.6,7 3.2 Evaluation. The Haddam Neck loop isolation valve power and con-trol system design includes the potential for a single failure, either i
human or mechanical, to cause an inadvertent loop isolation valve closure.
l Therefore, the design does not meet current licensing criteria.
4.0 SUPNARY i
The Haddam Neck loop isolation valve power and control system design is susceptible to single f ailure, and thus, does not comply with current licensing criteria.
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5.0 REFERENCES
1.
IEEE Standard 279, " Criteria for Protection Systems for Nuclear Power Generating Stations 2.
Branch Technical Position ICSB 18, " Application of the Single Failure Criterion to Manually-Controlled Electrically-Operated Valves."
3.
Haddam Neck drawing 16103-26007, Revision 11, dated 2-25-78.
4.
" Technical Specifications for the Connecticut Yankee Atomic Power Company Haddam Neck Plant," Amendment 20, paragraph 3.3.C.
5.
Haddam Neck drawing 16103-32112, Sheet 27, Revision 4, dated 10-22-68.
6.
Letter, CYAPCo (Counsil) to NRR (Crutchfield), dated 7-22-81.
7.
Haddam Neck drawing 16103-32011, Sheet llc, Revision 11, datad 2-5-79.
8.
Letter, CYCAPCo (Counsil) to NRR (Crutchfield), dated 2-12-82.
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