ML20083K314
| ML20083K314 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/31/1984 |
| From: | NUCLEAR UTILITY TASK ACTION COMMITTEE |
| To: | |
| Shared Package | |
| ML20083K289 | List: |
| References | |
| GL-83-28, INPO-84-010, INPO-84-10, NUDOCS 8404160129 | |
| Download: ML20083K314 (86) | |
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E_ F1UtBC ON GENERIC LETTER 83-28, SECTION 2.2.2
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Vendor Equipment Technical Information Program M
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, ; Developed By i Nuclear Utility Task Action Committee r:
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for Generic Letter 83-28, Section 2.2.2 l
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INP0 84-010 (NUTAC)
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O Cop ,,,ht 1984 by Institute of Nuclear Power Operations. All rights reserved. Not for sale. Unauthorized reps.iuction is a violation of applicable law. Reproduction of not more than ten copies by each recipient for its -
interri'. aJe onlyis permitted. ,%
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Publications produced by a nuclear utility task action committee (NUTAC) represent a consensus of the utilities participating in the NUTAC. These pub-lications are not intended to be interpreted as industry standards. Instead, Q the publications are offered as suggested guidance with the understanding that individual utilities are not obligated to use the suggested guidance.
This publication has been produced by the NUTAC on Generic Letter 83-28, Section 2.2.2., with the support of the Institute of Nuclear Power Operations (INP0). The officers of this NUTAC were Chairman Edward P. Griffing and Vice Chairman Walter E. Andrews.
Utilitics that participated in this NUTAC include the following:
Alabama Power Company Nebraska Public Power District American Electric Power Service Corporation New York Power Authority Arizona Public Service Company Niagara Mohawk Power Corporation Arkansas Power & Light Company Northeast Utilities Baltimore Gas and Electric Company Northern States Power Company Boston Edison Company Omaha Public Power District Carolina Power & Light Company Pacific Gas and Electric Company Cincinnati Gas & Electric Company Pennsylvania Power & Light Company The Cleveland Electric Illuminating Company Philadelphia Electric Company Commonwealth Edison Company Portland General Electric Company Consolidated Edison Company of New York, Inc. Public Service Company of Colorado Consumers Power Company Public Service Company of Indiana, Inc.
The Detroit Edison Company Public Service Company of New Hampshire Duke Power Company Public Service Electric and Gas Company Duquesne Light Company Rochester Gas and Electric Corporation O Florida Power Corporation Florida Power & Light Company Sacramento Municipal Utility District South Carolina Electric & Gas Company GPU Nuclear Corporation Southern California Edison Company Georgia Power Company Tennessee Valley Authority Gulf States Utilities Company Texas Utilities Generating Company Houston Lighting & Power Company The Toledo Edison Company Illinois Power Company Union Electric Company Iowa Electric Light and Power Company Vermont Yankee Nuclear Power Corporation Kansas Gas and Electric Company Virginia Electric and Power Company Long Island Lighting Company Washington Public Power Supply System Louisiana Power & Light Company Wisconsin Electric Power Company Maine Yankee Atomic Power Company Wisconsin Public Service Corporation Mississippi Power & Light Company Yankee Atomic Electric Company NOTICE: This document was prepared by a nuclear utility task action committee (NUTAC) with the staff support of the Institute of Nuclear Power Operations (INP0).
Neither this NUTAC, INPO, members and participants of INPO, other persons contrib-uting to or assisting in the preparation of the document, nor any person acting on behalf of these parties (a) makes any warranty or representation, expressed or implied, with respect to the accuracy, completeness, or usefulness of the informa-tion contained in this document, or that the use of any information, apparatus, method or process disclosed in this document may not infringe on privately owned rights, or (b) assumes any liabilities with respect to the use of any information, apparatus, method, or process disclosed in this document.
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EXECUTIVE
SUMMARY
This report was prepared by the Nuclear Utility Task Action Committee (NUTAC) on Generic Letter 83-28 " Required Actions Based on Generic Implications of
! Salem ATWS Events," Section 2.2.2. It describes the Vendor Equipment Tech-
- nical Information Program (VETIP) developed by the NUTAC in response to the i
concerns on vendor information and interface addressed in Section 2.2.2 of the generic letter. VETIP is a program that enhances information exchange and evaluaticn among utilities constructing or operating nuclear power plants and provides for more effective vendor interface. .
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, The NUTAC was comprised of representatives of 56 utilities that are members of the Institute of Nuclear Power Operations (INP0). Staff support for the NUTAC was provided by INP0. This report unanimously presents the final conclusions of the NUTAC and is provided to assist individual utilities in developing specific programs to meet the intent of the generic letter.
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Generic Letter 83-28 was developed following investigations by the NRC on the ;
1 Salem events. As a result of these investigations, the NRC determined that 4 j.
' better control and utilization of information regarding safety-related compo- 4 nents might have helped to prevent these events. The NUTAC identified a i program to better ensure that plant personnel have timely access to such information. l The NUTAC efforts were guided by the recognition that individual utilities have the greatest experience with and are most cognizant of the application of 13 safety-related equipment. Vendor involvement with such equipment is generally N greatest during construction and initial operation of the plant. Vendors are not familiar.with the surveillance or maintenance histories, nor with the y r application of the equipment or its environment. This type of information is il most readily available at the plant level within individual utilities. d p
-l Based on this recognition, the NUTAC investigated the mechanisms currently available to facilitate information exchange among utilities. The NUTAC j
-identified four activities that currently address information about safety- i I!
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related components. These are routine utility / vendor and utility / regulator interchange, and the SEE-IN and NPRDS programs managed by INP0.
It was the assessment of the NUTAC that these existing activities, if properly integrated and implemented, would provide a framework for an overall program to ensure effective communication of safety-related information among all :
utilities. Accordingly, the program developed to accomplish this goal (VETIP) uses the existing efforts as elements of a more comprehensive program.
The VETIP combines these existing programs, incorporating enhancements, with a ,
coordinated program within each utility. A key element of the VETIP is the development by each utility of an active internal program to contribute infor-mation to the NPRDS and SEE-IN Programs and to use the results of these programs.
The effectiveness of the VETIP will be determined by the level of utility par-ticipation in these programs. To implement the VETIP, each utility should assess the type of information currently being provided to NPRDS and SEE-IN and expand the scope of reporting if appropriate. Additionally, each utility should evaluate current administrative controls for reporting information and for disseminating the results of the NPRDS and SEE-IN Programs to the plant level. These administrative controls may require modification to ensure that effective coordination is established. Concurrent with these efforts, enhance-ments will be made to both NPRDS and SEE-IN by INP0 within its present insti-tutional objectives.
i The VETIP has been developed to ensure that nuclear utilities have prompt access to and effective handling of safety-related equipment technical infor-mation. In addition, VETIP is responsive to the intent of Generic Letter 83-28, Section 2.2.2. Further details are provided in the body of this report.
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FOREWORD lh jj On February 22 and 25,1983, during start-ups of the Salem Unit 1 plant, both
'E reactor trip breakers (Westinghouse model DB-50) failed to open on an auto-matic trip signal. As a consequence, the Nuclear Regulatory Commission (NRC) formed an investigating task force to determine the factual information perti-nent to the management and administrative controls that should have ensured proper operation of the trip breakers. The findings and conclusions of the t
j task force are documented in NUREG-0977, "NRC Fact Finding Task Force Report k on the ATWS Events at the Salem Nuclear Generating Station, Unit 1, on r February 22 and 25,1983." A second task force determined the extent to which
! these investigative findings were generic in nature. The NRC subsequently
, issued NUREG-1000, " Generic Implications of ATWS Events at the Salem Nuclear Power Plant" and Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events."
On September 1,1983, a group of utility representatives mat at the offices of the Institute of Nuclear Power Operations (INP0) to discuss the establishment i of an ad hoc utility group to address issues relative to the NRC Generic Letter 83-28, Section 2.2.2. The representatives decided that such a group could provide direction that would be of generic benefit to the utilities and consequently formed the Nuclear Utility Task Action Committee (NUTAC) on Generic Letter 83-28, Section 2.2.2. The specific charter for the NUTAC l (Appendix A) was adopted, and the target date for completion of activities was established as February 1984.
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'Q l. INTRODUCTION The objective of Generic Letter 83-28, Section 2.2.2 (Appendix D), is to improve the safety and reliability of nuclear power generating stations by "
ensuring that the utilities are provided with significant and timely tech-nical information concerning reliability of safety-related components. In -
a typical nuclear station, hundreds of vendors supply the thousands of components that perform safety-related functions. The variations in vintage and design of plants ensure that although common applications of specific components may exist, there are an equal or greater number of 1; unique applications. To attain the objective in a cost-effective and efficient manner, this NUTAC has developed the program outlined in this document. This positive program has been found to be the most realistic "
approach to attain the objective.
The Vendor Equipment Technical Information Program (VETIP) described in this document establishes a more formal interaction among the major organ- ,
izations involved with commercial nuclear power generation. The goal of Q
the interaction is to improve the quality and availability of equipment technical information for use by the utilities. The major components of the VETIP are an information transfer system and a centralized evaluation '
of industry experiences. '
This document provides the unanimous NUTAC position on the guidelines for an effective technical information program. The determination of each '
individual utility to support and utilize these guidelines is the key to the effectiveness of this program for the industry as a whole. The pro- .
gram does not require the use of nor prescribe standard administrative ;i
- procedures, but it allows the use of plant-specific procedures compatible ,
- with the utility's internal organization and needs. However, the recom- ;
q mendations in this document provide the basis for a uniform industry response to NRC questions and requirements relative to a technical infor-
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mation program. This program will be beneficial to the utilities and, at
- the same time, it will be responsive to Section 2.2.2 of the NRC Generic {
Letter 83-28.
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- 2. ACRONYMS AND DEFINITIONS 2.1 Acronyms A/E Architect-Engineer AE00 Office of the Analysis and Evaluation of Operational Data
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IEB, IEN Inspection and Enforcement Bulletins and Notices, issued by the NRC IEEE Institute of Electrical and Electronics Engineering INP0 Institute of Nuclear Power Operations LER Licensee Event Report, issued by a utility MOR Monthly Operating Report NPROS Nuclear Plant Reliability Data System NRC Nuclear Regulatory Commission NSAC Nuclear Safety Analysis Center NSSS Nuclear Steam Supply System t NUTAC Nuclear Utility Task Action Committee 0&MR Operations and Maintenance Reminder PRA Probabilistic Risk Assessment QA Quality Assurance
, SEE-IN Significant Event Evaluation and Information i Network
[ SER Significant Event Report SOER Significant Operating Experience Report 4 VETIP Vendor Equipment Technical Information I Program l
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2.2 Definitions u.,'
Component - A component is a mechanical or electrical assembly (including instruments) of interconnected parts that constitutes an identifiable device or piece of equipment. Examples of electrical components include a drawout circuit breaker, a circuit card, instru-ments, or other subassemblies of a larger device that meet this definition. Examples of mechanical components include valves, piping, pumps and pressure vessels, and associated prime movers and/or operators.
Equipment Technical Information (ETI) - For the purposes of this report, this term includes, as a minimum, the following documenta-tion:
o vendor-supplied engineering and technical information (drawings, manuals, etc.) and changes thereto
,, o equipment qualification data (provided by the equipment vendor or
'J qualification lab) o industry-developed information, including utility and NRC-originated information (NPRDS, SER, IEB, IEN, etc.)
NUCLEAR NETWORK"* - An information service provided through INP0.
(NUCLEAR NETWORK replaced NUCLEAR NOTEPAD.)
NUREG - These are guidance documents that are issued by the NRC.
Safety-Related - Safety-related structures, systems, and components are those relied upon to remain functional during and following ,
design basis events to ensure (1) the integrity of the reactor cool-ant pressure boundary, (2) the capability to shut down the reactor and maintain it in a safe shutdown condition, and (3) the capability
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to prevent or mitigate the consequences of accidents that could t-result in potential off-site exposures comparable to the guidelines I of 10 CFR Part 100.
ky (j Vendor - For the purposes of this report, this term is used to iden-l tify the manufacturer of the component concerned and/or those who f provide the related equipment technical information.
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] 3. VENDOR EQUIPMENT TECHNICAL INFORMATION PROGRAM (VETIP) DESCRIPTION The VETIP includes interactions among the major organizations involved with commercial nuclear power generation. As illustrated in Figure 1, a utility exchanges safety-related equipment information with vendors, NRC, INP0, and other utilities via reports, bulletins, notices, newsletters, and meetings. The purpose of these information exchanges is to share equipment technical information to improve the safety and reliability of nuclear power generating stations. The NUTAC concluded that the lack of I information is not a problem, but that the various information systems available are not integrated properly. The purpose of VETIP is to ensure that current information and data will be available to those personnel responsible for developing and maintaining plant instructions and pro-cedures. These information systems and programs currently exist and are capable of identifying to the industry precursors that could lead to a Salem-type event. VETIP is an industry-controlled and mainly hardware-oriented program that does not rely on vendor action, other than the NSSS supplier, to provide information to utilities. Instead, VETIP provides o
j information developed by industry experience through SERs and SOERs to the vendor for comment before it is circulated to the utilities concerned.
, The majority of information provided by vendors is commercial in nature.
This usually is provided voluntarily by the vendor, but does little to improve the safety or reliability of existing equipment.
>- A vendor-oriented program to provide information that would improve the safety and reliability of existing equipment relies on the vendor having
! an internal program to develop the information. Such programs typically are not in existence. Following design and qualification testing, vendors normally do not continue extensive testing or engineering programs in anticipation of equipment problems. Subsequent failures discovered during operations require several steps to complete the information feedback loop. For example, when a problem occurs and a local vendor represen-tative provides a solution, he would have to provide that information to the vendor headquarters. Then, the headquarters would need a tracking h program to identify a trend and subsequently a program to provide the information to the industry. In addition, the vendor often is not in the
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best position to analyze the failure. The vendor is not always aware of the component's application and environment nor its maintenance and sur-veillance history.
The VETIP recognizes that the utility user is in a unique position. The utility user alone has immediate access to the maintenance and surveil-lance history of the equipment. The utility, not the manufacturer, knows the component's actual application and environment. The utility is the primary source of information on the failure, and the utility has the greatest need for the solution. As such, the utility is the central organizer in any approach to the solution, whether or not the manufacturer gets involved. The utility is in the position to know of the failure analysis and its solution at the earliest possible time. The utility can then disseminate the information to other utilities, with an indication of its significance and urgency.
By sharing the operating history, problems, and solutions within the nuclear industry, independent f any n rmal vendor contacts, the other O users will be informed in a much more timely and uniform way. In this way, the distribution of information is controlled entirely by the nuclear utility industry. The programs that comprise the VETIP currently are in existence. The recommended enhancements contained within this report are suggested ways to improve the current use and application of these exist-ing programs.
3.1 _ Existing Programs The existing systems and programs included in the VETIP are the Nuclear Plant Reliability Data System (NPRDS) and the Significant Event Evaluation and Information Network (SEE-IN), both managed by INP0. Also, the VETIP includes existing programs that the utilities now conduct with vendors and other sources of ETI, particularly the NSSS vendor interaction programs and the NRC reporting programs that disseminate significant failure information. Utility-vendor inter-action is further enhanced by the INP0 supplier participant practices.
g Through participation in this program, NSSS vendors and A/E firms are working toward greater participation in the NPRDS and SEE-IN Programs.
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( 3.1.1 Nuclear Plant Reliability Data System (NPRDS)
NPRDS is an industrywide system managed by INP0 for monitoring the performance of selected systems and components at nuclear
' power plants. INP0 member utilities have agreed to partici- ;
pate in the program. United States plants in commercial '
operation (except for six atypical, early vintage units) supply basic engineering information and subsequent failure data on the selected systems and components (typically six to seven thousand components from soae 30 systems per unit). The value of NPRDS lies in the ready availability of this data base to operation and engineering groups for a broad range of applications. The criteria used to determine the scope of NPRDS reports are as follows:
o systems and components that provide functions necessary for accident mitigation o systems and components for which loss of function can initiate a significant plant transient
- O Uniform scoping and reporting criteria are set forth in the Nuclear Plant Reliability Data System (NPRDS) Reportable System and Component Scope Manual (INPO 83-020) and in the Reporting Procedures Manual for the Nuclear Plant Reliability
.i Data System (INPO 84-011). ,
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- To support the benefits that can be obtained from NPRDS usage, b utilities submit three kinds of information to the NPRDS data base
- engineering / test information, failure reports, and f
operating history. Ti:e engineering / test record on a component contains information necessary to identify the component-and
-its^ application,isuch as manufacturer, model' number, operating ,
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- environment, size, horsepower, and test frequencies. The information is submitted when the component'is.placed in' <
service and.is stored in the' data base. If that component fails to perform as intended, a report is submitted containing n .
a description of'the failure mode and cause the failure's V offact on plant operations, corrective actions taken and other- l
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l information necessary to assess the failure. On a quarterly
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basis, utilities submit information on the number of hours the plant is in different modes of operation. This information is used in conjunction with the engineering and failure reports to generate failure statistics for systems and components.
The data is retrievable from a computer, and the engineering
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and failure information can be combined in various ways. A l search of the failure records can identify problems experi- f enced with components in other plants and the corrective l i
actions taken. There are several hundred searches of the data base in a typical month. Following are some example uses of the data base:
Utility and Plant Staffs
' o accessing comprehensive equipment history files to support' maintenance planning and repair o avoidance of forced or prolonged outages by identifying O
other plants with similar or identical equipment that may have spares for a possible loan o determination of spare parts stocking, based on industry mean time between failures j
o comparison of component failure rates at a given plant with j
l the industry average failure rates 4
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o identification of common failure modes and causes o selection of vendors based on component application and j performance o identification of component wearout and aging patterns.
h I o studies of component performance as a function of operating characteristics, such as test frequency and operating
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's o identification of significant failure modes affecting safety or availability o trending of component failure rates o development of failure probability estimates for use in fault-tree analyses (reliability or PRA studies)
NPRDS data is available to users through various periodic reports and through on-line access of the data from a computer terminal.
3.1.2 Significant Event Evaluation and Information Network (SEE-IN)
Since the early days of nuclear power plant operations, utili-ties and manufacturers have attempted to share what has been learned from plant operating experience. As nuclear tech-nology becomes more complex and more demanding, the need for sharing operating experience continues to grow and becomes
,o more important. The safety benefits of avoiding problems already encountered and resolved more than justifies the costs and extra effort required for utilities to keep each other informed. The Nuclear Safety Analysis Center (NSAC), with the support of its utility advisory group, began developing a program to share information learned from analyzing nuclear plant experiences. Shortly after its formation in late 1979, .
the Institute of Nuclear Power Operations (INPO) joined NSAC in the development and implementation of the program. The program has been named "Significant Event Evaluation and Information Network" (SEE-IN). In 1981, the management of the SEE-IN Program became the sole responsibility of INP0.
Objective The objective of SEE-IN is to ensure that the cumulative learning process from operating and maintenance experience is j effective and that the lessons learned are reported and cor- +
n rective action taken in a timely manner to improve plant safety, reliability, and availability. This objective is mu l
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n by screening available nuclear plant event information system-l }
V atically, id?ntifying and evaluating the important or signifi-cant events, and communicating the results to the utilities and appropriate designers and manufacturers.
1 Scope The functional approach to SEE-IN is an eight-step process outlined in Appendix C. While INP0 has the program management function, no single organization is responsible for performing all of these functions; rather, the responsibility is spread among key participants in the network. The principle organi-zations involved in the initial screening of plant event data are the utilities and INP0. Each nuclear utility has an in-house program to screen events that occur in its nuclear plant (s). INP0 has a broader charter to screen all nuclear plant events. The sources of input to the screening process include NPRDS, NUCLEAR NETWORK, NRC-mandated reports, IE8s, p IENs, etc. The provision to control the data normally is governed by agreements between INP0 and the supplying organi-zation (e.g., utilities, NRC, NSSS vendors, international participants,etc.). When a significant event or trend has been identified from the screening process, a Significant Event Report (SER) is prepared by INPO and transmitted to the i
utilities and other participants on NUCLEAR NETWORK. This
! event then undergoes an action analysis by INP0. The purpose
{ of the action analysis is to investigate the event or trend in I
more detail and to develop and evaluate practical remedies.
4 For events requiring utility action, the results of the action i analysis are communicated to the utilities, normally in the form of a Significant Operating Experience Report (50ER). In these instances, recommendations are made to resolve the under-lying problems. The implementation of applicable recommended remedial actions is the responsibility of the individual util-ity. Implementation may include changes in plant procedures,
, equipment design, and/or operator training programs. The two final steps in the SEE-IN process are (1) feedback and INPO
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I assessment during plant evaluation of actions taken by the utilities as a result of information provided through SEE-IN and (2) periodic assessment of the process effectiveness by INP0.
i For events which, through the screening process, are deter-mined not significant but have valuable operations and mainte-nance information, an Operations & Maintenance Reminder (0&MR)
- is prepared and processed in the same way as SERs.
The SEE-IN Program provides copies of draft SERs, 0&MRs, and SOERs to the affected vendors for review. Vendor comments are considered in preparation of final SEE-IN reports. Once finalized, the reports are sent to the utilities.
1 The SEE-IN Program includes a cross-reference capability to identify SERs, O&MRs, SOERs, LERs, etc., which report compo-C nent problems that could cause a significant event. This cross-reference facilitates utility review of the component's prior history before using that component in a safety-related application.
Program Operation Plant operating experience data is reviewed from several perspectives including design, component and system perfor-mance, plant procedures, human factors, personnel training, maintenance and testing practices, and management systems to identify significant events and trends.
Formal Review Sources A formal review is conducted on NRC information notices, I bulletins, AE00 reports, event-related generic letters, etc.
A formal review also is conducted on industry-prepared infor-P mation (including those required by NRC) such as LERs, monthly
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operating reports, NRC event-related reports,' NSSS technical hulletins, NPRDS data . NUCLEAR NETWORK operating experience
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entries, international operating experience reports, construc-
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" tion deficiency reports, safety defect reports, and trends identified as significant in the INP0 NPRDS and LER data bases. The formal review includes a dual, independent screen-ing process. The review status is documented and tracked by computer.
Other sources of operating experience information are used by the SEE-IN Program on an ad hoc basis as reference or supple-mental material but do not receive a formal review. The sources include such items as NRC NUREG documents, EPRI and NSAC reports, and other industry reports or data concerned with plant operating experience. The INP0 process for screen-ing is shown in Figure 2.
I Utility Contact (SEE-IN)
In addition to the formal and reference information sources, q another vital information source is direct contact with power plant technical personnel on an ad hoc basis. Each utility designates a SEE-IN contact to respond to questions from INP0 on plant events. The majority of such communications was handled over the telephone or via NUCLEAR NETWORK. Files are 3
maintained by INPO on nuclear utilities and contain names and telephone numbers of designated contacts, telecopier numbers, i
status of nuclear units (i.e., operating, under construction or planned), and NSSS vendor (s).
3.1.3 Interaction With Vendors In the interest of operating the plant safely and efficiently, the utility-vendor contact is essential. To accomplish this goal, utilities already interact with various vendors.
The contractual obligations for furnishing equipment and
> software (manuals, drawings, etc.) are fulfilled upon accep-g tance at the plant site. Interaction between utilities and vendors, due to deficiencies, may be brought about by the t
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p reporting requirements of 10 CFR 21 and 10 CFR 50.55(e). The continuing contract with vendors for warranty obligations or maintenance work are two examples of active interaction after an initial purchase. In addition, much of the interaction with the vendors during plant life is initiated in response to significant failures, to failure trends experienced at the plant, to spare parts procurement, or to subsequent purchase orders of new equipment.
The interaction with the NSSS vendor, who typically supplies a large portion of the safety-related plant equipment, generally is more active than with the other vendors. There are exist- ,
ing channels through which the NSSS suppliers disseminate information of interest to their client utilities. These include the following: ..
o In regular meetings, NSSS representatives outline recent developments and maintenance / design recommendations. Any Q
special concerns of the utility can be addressed in follow-up correspondence with the NSSS supplier's service depart- , .
ment. -
o Bulletins or advisories from the NSSS supplier's service department alert client utilities to special problems experienced by similar plants. Typically included in this correspondence are a description of the problem and the torrective actions taken to resolve it. Recommendations L for preventive actions or for particular cautions to be ..
considered by the utility usually are included. "
o Owners groups provide an additional forum for the exchange of information that may be of generic interest to member utilities. For example, problems in the design or oper-ation of a system or component may be shared with the group and potential resolutions identified. The owners groups' efforts often are directed at seeking improvements or anti-cipating problems rather than being only reactive in nature.
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Improvements in availability or testing and maintenance 10 ,cocedures are exampies of ,ositive results that have come about through owners groups activities. The NSSS supplier makes his broadly-based knowledge available to the group for the specialized evaluations that may be required.
3.1.4 Regulatory Reporting Requirements ,
Other existing sources of information are the documents that I result from the NRC's reporting requirements. These documents include 10 CFR 21 reports, 10 CFR 50.55(e) reports, Licensee !
Event Reports, and NRC Inspection & Enforcement (IE) Bulletins and Information Notices. 10 CFR 21 specifies reporting require-ments relating to component or system deficiencies that may create a substantial safety hazard. This reporting provides the nuclear utility industry notification of significant noncompliances and defects identified by other utilities, architect-engineers, constructors, vendors, and manufacturers associated with nuclear facilities.
10 CFR 50.55(e) requires that the holder of a construction j permit notify the NRC of each deficiency found in design and construction, which, if uncorrected, could affect the safe operation of the nuclear power plant adversely. j i
( 10 CFR 50.73 requires the holder of an operating license for a I nuclear power plant to submit a Licensee Eve Report (LER)
, for events described in 50.73(a)(2). These LEka are incor-
- -porated into the INP0 LER' data base, which provides informa-tion to identify and isolate precursor events and identify
. emerging trends or. patterns of potential. safety significance.
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- The istC Office of Inspection and Enforcement (IE) issues various ' documents,' includi_ng bulletins and information
- notices,Lto inform licensees and construction permit holders q of significant. concerns .that may result from the NRC evalua-V tion of reports,; as; required by 10 CFR 21.21,. 50.55(e), and
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p iO 50.73. These documents provide the nuclear utilities with information on events and concerns that are considered sig-nificant by the NRC.
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- l. 3.2 Recommended Enhancements to Existing Programs The following are recommended enhancements to the existing programs.
INPO and the NPROS User's Group should investigate the feasibility of these recommendations. If found feasible, an implementation program should be developed.
3.2.1 Enhancements to NPRDS o The present definition of component in NPROS (extracted from IEEE 603-1980) is more applicable to electrical components.
The definition should be improved to describe mechanical components better.
o The present failure. reporting guidance needs improvement in
.h the following areas:
Guidance is needed to provide better information for l
analyzing the role of piece parts as a factor in causing j component failures.
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-- The guidance should be revised to indicate that utilities should supply'information when inadequate vendor informa- 3 tion is identified as a causal or contributing factor in a failure. The guidance should provide users of the data base the ability.to retrieve readily those failures involving inadequate vendor information (example, key word sorting, coding).
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Present _ failure reports are often sketchy in providing l
' details of the failure analysis conducted by utilities. '
- The. guidance should emphasize th4 importance of providing more' complete results of failure analysis when one is
( conducted. Although detailed failure analyses are not [, .
+
fk
$bb h),[ .
a
l I .
I h always conducted for every failure, when they are con-ducted they should be provided in NPRDS failure reports.
In this way, the SEE-IN Program and other utilities can derive more benefit from the work of each utility.
o Utilities should develop internal methods to ensure that their NPRDS reports are clear and complete and that the program guidance is followed appropriately, o For some failures it may not be possible for utilities to provide a complete failure description within the time frames for reporting to NPROS. Utilities should still submit preliminary failure reports within the established time frame. Utilities should revise these reports when the necessary information is available. However, the present system does not provide methods for utilities to indicate that reports will be revised later. NPRDS should be modi-O fied to Permit each utiiity to readiis identify whicn of their reports still requires follow-up information. Utili-ties should report a failure event promptly and include an initial analysis. Detailed and complete information should be provided in a timely manner once final analysis has been completed.
o The present scope of NPROS reporting may not meet all the needs of individual utilities for monitoring the relia-bility of their own safety-related components. Each utility that decides that additional systems and components should be added to their basic scope of NPRDS systems M d components should request that INPO accept these systems. INPO will consider these requests, identify the additional resource requirements needed to handle these requests, and notify utilities when it is able to accept additional information.
18-1
l 3.2.2 Enhancements to SEE-IN o Reports should be generated for potential failures caused by faulty or missing vendor-supplied information or other ETI. The VETIP recognizes that the utility will uncover errors in ETI (e.g., during review of the information, writing of instructions, testing, etc.) before anyone else. It is recommended that ETI faults be reported over NUCLEAR NETWORK for review by INPO under the SEE-IN Program, o The SEE-IN Program should be broadened by INP0 to improve the ability to trend NPRDS data. Present methods of trend-ing are largely qualitative and subjective in nature. They depend largely on the ability of analysts to recognize the need to look for degrading or unacceptable system and com-ponent reliability. INPO should develop methods to use NPROS in a more quantitative fashion to detect trend prob-lems. This enhancement is presently under development by INP0.
3.3 Summary Example One problem that led to the Salem event was that the information con-tained in the NSSS vendor technical bulletin (issued in 1974) was not processed appropriately and therefore not incorporated into plant procedures. If the systems that comprise the VETIP were functional 1 in the early 1970s, this oversight probably would not have occurred or would have been rectified. Westinghouse had prepared the techni-cal bulletin based on a precursor event that occurred at another nuclear unit. This type of precursor event would have required that an LER be written and submitted to the NRC. INP0 also would have reviewed the Westinghouse technical bulletin and the LER. The cur-rent criteria for significance screening used by INP0 personnel identify this type event as a significant single failure. It is highly likely that an SER would have been generated by INPO and disseminated to utilities via NUCLEAR NETWORK. Utilities would have g reviewed the SER through their operating experience report review programs.
'L , . _ . - _ '
-f ; ' r: : .__-_,p ,_
's?
- "" * *,,e_'- .,' __ _': A
-'y n. .'
'r - tt n
- 4,_
^
__.,'_ ,Q g In addition, utilities would have had an ongoing program with their NSSS vendors to obtain ETI. Utilities would have had systems in i place to track and process this information. Therefore, there are two pathways that would have ensured this type of information was received and evaluated by the utility: .
o NPRDS/SEE-IN(SERs,50ERs) o NSSS vendor technical bulletins The utility's VETIP procedures would have assessed this information and effected positive action to correct the failed component.
O .
l l
'O 6 NSSS Vendor D '
Spare Parts O Problems
/ Tech. Reps.
DirectContact Tech. Bulletins 9 Owners Groups lEN/IEB/EER
" tg - O -
10CFR 55e ( E-IN)
Generic Letter n
b Other Utilities Spare Parts Probleins
/0 Tech Reps
(
j Non-NSSS Vendors IEB/IEN/LER ,
10CFR21 10CFR 50.55e ,
,,q (;f),h*'q
' ~
(l Generic Letters .
1s3
~'^
t ;- 'l Board Notification
.*7'.
\
i VETIP Block Diagram Figure 1
O O O Misc. Event Info From Other Sources, e.g. NPRDS
-~; y INPO Receeves Reviewer Evaluates O' '
r Event For And N Significance EventInfo if involved, Vendor Contacted U For Comment
, - - If Appropriate,
, Reviewer Prepares
, ,;l Andissues An
. :s Event O&MR
- Is Not -
Reviewer SERis Significant Drafts SER Revised As Necessary Eventis And Ser.t Discussed At _ To Member W ic Utilities "9 ViaThe Event NETWORK May Be Event
+ -
, ,, -s Eventis Significant Designated "SO" g cant
- No (Significant By
-* FurtherAction; Others)
Document Reasons Event is Studied Event Further By INPO, Dedsionis Second Reviewer Assigns
+ ls Not A Significance -* Affected Utility. ->
Ream On _, Develop An Review. OR -
her Significant Updates Of "NS* And Others As SOER Necessary Operating Experience Review Process . $agg^"
And Related Activities . Evaiuation Figure 2
SEE-IN Functior.s
- 1. Provide basic report of plant event (utilities).
- 2. Screen events for significance and transmit Significant Event Reports (SERs) via NUCLEAR NETWORK (utilities and INP0 with vendor input solicited when specific product is identified).
- 3. Provide backup data on contributing factors and probable causes and con-sequences (utilities and vendors).
- 4. Perform action analysis on significant events to evaluate possible options for short-term remedies and feasible long-term solutions that might be implemented (utilities, INPO, and vendors).
- 5. Disseminate information, along with an alert of potential implication, to the utilities (INPO).
O 6. Evaluate the information and implement remedies as appropriate (utili-ties).
- 7. Provide feedback on implementation actions (utilities and INPO).
- 8. Evaluate periodically the effectiveness of the process, including steps 1-7above.(INPO).
s ->
n a t. a %/es
O 'ist or aerereaces
- 1. " Required Actions Based on Generic Implications of Salem ATWS Events" (Generic Letter 83-28). Washington, D.C.: U.S. Nuclear Regulatory Commission, July 8,1983.
- 2. NRC Fact-finding Task Force Report on the ATWS Events at Salem Nuclear Generating Station Unit 1 on Februar:r 22 and 25. 1983 (NUREG-0977).
Washington, D.C.: U.S. Nuclear Regulatory Commission, March 1983.
- 3. Generic Implication of ATWS Events at the Salem Nuclear Power Plant (NUREG-1000). Washington, D.C.: U.S. Nuclear Regulatory Connission.
April 1983.
- 4. Significant Event Evaluation and Information Network (SEE-IN)
(INP0 83-001). Atlanta, Ga.: Institute of Nuclear Power Operations, February 1983.
- 5. Nuclear Plant Reliability Data System (NPRDS) Reportable System and Compo-nent Scope Manual (INPO 83-020). Atlanta, Ga.: Institute of Nuclear l Power Operations, 1983.
pV
- 6. Re)orting Procedures Manual for Nuclear Plant Reliability Data Systems (lip 0 84-011). Atlanta, Ga.: Institute of Nuclear Power Operations, 1984.
- 7. 10 CFR 21, Code of Federal Regulations: Title 10 Part 21, " Reporting of Defects and Noncompliance." Washington, D.C.: U.S. Government Printing Office.
, 8. 10 CFR 50, Code of Federal Regulations: Title 10 Part 50, " Domestic
! Licensing of Production and Utilization Facilities." Washington, D.C.:
l U.S. Government Printing Office.
- 9. Standard Criteria for Safet:r Systems for Nuclear Generating Stations (IEEE 603-80). New York, N.Y.: institute of Electrical and Electronics l Engineers, 1980.
i
/~N RiFMMI!TIONONLY
, Attachment 3 u Tg 2, 3
- - +
1 w.
fO .
6.0 DETAILS 3 \
6.1 The Q-List will be included in a file with other generic infor-mation; however, the fields specifically identified as part of the Q-List shall be safegsarded to prevent revisions by unauthorized persons. The Q-List shall contain but not be limited to, the following protected-fields: , ~l
. . . . .W
, z e *-
- 1. The MPL number specifically ; assigned ~to thla subcomponent or parent component.- ,
,g (y ., O -
~2. The Original Procurement.s'peci and Sub-Specification number for the component. * ' '
T 3.. The ' safety. classification of the MPL, Assemblies and Stock Codes (both as required and.as: purchased). The entries will
-be as follows:
. ,' w "1"
^
Essential-to-Function 'ASME Cfass 1.
"2"
~
y3
,s--
Essential-to-Function, ASME Class 2. Q "3"; 4 Essential-to-Function, ASME Class 3.s' '
- h)[g,,
, x_ ,
~
( . ,J ; 'y, "1E" Essential-to-Function, Electrical.
"SR" iEssential-to-Function, NON-ASME CODE ITEMS.
,m Ji
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'% C n .,
[%';
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- a
_, , - -+ ~ * - *
- l
+
OM1A:
Page: 4 PAP-0303 f i Rev.: 0 Nod-Nuclear-Safety-Related:
?
"4" Not Essential-to-Function "4Q" Essential-to-Function,' Augmented QA (Off-Cas).
"5" Essential-to-Function, Fire Protection "6" Essential-to-Function, American Water Works Assoc.
4 "7" Essential-to-Function, ASME Code Components (non-nuclear)
. 4. The component function. Entries shall be made as follows:
"AC" Active Component "PBC" Pressure Boundary Component "R" Electrical Component "NA" Not Applicable Subcategories within each of these will be the Seismic i
Functions as follows:
"A"- - Seismic Category I. The component must accomplish its safety-related function during and after the seismic e event.-
,to I "B" - Seismic Category I. The component need not function ( ,
' during the seismic event but must be capable of per-forming properly after.
"C" - Seismic Category I. The component can fail to' function at any-time, but it must not incapacitate an essential-power-source.or fail to hold pressure at pny time.
.<3 "D" - Nonseismic. . The component, includ 51sure retaining components,canfailinanymanger,1,ng{, hadWt any time, ,
provided safety class'com -" not affected by its failure.
"I" . Seismic Category I.; ginal equipment specifi-cation applies in'th ase. 'An evaluation to determine
- Category A,'B, C or D-should be performed if possible.
- 5. The Normal Position of the component.. . The entries will be as
. ^follows:'
"M" Modulati*ng, throttled:and/or sequence ~d .(does not close -
A :or shut completely. nor does it open' fully)
M,,N
-"S'? .
= Shut (electrical)- .
F "O" 'Open;
- Q' q?b, f~^ ."E" Energized'.
L'V. Q,. .N ~~
- q. h '"D"E De-energized.
' * $;%"C ? . Closed: (mechanical)
(/
N ,'?N"QNot L Applicable'- -
l- fl[Q .- .
t.
. , -.y- ,, g: e 4 ,- ,m. w- g-,J -,
..w .-3-, 9 .. ppe- -4 ----pw .- e 'n y s .p.,,...9g*-
f OM1A: PAP-0303 Page: 5 '
Rev.: 0 "R" Normal Operation - not required to close during event "T" Operable over full range (may close or shut completely, or open fully)
- a. The first two letters will be :
PE for PSAR listed DBE's and FE for FSAR listed DBE's
Entries for the DBE positions will be as in Section 6.1.5, preceeding.
- 7. The Original Manufacturer, Model Number, and Serial Number, at the MPL, Assembly and Stock Item (PART) level, as installed in the plant.
, A (m],/
L
- 8. Q-List specific notes.
- 9. A complete listing of all replacement parts and subassemblies of the component, with the following fields controlled:
- a. Association to a specific MPL/ ASSEMBLY.
- b. Limited Life designation.
- c. Shelf Life, expressed in weeks.
- d. Storage Maintenance Requirements. Format for the entries will be as defined in PAP-0903, Repetetive Tasks Program,
- e. Storage Code. As defined in section 2.7 of ANSI N45.2.2-1978.
s
- 10. Procurement Requirements. These will represent the_ Procure-ment requirements as defined in PAP-0402, Procurement of Safety-Related and other Special Items, or ,(Later) ~ Procurement Requirements Evaluations. *
[y?%
m; gn ~
3 ,
( f%>,
~*
ATTACHMENT A l
l
[) SEQUENCE OF EVENTS LOG - PLANT COMPUTER PARAMETER MEASURED COMPUTER ID REACTOR HI-PRESS A B21NC001 REACTOR HI-PRESS B B21NC002 REACTOR HI-PRESS C B21NC003 REACTOR HI-PRESS D B21NC004 RV LO WATER LVL CH A B21NC005 RV LO WATER LVL CH B B21NC006 RV LO WATER LVL CH C B21NC007 RV LO WATER LVL CH D B21NC008 RHR/ ADS DW PRESS CH B B21NC009 RHR/ ADS DW PRESS CH F B21NC010 RHR/ ADS WTR LVL CH B B21NC011 ,
RHR/ ADS WTF LVL CH F B21NC012 LPCS/RHR/ ADS DW PRS CH A B21NC013 LPCS/RHR/ ADS DW PRS CH E B21NC014 LPCS/RHR/ ADS WTR LVL CH A B21NC015 LPCS/RHR/ ADS WTR LVL CH E B21NC016 HPCS DW PRE 3S CH C B21NC017 HPCS DW PRESS CH L B21NC018 HPCS DW PRESS CH G B21NC019 HPCS DW PRESS CH R B21NCO20 HPCS LO WTR LVL CH C B21NC021 ry HPCS LO WTR LVL CH L B21NC022
('~'l HPCS LO-WTR LVL CH G B21NCO23 HPCS LO WTR LVL CH R B21NC024 SAFETY RLF VLV NO. 1 B21NC025 SAFETY RLF VLV NO. 2 B21NC026 SAFETY RLF VLV NO. 3 B21NCO27
- SAFETY RLF VLV NO. 4 B21NCO28 SAFETY RLF VLV NO. 5 B21NCO29 SAFETY RLF VLV NO. 6 B21NC030 SAFETY RLF VLV NO. 7 B21NC031 SAFETY RLF VLV NO. 8 B21NC032 SAFETY RLF VLV NO. 9 B21NC033 SAFETY RLF VLV NO. 10 B21NC034 SAFETY RLF VLV NO. 11 B21NC035 SAFETY RLF VLV NO. 12 B21NC036 SAFETY RLF VLV NO. 13 B21NC037 SAFETY RLF VLV NO. 14 B21NC038 SAFETY RLF VLV NO. 15 B21NC039 r e* SAFETY P.LF VLV NO. 16 B21NC040 Thh SAFETY RLF VLV NO. 17 B21NC041
'd SAFETY RLF VLV NO. 18 B21NC042 3 . SAFETY RLF VLV NO. 19 B21NC043-
B21NC044 B21NC045 NSSS SPARE (RFL VLV) B21NC046
'- -1 MSL ISOLATION CH A B21NC047 a MSL ISOLATION CH B B21NC048
[ ', e 9, MSL ISOLATION CH C MSL-ISOLATION CH D B21NC049 B21NC050
. RV HI WTR LVL CH A B21NC051
"'" 1
ATTACHMENT A SEQUENCE OF EVENTS LOG - PLANT COMPUTER
[O
~
PARAMETER MEASURED COMPUTER ID RV HI WTR LYL CH B B21NC052 RV HI WTR LYL CH C -B21NC053 RV HI WTR LVL CH D B21NC054 DSCH VOL HI WTR LVL CH A C11NC033 DSCH VOL HI WTR LVL CH B C11NCO34 DSCH VOL HI WTR LYL CH C C11NC035 DSCH VOL HI WTR LVL CH D C11NC036 APRM NEUT FLUX CH A C51NC061 APRM NEUT FLUX CH B C51NC062 APRM NEUT FLUX CH C C51NC063 APRM NEUT FLUX CH D C51NC064' APRM NEUT FLUX CH E C51NC065 APRM NEUT FLUX CH F C51NC066 i APRM NEUT FLUX CH G C51NC067 -
l APRM NEUT FLUX CH H C51NC068 APRM THERMAL PWR CH A C51NC071 c APRM THERMAL PWR CH B .C51NC072 APRM THERMAL PWR CH C C51NC073 APRM THERMAL PWR CH D C51NC074 APRM THERMAL PWR CH E C51NC075 APRM THERMAL PWR CH F C51NC076 "
APRM-THERMAL PWR CH G C51NC077 l
Q APRM THERMAL PWR CH H NEUT MON SYSTEM CH A1 C51NC078
'C51NC091 NEUT MON SYSTEM CH A2 C51NC092 NEUT MON SYSTEM CH B1 C51NC093 7
NEUT MON SYSTEM CH B2 C51NC094 DRYWELL HI PRESS CH A C71NC001 DRYWELL.HI PRESS CH B C71NC002 i DRYWELL HI PRESS CH C C71NC003 i
DRYWELL HI PRESS CH D C7.1NC004 MANUAL SCRAM DIV 1 C71NC005 MANUAL SCRAM DIV-2 C71NC006 REACTOR SCRAM DIV 1 C71NC009
-REACTOR SCRAM DIV 2 C71NC010
'TSVECLOSURE CH A C71NC013 TSV CLOSURE CH B. C71NC014
-TSV CLOSURE'CH C C71NC015 TSV CLOSURE'CH D G71NC016' TCV FAST CLOSURE'CH A C71NC017 TCV FAST CLOSURE CH-B C71NC018 TCV FAST CLOSURE CH C C71NC019 TCV-FAST CLOSURE CH D' C71NC020 RECIRC PMP TRIP CH A C71NCO25 L .RECIRC-PMP~ TRIP'CH B C71NCO26 TURBINE BYPASS VLV C85NC001
=
MSL HI RADIATION CH A D17NC001 oh.
J . .
m ggggpJn' tlDR6H}J
ATTACHMENT A
'p-V' SEQUENCE OF EVENTS LOG - PLANT COMPUTER PARAMETER MEASURED COMPUTER ID MSL HI RADIATION CH B D17NC002 MSL HI RADIATION CH C D17NC003 MSL HI RADIATION CH D D17NC004 RHR PUMP BREAKER LOOP A E12NC001 RHR PUMP BREAKER LOOP B E12NC002 RHR PUMP BREAKER LOOP C E12NC003 RHR PRESSURE LOOP A E12NC004 RHR PRESSURE LOOP B E12NC005 RHR PRESSURE LOOP C E12NC006 RHR INJECT FLOW LOOP A E12NC007 RHR INJECT FLOW LOOP B E12NC008 RHR INJECT FLOW LOOP C E12NC009 LPCS PUMP BREAKER E21NC001 LPCS SYSTEM PRESS E21NC002 LPCS LO FLO BYP VLV E21NC003 HPCS PUMP BREAKER NO. 2 E22NC001 HPCS PRESSURE E22NC002 HPCS LO FLO BYP VLV E22NC003 DIV. 3 MANUAL SCRAM C71NC007 DIV. 4 MANUAL SCRAM C71NC008 ,
,, IRM CHANNEL A UPSCALE C51NC031 IRM CHANNEL B UPSCALE
() IRM CHANNEL C UPSCALE C51NC032 C51NC033 .
IRM CHANNEL D UPSCALE C51NC034 IBM CHANNEL E UPSCALE C51NC035 IRM CHANNEL F UPSCALE C51NC036 IRM CHANNEL G UPSCALE C51NC037 IRM CHANNEL H UPSCALE C51NC038 REACTOR SCRAM DIV. 3 C71NC011 REACTOR SCRAM DIV. 4 C71NC012 3
ATTACHMENT B
()- SEQUENCE OF EVENTS RECORDER SER ALARM DESCRIPTION ELEMENTARY REV ADDRESS DIAGRAM 001 HP CONDENSER VACUUM LOW 1R6125 E 002 IP CONDENSER VACUUM LOW 1R6125 E 003 LP CONDENSER VACUUM LOW 1R6125 E 004 HOTWELL PUMP A TRIP 1R6125 E 005 HOTWELL PUMP B TRIP 1R6125 E 006 HOTWELL PUMP C TRIP 1R6125 E 007 CONDENSATE BOOSTER PUMP A 1R6126 G TRIP 008 HEATER 4 LEVEL LOW 1R6126 G 009 HEATER 4 LEVEL HIGH 1R6126 G 010 HOTWELL PUMP DISCH HDR 1R6126 G PRESSURE LOW 011 CONDENSATE BOOSTER PUMP 1R6126 G DISCH HDR PRESSURE LOW 012 CONDENSATE BOOSTER PUMP C 1R6126 G TRIP 013 REACTOR FEEDWATER BOOSTER 1R6150 G PUMP A DISCH PRESSURE LOW 014 REACTOR FEEDWATER BOOSTER 1R6150 G PUMP B DISCH PRESSURE LOW 015 REACTOR FEEDWATER B0OSTER 1K6150 G
/~T PUMP C DISCH PRESSURE LOW
~# 016 REACTOR FEEDWATER BOOSTER 1R6150 G PUMP'D DISCH PRESSURE LOW 017 MOTOR FEEDWATER PUMP DISCH 1R6150 G PRESSURE, LOW.
, 018 MOTOR FEEDWATER PUMP TRIP 1R6150 G 019 REACTOR FEEDWATER. PUMP A 1R6150 G DISCH PRESSURE LOW 020 REACTOR FEEDWATER PUMP ~B 1R6151 J DISCH PRESSURE LOW 021. REACTOR FEEDWATER PUMP A 1R6151 J TRIP 022 REACTOR FEEDWATER PUMP B 1R6151 J TRIP 023 FEEDWATER BOOSTER PUMP A .1R6151 J TRIP
.024 FEEDWATER B0OSTER PUMP B 1R6151 J TRIP 025 FEEDWATER BOOSTER PUMP C 1R6151 J TRIP-026 :FEEDWATER B00 STER' PUMP D 1R6152- E TRIP 1027 . AUXILIARY CONDENSER A 1R6152 E VACUUM LOW 028 AUXILIARY CONDENSER ~B- 1R6152 E VACUUM LOW
( );
.m
'029. REACTOR FEED PUMP TURBINE A 1R6152, E MANUAL TRIP
- gw'MkY&[]
Ah 1.
ATTACHMENT B
.( ) SEQUENCE OF EVENTS RECORDER SER ALARM DESCRIPTION ELEMENTARY REV ADDRESS DIAGRAM 030 REACTOR FEED PUMP TURBINE B 1R6152 E MANUAL TRIP 031 MAIN TURB MFP TRIP 1R6153 C 032 REACTOR FDW PUMP 1R6153 C CONTROL SYSTEM FAILURE 033 INTERMEDIATE RANGE MONITOR A 1R61257 B OR E UPSCALE TRIP OR INOP 034 INTERMEDIATE RANGE MONITOR B 1R61257 B OR F UPSCALE TRIP OR INOP 035 INTERMEDIATE RANGE MONITOR C 1R61257 B OR G UPSCALE TRIP OR INOP 036 INTERMEDIATE RANGE MONITOR D 1R61257 B
- OR H UPSCALE TRIP OR INOP 037 MAIN TURB TSI HIGH VIB TRIP 1R61154 A 038 MAIN TURB LOSS OF STATOR 1R61155 A COOLANT TRIP 039 MAIN TURB LOW SHAFT, PUMP 1R61155 A DISCH PRESSURE TRIP i
040 MAIN'TURB EXH HOOD TEMP TRIP 1R61155 A 041 MAIN TURB HYD PRESS TRIP 1R61155 A 042 MAIN TURB MOIST SEP HL TRIP 1R61155 A
((<sc,) - 043 MAIN'TURB LOW BEARING OIL' 1R61155 A
~
PRESS TRIP 044 MAIN TURB CONDENSER LOW 1R61155 A VACUUM TRIP 045 MAIN TURB THRUST BRG WEAR 1R61155 A DETECTOR LOW TRIP 046- MAIN TURB THRUST BGR WEAR 1R61155 A DETECTOREUP TRIP-047 MAIN TURB LOW ETS. PRESS TRIP 1R61155 A i- 1048 MAIN TURB 125V MASTER TRIP 1R61155 A BUTTON ACTUATED L 049 'BACK UP_0VERSPEED. TRIP 1R61156 D 050 MAIN TURB MASTER TRIP BUS 1R61156 D TRIPPED L 051 ' MAIN:TURB MECH:0VERLOAD/ 1R61156 D L SWITCH _ TRIPPED-L
- 052- TURBINE 1 TRIP . . _ _ :1R61156 D L 053 VOLTS / HERTZ" RATIO HIGH TRIP' 1R61177 054 MAIN..TRANSF'l-PY-T A PHASE 1R61175 -c DIFFERENTIAL-N <
055' MAIN TRANSF 1-PY-T'B PHASE '1R61175 C DIFFERENTIAL 056' f MAIN TRANSF ol-PY-T C PHASE: '1R61175 C' DIFFERENTIAL 057, MAIN TRANSF'1-PY-T'345 KV 1R61175 -C os c 1NEUT_0VERCURRENT '
); ~058- . MAIN TRANSF 1-PY-T-A PHASE L1R61175- C
![1lpjg m&p Win
~
--SUDDEN PRESS
% Npygy
, , < . .,- c., ,,...-<T..
ATTACHMENT B
( SEQUENCE OF EVENTS RECORDER SER ALARM DESCRIPTION ELEMENTARY REV ADDRESS DIAGRAM 059. MAIN TRANSF 1-PY-T B PHASE 1R61175 C 4
SUDDEN PRESS 060 MAIN TRANSF 1-PY-T C PHASE 1R61175 C SUDDEN PRESS 061 GEN 1-PY-G NEUTRAL GROUND 1R61175 C OVERVOLTAGE 062 GEN 1-PY-G UNDERFREQUENCY 1R61175 C 063 GEN 1-PY-G NEG SEQUENCE 1R61175 C OVERCURRENT 064 GEN 1-PY-G ZERO SEQUENCE 1R61175 C OVERVOLTAGE 065 GEN 1-PY-G A PHASE DIFF- 1R61176 A ERENTIAL NO 1 066 GEN 1-PY-G B PHASE DIFF- 1R61176 A ERENTIAL NO 1 067 GEN 1-PY-G C PHASE DIFF- 1R61176 A 4 ERENTIAL NO 1
- -068 GEN BREAKER S-611-PY TIE 1R61.176 A FAILURE-069 UNIT OVERALL DIFFERENTIAL 1R61176 A 070 GEN 1-PY-G. LOSS OF EXCITER 1R61176 A O- .
071 c1NSTANTANEOUS)
GEN _1-PY-G LOSS OF EXCITER 1R61176 A (DELAYED)
~
072 GENERATOR ~1-PY-G OF STEP 1R61176 A 073- GENERATOR! BREAKER 5-610-PY 1R61176 A TIE-FAILURE 074 GENERATOR.1-PY-GLA PHASE 1R61176' A DIFFERENTIAL-NO 2 075 GENERATOR 1-PY-G B PHASE 1R61176 A DIFFERENTIAL NO 2 076 _ GENERATOR 1-PY-G C PHASE 1R61176 -A DIFFERENTIAL.NO 2 077- GENERATOR LOCK 0UT-RELAY TRIP 1R61179 D
-078 AUTO VOLT REGULATOR. TRIP . 1R61179 D 079 ISOPHASE BUS' COOLING TROUBLE: 1R61180 F 080 ISOPHASE BUS HYDROGEN TROUBLE 1R61180 D 081 SPARE 082 GENERATOR CASING LIQUID 1R61180 D
- DETECT LEVEL'HI' .
083 MAIN ~TURB BRG. METAL ~ TEMP HI 11R61876 084- : ELECTRO HYD CONTR DC' INPUT- 1R61875 D POWER LOST
'085. ~ LUBE-0IL PRESS LOW - 1R61200~ G 086L DIV11 DIESEL GENLBREAKER- : 1R61200 G-EH1102.CLOSE 1R61200 .G
.. X 087 '
. DIESEL GEN PROTECTIVE' RELAY. '
1R61201? H T ). TRIP
": ~' ' 088 ' DIESEL GEN LOCKOUT RELAY. TRIP 1R61202 H v- 089 . BUS .EH11(4.16.KVO_UNDERVOLT- 1R61202' H Mthy ,'h ?q 97
~ '
3 h, +
, - - , . ,,.-,--%+-w., , ,
ATTACHMENT B SEQUENCE OF EVENTS RECORDER h( )
SER- ALARM DESCRIPTION ELEMENTARY REV ADDRESS DIAGRAM 090 BUS XH11 (4.16 KV) UNDERVOLT 1R61202 H 091 BUS XH11 (4.16 KV) BREAKER 1R61202 H TRIP 092 BUS EH11 (4.16 KV) BREAKER 1R61203 G TRIP 093 DIESEL GEN EMERGENCY START 1R61204 J SIGNAL RECEIVED 094 ' DIESEL GEN FAILURE TO START 1R61204 J 095 LUBE OIL PRESS LOW 1R61225 F
'096 DIV 2 DIESEL. GEN BREAKER 1R61225 F EH 1201 CLOSE 097 DIESEL GENERATOR PROTECTIVE 1R61226 G RELAYiTRIP 098 DIESEL GEN LOCKOUT RELAY TRIP 1R61227 G
-099 BUS EH12(4.16KV)UNDERVOLTAGE 1R61227 G
.100- . BUS XH12(4.16KV)UNDERVOLTAGE 1R61227 G 101 BUS EH12(4.16KV) BREAKER TRIP 1R61228 H 102 DIESEL GEN EMERGENCY 1R61229 H START. SIGNAL RECIEVED 103- BUS XH12(4.16KV) BREAKER TRIP 1R61229 H o
][ 105 A RE
- DIV 3 DIESEL GEN BREAKER
- EH1301, STATUS:
AR 1R61278 E
_..106~ LUBE OIL 1 PRESSURE' LOW 1R61279 D-
- 107- " DIESEL GENERATOR. EMERGENCY. 1R61280 -F- '
't START SIGNAL 1: RECIEVED!
-108- DIESEL' GENERATOR' 1R61280' F-FAILURE TO START-~ ~
o 109. . BUS:EH13(4.'16KV)UNDERVOLTAGE 1R61280 F L 110 xBUS EH13(4.'16KV) BREAKER TRIP- 1R61281' =F L -111. DIESEL GENERATOR 1R6182- E. '
l '
' LOCKOUT. RELAY: TRIP _
. .112 . DIESEL' GENERATOR . .
'1R6182 .E-l: DIFFERENTIAL RELAYLTRIP P . 113 SPARE _ .
114x '
RCIC &-RHRLISOL TIMER: c1R61413 .B
~
RUNNING:STEAMLTUNNEL TEMP-HIGHl
-115: -BUS!H12-(4.16KV) UNDERVOLTAGEJ1R61453 'F
't '1161 ' BUS;L10l(13 8KV)1 BREAKER TRIP 1R61453 F-g .117 .BUSHL11E(13.8KV)' BREAKER: TRIP..~1R61453 . F .~
" F L118 -
BUS!L12-(13.8KV) BREAKER-TRIP 11R61453
' 7 119 BUS:H11e(4.16KV)" BREAKER-TRIP 1R61453 F 11,2 0- iBUS H121(4.16KY)LBREAKER TRIPL1R61453- F=
< - .121' -BUSiL10;(13 8KV)iUNDERVOLTAGE1R61454- FJ 1221 ~ BUS L11-(13.8KV)._UNDERVOLTAGE 1R61454- F g A //
- N ~
'123-1124.'
BUStL12.(13 8KV)^UNDERVOLTAGEf1R61454 JBUS :H11; (4.'16KV)' UNDERVOLTAGE E.1R61454
-F-
-F i!
s
- E bkh ~
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w
..m. ~ .,,,,;.~.4
._ _ , - , ,,,,a
r ATTACHMENT B
-( ) SEQUENCE OF EVENTS RECORDER SER ALARM DESCRIPTION ELEMENTARY REV ADDRESS DIAGRAM 125 STARTUP TRANSFORMER 100-PY-B 1R61454 F DIFFERENTIAL STATUS 126 STARTUP TRANSFORMER 100-PY-B 1R61460 D SUDDEN PRESS STATUS 127 STARTUP TRANSFORMER 100-PY-B 1R61460 D 345 KV NEUTRAL OC STATUS 128 STARTUP TRANSFORMER 100-PY-B 1R61460 D 13.8 KV NEUTRAL OC STATUS 129 UNIT 1 AUX TRANSFORMER 1R61461 C 110-PY-B A PHASE DIFF 130 STARTUP TRANSFORMER 100-PY-B 1R61460 D 13.8 KV PHASE OC 131 UNIT 1 345 KV BUS 1R61460 D DIFF STATUS 132 UNIT 1 AUX TFMR 100-PY-B 1R61460 D B PHASE DIFF STATUS 133 UNIT AUX TFMR 100-PY-B 1R61460 D C PHASE DIFF STATUS 134 UNIT AUX TFMR 100-PY-B 1R61461 C SUDDEN PRESS
< s- 135 UNIT AUX TFMR 100-PY-B 1R61461 C
' (,)
A WINDING 13 8KV NEUT GND OC 136 UNIT AUX TFMR 110-PY-B 1R61461 C
.C WINDING 13.8KV NEUT GND OC 137. . TURBINE BLDG CLOSED COOLING 1R61475 C HX OUTLET TEMP HIGH 138 SERVICE AIR COMMON HEADER 1R61476 D PRESSURE LOW 139 SERVICE AIR RECIEVER 1R61476 D PRESSURE LOW 140 INSTRUMENT AIR RECIEVER 1R61476 D PRESSURE-LOW 141 TB BLDG BASEMENT WTR LVL 1R61500 C HIGH CIRW PMP TRIP 142 CIRC WATER PUMP SUCT CHAMBERS 1R61500 C LEVEL LOW 143 ~ CIRCULATION WATER PUMP A TRIP'1R61500 C-144 CIRCULATION WATER' PUMP B TRIP 1R61500- C
.145 CIRCULATION WATER PUMP C TRIP 1R61500 C 146 CONDENSATE OR FEEDWATER 1R61850- .F CONDUCTIVITY HIGH 147 STEAM SEAL EVAPORATOR 1R61575 D STEAM PRESSURE-LOW 148 STEAM SEAL EXHAUST SYSTEM- 1R61575 D VACUUM LOW '
149 STEAM JET AIR EJECTOR.INTLK 1R61575- D.
CONDENSER A LEVEL HI/LO j%-): 150 STEAM' JET. AIR EJECTOR INTLK 1R61575 D
' CONDENSER'B-LEVEL HI/LO
^. k ?$$f-hh. -
5
{-
ATTACHMENT B i'
SEQUENCE OF EVENTS RECORDER SER ALARM DESCRIPTION ELEMENTARY REV ADDRESS DIAGRAM 151 MECHANICAL VACUUM PUMP A TRIP 1R61576 G
' MECHANICAL VACUUM PUMP B TRIP 1R61576 152 G 153 REACTOR FEED PUMP TURBINE A 1R61.650 B THRUST BRG ACTIVE WEAR HIGH 154 REACTOR FEED PUMP TURBINE B 1R61650 B
.- THRUST BRG ACTIVE WEAR HIGH 155 REACTOR FEED PUMP TURBINE A 1R61650 B BEARING OIL PRESSURE LOW
, 156 REACTOR FEED PUMP TURBINE B 1R61650 B 3
BEARING OIL PRESSURE LOW 157 LP TURBINE EXHAUST HOOD 1R61800 D TEMP HIGH
- - 158 STATOR COOLING SYSTEM 1R61801 D -
FLOW LOW 159 GENERATOR CASING HYDROGEN 1R61801 D i PRESSURE HI/LO F 160 ELECTRO HYDRAULIC CONT SYSTEM 1R61801 D SUPPLY HEADER PRESSURE LOW
. .161 SERVICE WATER PUMP DISCHARGE 1R61627 F
!. HEADER PRESSURE LOW 162 NUCLEAR CLOSED COOLING PUMP 1R61629 D ch' 163
. DISCHARGE HEADER PRESSURE LOW NUCLEAR. CLOSED COOLING HX 1R61629 D OUTLET TEMP HIGH 164 UNIT 1 345 KV BUS-_NO 2 1R61460 D DIFFERENTIAL' STATUS
.165 .BKR S-610-PY TIE.A PHASE. 1R61177 -
, STATUS
! 166- 'BKR S-610-PY TIE _B PHASE 1R61177 -
f- , STATUS:
L .167 BKR-S-610-PY TIE,C PHASE 1R61177- -
- i l STATUS ~
l_ 168- . .BKR S-611-PY' TIE'A-PHASE' 1R61177 -
l STATUS I 169, BKR ~ S-611- PY TIE B' PHASE . 1R61177. -
h, STATUS 170 .BKR S-611-PYnTIE C PHASE- 1R61177- --
-STATUS-
~
.171 : CONDENSATE. BO'0 STER : PUMP : B 1R6126. 'G K . TRIP f
a r ,
, '. lf% ~, _
t , %, . , , .
NN3;Qjg
, '6 x
O ATTACHMENT C RECORDERS FOR POST TRIP REVIEW TAG NO. PARAMETER POINTS PCWER SOURCE 1,2B21R614 REACTOR STEAM TEMP 24 NON CLASS 1E 1,2B21R615 REACTOR LEVEL 1 NON CLASS 1E 1,2B21R623A,B REACTOR PRESS 2 CLASS 1E LEVEL DIV 1 AND 2 1,2B21R643 REACTOR METAL TEMP 4 NON CLASS 1E 1,2C34F608 REACTOR LEVEL 2 NON CLASS 1E 1 REACTOR /TURB PRESS' 2 NON CLASS 1E 1,2C34R609
,2C51R603A, , REACTOR POWER RANGE 2 C NEUTRON FLUX NON CLASS 1E 1,2C51R614 , REACTOR RECIRC FLOW 2 NON CLASS 1E NEUTRON MONITOR 2D17R601 0FF GAS POST TREAT 2 NON CLASS 1E 1,2D17R604 1, 0FF GAS PRE TREAT 1 NON CLASS 1E 1,2D23R090A,B SUPPRESSION POOL TEMP 8 CLASS 1E DIV 1 AND 2 1,2D23R170A,B DRWELL AND CONTAINMENT 7 CLASS 1E TEMP DIV 1 AND 2 1,2D23R180A,B DRWELL AND CONTAINMENT 3 CLASS 1E PRESS DIV 1 AND 2 1,2E12R601 RESIDUAL HEAT REMOVAL 16 NON CLASS 1E TEMP 1,2G33R601 REACTOR WATER CLEANUP 2 NON CLASS 1E CONDUCTIVITY 1,2G43R073A,B SUPPRESSION POOL LEVEL 4 CLASS 1E
..(3
-V NARROW RANGE -DIV 1 AND 2 WIDE RANGE 1,2N15R016A,B ANNULUS SPACE NON CLASS 1E DIFF PRESS 1,2N11R050 MAIN STEAM LINE 2 NON CLASS 1E PRESS 1,2N11R055 MAIN STEAM LINE 2 NON CLASS 1E PRESS 1,2N11R060 MAIN-STEAM LINE 2 NON CLASS 1E TEMP
'1,2N11R065 MAIN STEAM LINE 2 NON CLASS 1E TEMP 1,2N21R183- MAIN CONDENSER' 3 NON CLASS 1E PRESS 1,2N21R203 MAIN CONDENSER 2 NON CLASS 1E HOTWELL LEVEL 1,2N27R401 FEEDWATER PUMP 18 NON CLASS 1E TURB VIB AND ECCEN 1,2N31R001 MAIN TURB 24 NON CLASS 1E EXPANSION AND TEMP 1,2N31R002 MAIN TURB 12 NON CLASS.1E VIBRATION AND ECCEN 1,2N31R003 MAIN TURB 1
-ECCEN SPEED AND VALVE NON CLASS 1E POSITION
'1,2N31R005- MAIN TURB 24 NON CLASS 1E BEARING METAL ~ TEMP.
1,2N64R605 0FF GAS 12 NON CLASS 1E' HYDROGEN-h__.
~_ .
'( .
ATTACHMENT D h' POST TRIP LOG NSSS - PLANT COMPUTER PARAMETER MEASURED COMPUTER ID SCAN INTERVAL (SEC)
APRM FLUX LVL CH A C51NA051 1 APRM FLUX LVL CH B C51NA052 30 APRM FLUX LVL CH C C51NA053 1 APRM FLUX LVL CH D C51NA054 30 APRM FLUX LVL CH E C51NA055 30 APRM FLUX LVL CH F C51NA056 30 APRM FLUX LVL CH G C51NA057 30 APRM FLUX LVL CH H C51NA058 30 STEAM DOME PRESSURE C34NA001 1 STEAM DOME TEMP B21NA006 30 TOTAL CORE FLOW BCCNA001 1 REACTOR FW FLOW LINE A C34NA002 1 REACTOR FW FLOW LINE B C34NA003 1 REACTOR WATER LEVEL C34NA004 1 RECIRC LP A DR FL CH A B33NA005 30 R2 CIRC LP A'DR FL CH D B33NC006 30 RECIRC LP B DR FL CH A B33NA007 30 RECIRC LP B DR FL CH D B33NA008 30 TOTAL STEAM FLOW C34NA005 1 MAIN TURB STEAM FLOW C34NA006 30
- p. REACTOR CORE PRESS' DROP B21NA001 1
,x RFR" TOR FW INLET TEMP CH A B21NA002 1 CRD SYSTEM FLOW C11NA001 30 GROSS-GENERATOR PWR C91NA005 30 l
l l
/
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' l- usuf
. : + ,,,
m'*1 Arg s-
- )
1 t '7
ATTACHMENT E
%)
POST TRIP LOG BOP - PLANT COMPUTER PARAMETER MEASURED COMPUTER ID SCAN INTERVAL (SEC)
UNIT 1 PLANT VNT GAS D17BE001 15 UNIT 1 PLANT VNT IODINE D17BE002 60 UNIT 1 PLANT VNT PART D17BE003 60 UNIT 2 PLANT VNT GAS D17B3007 15 UNIT 2 PLANT VNT IODINE D17BE008 60 UNIT 2 PLANT VNT PART D17BE009 60 UNIT 1 OG VENT GAS D17BE004 15 UNIT 1 OG VENT IODINE D17BE005 60 UNIT 1 OG VENT PART D17BE006 60 ANNULUS EXH A GAS D17BA019 60 ANNULUS EXH B GAS D17BA020 60 MAIN STEAM LINE A PRESS NilBA001 15 MAIN STEAM LINE B PRE 3S NilBA002 15 MAIN STEAM LINE C PRESS NilBA003 15 MAIN STEAM LINE D PRESS NilBA004 15 FDW HOR PRESS A N27BA001 15 FDW HOR PRESS B N27BA002 15 MFP SUCTION FLOW N27BA003 15
( 'y RFP A SUCTION FLOW N27BA010 15
(_/ RFP B SUCTION FLOW N27BA0ll 15 RFPT A HP BRG VIB N27BA004 5 RFPT A HP BRG VIB N27BA005 5 RFPT A ECCENTRICITY N27BA006 15 RFPT B HP BRG VIB N27BA007 5 RFPT B HP BRG VIB N27BA008 5 RFPT B ECCENTRICITY N27BA009 15 RFP A CPLG END BRG VIB N27BA089 5 RFP A TH END BRG VIB N27BA090 5 RFP B CPLG END BRG VIB N27BA091 5 RFP B TH END BRG VIB N27BA092 5 HTR 4 PRESS N36BA013 30 AUX COND A PRESS N21BA008 15 AUX COND B PRESS N21BA009 30 AUX COND A TEMP N21BA089 30 AUX COND B TEMP N21BA090 30
~
2W* W "' . "
ATTACHMENT F h TURBINE GENERATOR LOG - PLANT COMPUTER PARAMETER MEASURED COMPUTER ID SCAN INTERVAL (SEC)
LP EXH HOOD C TEMP N31BA028 30 LP EXH HOOD D TEMP N31BA027 30 LP EXH HOOD A TEMP N31BA026 30 HP CNDR EXH PRESS N21BA007 15 IP CNDR EXH PRESS N21BA006 15 LP CNDR EXH PRESS N21BA005 15 HP CNDR TEMP N21BA031 30 IP CNDR TEMP N21BA030 30 LP CNDR TEMP N21BA029 30 MAIN TURBINE SPEED N31BA013 30 MAIN TURB CONT VLV OPEN N31BA018 30 MAIN STEAM LINE A PRESS N11BA001 15 MAIN STEAM LINE B PRESS N11BA002 15 MAIN STEAM LINE C PRESS N11BA003 15 MAIN STEAM LINE D PRESS N11BA004 15 GEN HYDROGEN PRESS N35BA001 15 TRUB IST STG SHL IN TEMP N31BA025 30 HP TURB 1 BRG VIB N31BA001 5 HP.TURB 2 BRG VIB N31BA002 _ 5 LP TURB A3 BRG VIB N31BA003 5 LP TURB A4.BRG VIB N31BA004 5
!h' LP.TURB B5 BRG VIB N31BA005 5 LP TURB B6 BRG VIB N31BA006 5 LP TURB C7 BRG VIB N31BA007 5 LP.TURB C8 BRG VIB N31BA008 5 GEN 9 BRG VIB N31BA009 5 GEN 10 BRG VIB N31BA010 5 ALTERREX 11 BRG VIB N31BA011 5 ALTERREX 12 BRG VIB . N31BA012 5
'TURB TH FR UP BRG TEMP N31BA019 5 TRUB TH FR LW BRG TEMP N31BA020 5 TURB TH REAR UP BRG TEMP N31BA021 5
-TURB TH REAR LW BRG TEMP N31BA022 5 1
ATTACHMENT G Page 1 DIGITAL INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION B21EC001 ISLN VALVE GROUP 1-A COMMAND B21EC002 ISLN VALVE GROUP 1-B COMMAND B21EC003 ISLN VALVE GROUP 2-A COMMAND B21EC004 ISLN VALVE GROUP 2-B COMMAND B21EC005 ISLN VALVE GROUP 3-A COMMAND B21EC006 ISLN VALVE GROUP 3-B COMMAND B21EC007 ISLN VALVE GROUP 4-A COMMAND B21EC008 ISLN VALVE GROUP 4-B COMMAND B21EC009 ISLN VALVE GROUP 5-A COMMAND B21EC010 ISLN VALVE GROUP 5-B COMMAND B21EC013 RPS CHANNEL ISOLATION A STATUS B21EC014 RPS CHANNEL ISOLATION B STATUS B21EC015 RPS CHANNEL ISOLATION C STATUS B21EC016 RPS CHANNEL ISOLATION D STATUS B21ECO21 SRV INITIATION STATUS B21ECO22 SRV INITIATION STATUS
.B21ECO23 SRV INITIATION STATUS B21EC024 SRV INITIATION STATUS B21ECO25 SRV INITIATION STATUS B21ECO26 SRV INITIATION STATUS B21ECO27 SRV INITIATION STATUS
- -- B21EC028- -SRV INITIATION STATUS O sa'eco29 B21EC030 sav 1" 7 ^T o" sTATos SRV INITIATION STATUS
~.B21EC031 SRV INITIATION STATUS
.B21EC032; SRV. INITIATION STATUS B21EC033 SRV INITIATION STATUS B21EC034 SRV INITIATION STATUS B21EC035 SRV INITIATION STATUS
.B21EC036 SRV INITIATION STATUS B21EC037 SRV INITIATION STATUS
.B21EC038. SRV INITIATION STATUS,
? ~
'B21EC039 SRV. INITIATION STATUS
.B21EC042- SRV POSITION B21EC043' SRV POSITION
,. ~B21EC044 .SRV POSITION L B21EC045 .SRV POSITION-1B21EC046 SRV POSITION B21EC047 :SRV POSITION.:
l ~ .: g' B21EC048+ ,SRV POSITION
- B21EC049. :-SRV POSITION B21EC050 SRV POSITION ~
@m@h 'C N3
- B21EC051:
'B21EC052-
.SRV POSITION:
iSRV POSITION-
-B21EC053.: SRV: POSITION'-
i = " ~ @$$; .. - ~ B21EC054L' SRV POSITION'
-%- B21FC055 'SRV POSITION:
y - , 'PC B21EC056' 'SRV POSITION'
$6 i :B21EC058~
=
- B21EC057 SRV POSITION-SRV POSITION -
s
- . ;B21EC059= SRV. POSITION- - '
~ '
, :SRV POSITION
, % d B21EC060 B21EC065= FEEDWATER VALVE POSITION '
~
-/
L
ATTACHMENT G Page 2' DIGITAL INPUTS ERIS SYSTEM 10/26/83 f]
FUNCTION ID DESCRIPTION B21EC066 EEDWATER VALVE POSITION B21EC067 FEEDWATER VALVE POSITION B21EC068 FEEDWATER VALVE POSITION B21EC069 INBOARD MSIV SOLEN 0ID STATUS B21EC070 INBOARD MSIV POSITION B21EC071 INBOARD MSIV POSITION B21EC072 INBOARD MSIV SOLEN 0ID STATUS B21EC073 INBOARD MSIV POSITION B21EC074 INBOARD MSIV POSITION B21EC075 INBOARD MSIV SOLENOID STATUS B21EC076 INBOARD MSIV POSITION B21EC077 INBOARD MSIV POSITION B21EC078 INBOARD MSIV SOLEN 0ID STATUS B21EC079 INBOARD MSIV POSITION B21EC080 -INBOARD MSIV POSITION B21EC081 OUTBOARD MSIV SOLEN 0ID STATUS B21EC082 ' OUTBOARD MSIV POSITION B21EC083 OUTBOARD MSIV POSITION B21EC084 OUTBOARD MSIV SOLENOID STATUS B21EC085 OUTBOARD MSIV POSITION B21EC086 0UTBOARD MSIV POSITION B21EC087 OUTBOARD MSIV SOLENOID STATUS
'(d)
B21EC088 OUTBOARD MSIV POSITION B21EC089 OUTBOARD MSIV POSITION B21EC090 OUTBOARD MSIV SOLEN 0ID STATUS B21EC091 OUTBOARD MSIV POSITION B21EC092 OUTBOARD MSIV POSITION B21EC093 OUTBD MN ST DR ISLN VALVE POSN B21EC094 OUTBD MN ST DR ISLN VALVE POSN-B21EC095 OUTBD MN ST DR ISLN VALVE POSN B21EC0% .OUTBD MN ST DR ISLN VALVE POSN
,B21EC097 .OUTBD MN ST DR ISLN VALVE POSN
? B21EC098 OUTBD MN ST DR ISLN VALVE POSN B21EC099 OUTBD MN ST DR ISLN VALVE POSN B21EC100- OUTBD MN ST DR ISLN VALVE POSN B21EC101 OUTBD MN ST DR ISLN VALVE POSN B21EC102 OUTBD MN ST DR ISLN VALVE POSN l B21EC103 INBD MN ST DR ISLN VALVE POSN B21EC104 INBD MN ST DR ISLN VALVE POSN TN- B21EC150 VACUUM BREAKER POSITION C B21EC151- VACUUM BREAKER POSITION J3 B21EC152 VACUUM BREAKER POSITION D '
B21EC153 VACUUM BREAKER POSITION
- B21EC154 VACUUM BREAKER POSITION O2 .B21EC155 VACUUM BREAKER POSITION g
- B21EC156 VACUUM BREAKER POSITION e B21EC157 VACUUM BREAKER POSITION f)v
'[ f B21EC158 B21EC159 VACUUM BREAKER POSITION VACUUM BREAKER POSITION
, : B21EC160. VACUUM BREAKER POSITION A B21EC161 VACUUM BREAKER POSITION B21EC162 VACUUM BREAKER POSITION
ATTACHMENT G Page 3 DIGITAL INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION
.B21EC163 VACUUM BREAKER POSITION B21EC164- VACUUM BREAKER POSITION B21EC165 VACUUM BREAKER POSITION B21EC166 VACUUM BREAKER POSITION B21EC167- VACUUM BREAKER POSITION B21EC168 . VACUUM BREAKER POSITION B21EC169- VACUUM BREAKER POSITION B21EC170- VACUUM BREAKER POSITION B21EC171 VACUUM BREAKER POSITION B21EC172 VACUUM BREAKER POSITION '
B21EC173. VACUUM BREAKER POSITION
.B21EC174 VACUUM BREAKER POSITION
.B21EC175 VACUUM BREAKER POSITION
, B21EC176 VACUUM BREAKER POSITION B21EC177 . VACUUM BREAKER POSITION B21EC178- VACUUM BREAKER POSITION
'B21EC179 . VACUUM BREAKER POSITION B21EC180 VACUlM BREAKER POSITION B21EC181 VACUUM BREAKER POSITION-B21EC182 - VACUUM BREAKER POSITION
- . 'B21EC183 ' VACUUM BREAKER POSITION B21EC184 VACUUM BREAKER POSITION
'B21EC185 VACUUM BREAKER POSITION B21EC186L 'VACULM BREAKER POSITION B21EC187 VACUUM BREAKER POSITION B21EC188 ISLN VALVE GROUP 3-E COPMAND
'B21EC189, . ISLN VALVE GROUP 3-F COMMAND B33EC001 LFMG SET MOTOR CB 1A-STATUS B33EC002 LFMG SET MOTOR CB 1B STATUS
- B33EC003. LFMG SET GEN CB~2A STATUS B33EC004 LFMG SET GEN CD 2B' STATUS
-B33EC005 RPT CB 3A STATUS
-B33EC009 RECIRC~ PUMP CB SA. STATUS-B33EC010: .RECIRC PUMP CB 5B STATUS
-C11EC001: . SELECTED CONTROL ROD' POSITION w .C11EC002 =CRD PUMP A STATUS T3 C11EC003
- C11EC004-CRD PtMP B STATUS iji 'ALL CONTROL' RODS IN
. "C22EC001 RRCS tell INITIATE--CHANNEL IA .
,' .k7y1. C22EC002' RRCS 901L INITIATE--CHANNEL.1B' ,
di L#
-C22EC003-
=C22EC004 RRCS ISIL' INITIATE--CHANNEL'2A RRCS ISIL INITIATE--CHANNEL 2B:
C .C22EC005 RRCS MIE. INITIATE ARMED-DIV .1
,4 C22EC006 RRCS 90E. INITIATE ARMED--DIV 2-f ~l _i 'C22EC007L -RRCS~ARI INITIATED-DIV 1.
J .g*- lC22EC008 .RRCS ARI INITIATED-DIV 2-i C22EC009! RRCS FW RUNBACK INITIATE-DIV 1
.RRCS FW RUNBACK INITIATE-DIV 2.
4
,'Q C22EC010' C22EC011' RRCS RX WATER LEVEL 2-1A g ,
s >
.L.
ATTACHMENT G Page 4 DIGITAL INPUTS ERIS SYSTEM '10/26/83 FUNCTION ID DESCRIPTION C22EC012 RRCS RX WATER LEVEL 2-1B C22EC013 .RRCS RX WATER LEVEL 2-2A <
C22EC014 RRCS RX WATER LEVEL 2-2B
~ C22EC015 RRCS RX HIGH DOME PRESS-1A C22EC016 RRCS RX HIGH DOME PRESS-1B.
C22EC017~ RRCS RX HIGH DOME PRESS-2A C22EC018 RRCS RX HIGH DOME PRESS-2B C22EC019 RRCS CONFIRMED AWS-DIV 1 C22EC020 RRCS CONFIRMED AWS-DIV 2 C22ECO21 RRCS POTENTIAL AWS-DIV 1 C22ECO22. RRCS POTENTIAL AW S-DIV 2 C22EC023 RRCS W/LFMG TRIP TIMER-DIV 1 C22ECO24 RRCS FW/LFMG TRIP TIMER-DIV 2
.C22ECO25 RRCS ARI READY FOR RESET-DIV 1 C22ECO26~ RRCS ARI READY FOR RESET-DIV 2
.. C22ECO27 RRCS READY FOR RESET-DIV 1 C22ECO28 RRCS READY FOR RESET-DIV 2 C22ECO29.. 'RRCS LFMG SET TRANSFER-DIV 1 C22EC030 RRCS LFMG SET TRANSFER-DIV'2 C22EC031 RRCS RWCU ISOLATED-DIV 1
.C22EC032 RRCS~RWCU ISOLATED-DIV 2 C34EC001 TDFP A TRIP. STATUS
-Qm C34EC002 TDFP B TRIP STATUS C34EC003 MDFP C TRIP STATUS C41EC001 SLCS PUMP A STATUS.
'C41EC002- SLCS PUMP B STATUS C41EC003 SLCS SQUIB VALVE STATUS C41EC004' SLCS SQUIB VALVE STATUS
.C41EC005 SLCS PUMP SUCTION VALVE POSITIOir C41EC006- SLCS PUMP SUCTION VALVE POSITION C41EC007 SLCS RX INLET MAINT VALVE POSN 7 C41EC008 SLCS RX INLET MAINT VALVE POSN
-C41EC009 SLCS TEST TANK OUTLET VALVE POSN C41EC010 SLCS TEST TANK OUTLET VALVE POSN
<C41EC011 SLCS PUMP SUCTION VALVE POSITION ~
.C41EC012 SLCS PUMP SUCTION VALVE POSITION C51EC001- SRM A. POSITION--FULL IN C51EC002 SRM B POSITION--FULL IN
-C51EC003. -SRM.C POSITION--FULL IN
%"y1 >$ C51EC004 .SRM D. POSITION--FULL IN-ja C71EC001 CHANNEL SCRAM A STATUS-
M4 .C71EC004- CHANNEL SCRAM D STATUS.
Qv3 ;C71EC005 C71EC006 MAIKIAL SCRAM A STATUS-MANUAL SCRAM B STATUS-My- ~C71EC007: MANUAL SCRAM.c STATUS:
-(,'y
'v W C71EC008 MANUAL. SCRAM D STATUS ep ; J C71EC009: RPT UXIIC A STATUS -
E y;;}. -C71EC010
~
'RPT u)GIC B STATUS
-y j C71EC011 RX MODE.Si1TCH POSITION.
'ea C71EC012- RX MODE SWITCH POSITION 4
ATTACHMENT G Page 5
- DIGITAL INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION C71EC013 RX MODE SWITCH POSITION C71EC014 RX MODE SWITCH POSITION 095EC001 MNL EVENT MARKER-CONTROL ROOM C95EC002 MNL EVENT MARKER-TSC D17EC001 OUTBD ISOLATION VALVE POSITION D17EC002 OUTBD ISOLATION VALVE POSITION D17EC003 INBD ISOLATION VALVE POSITION D17EC004 INBD ISOLATION VALVE POSITION D17EC005 OUTBD ISOLATION VALVE POSITION D17EC006 0UTBD ISOLATION VALVE POSITION D17EC007 INBD ISOLATION VALVE POSITION
-D17EC008. -INBD ISOLATION VALVE POSITION D17EC009 OUTBD-ISOLATION VALVE POSITION D17EC010- OUTBD ISOLATION VALVE POSITION D17EC011 INBD ISOLATION VALVE POSITION D17EC012 INBD ISOLATION VALVE POSITION D17EC013- 00TBD ISOLATION ~ VALVE POSITION D17EC014 OUTBD ISOLATION VALVE POSITION D17EC015- INBD ISOLATION VALVE POSITION D17EC016: INBD ISOLATION VALVE POSITION.
D23EC001- OUTBD ISOLATION VALVE POSITION.
D D23EC002 OUTBD ISOLATION VALVE POSITION O D23EC003- OUTBD-ISOLATION VALVE POSITION D23EC004 OUTBD ISOLATION VALVE POSITION D23EC005- OUTBD ISOLATION VALVE POSITION D23EC006' OUTBD ISOLATION VALVE POSITION -
D23EC007 OUTBD ISOLATION VALVE POSITION D23EC008 OUTBD ISOLATION VALVE' POSITION
~
D23EC009 INBD ISOLATION VALVE POSITION
-D23EC010: -INBD ISOLATION VALVE POSITION.
D23EC011 INBD. ISOLATION VALVE POSITION D23EC012 INBD ISOLATION VALVE POSITION
-D23EC013 INBD ISOLATION VALVE POSITION
~D23EC014 INBD ISOLATION VALVE' POSITION
.D23EC015- :INBD ISOLATION VALVE POSITION.
-D23EC016 -INBD ISOLATION VALVE POSITION D23EC017 _-ISOLATION VALVE POSITION
-D23EC018 ISOLATION VALVE POSITION
- g. E12EC001 :RHR PUMP A STATUS-
- E12EC002 RHR PLMP B STATUS ~-
.;$a
'g E12EC003 RHR PUMP C STATUS
' JA E12EC004 OUTE RHR SHTDN CLG SUCT VLV POS s
1@.
lE12EC005:
E12EC006 OUTBD RHR SHTDN CLG SUCT VLV POS INBD RHR SHTDN CLG SUCT VLV POSN E12EC007- INBD RHR SHTDN CLG SUCT VLV.POSN
- E12EC008. RHR VALVE POSITION E12EC009 :RHR VALVE POSITION
@*B .
! 7'N RHR PUMP A POOL:SUCT VALVE POSN
-E12EC012 "M #
'E12EC013, Mi;E12EC014 RHR PUMP.A POOL SUCT VALVE POSN.
iRHR VALVE POSITION
.RHR VALVE POSITION M" OE12EC016 E12EC015'
% ,RHR VALVE' POSITION t
ATTACHMENT G Page 6 oro T^' 'o'26'83 O- "eu's ra's s'ste"
-FUNCTION ID DESCRIPTION E12EC017 RHR VALVE POSITION E12EC018 RHR VALVE POSITION E12EC019 RHR VALVE POSITION E12ECO20 RHR VALVE POSITION E12ECO21- RHR VALVE POSITION E12ECO22 RHR VALVE POSITION E12ECO23 RHR VALVE POSITION E12ECO24 RHR VALVE POSITION
~E12ECO25- RHR VALVE POSITION E12ECO26 RHR VALVE POSITION E12ECO27 RHR VALVE POSITION E12ECO28 RHR VALVE POSITION E12ECO29 RHR VALVE POSITION E12EC030 RHR VALVE POSITION E12EC031 RHR VALVE POSITION E12EC032 RHR VALVE POSITION E12EC033 RHR VALVE POSITION E12EC034 RHR A SHTDN CLG RET VALVE POSN E12ECO35 RHR A SHTDN CLG RET. VALVE POSN E12EC036 RHR A CNTMT SPRAY VALVE-POSN E12EC037 RHR A CNTMT SPRAY VALVE POSN
.E12EC038 RHR VALVE POSITION h-- E12EC039_ RHR VALVE POSITION E12EC040- RHR VALVE AIR STATUS
-E12EC041 RHR VALVE AIR STATUS E12EC042 RHR A INJECTION VALVE POSITION E12EC043 RHR A INJECTION VALVE POSITION-
~E12EC044 RHR VALVE POSITION E12EC045 RHR VALVE POSITION E12EC046 RHR A INJECTION CHECK VLV POSN E12EC047- RHR A INJECTION CHECK VLV POSN E12EC048 RHR VALVE POSITION-E12EC049 RHR VALVE POSITION
-E12EC052- RHR VALVE POSITION E12EC053. RHR VALVE POSITION E12EC054 -RHR VALVE POSITION E12EC055 RHR VALVE POSITION pgr E12EC056 RHR VALVE POSITION
$yg E12EC057 RHR VALVE POSITION
~g3 9 E12EC058 RHR VALVE POSITION
,63 .E12EC059 RHR VALVE POSITION
&W E12EC060 RHR VALVE POSITION y:j$ : .E12EC061' RHR VALVE POSITION
- q E12EC062- 'RHR VALVE POSITION WtW -
E12EC063'
- E12EC064 RHR VALVE POSITION.
RHR VALVE POSITION.
c *Jd$ E12EC065: IBIR VALVE POSITION Li J
1 pg : E12EC066 RHR VALVE POSITION g.. E12EC067. a;RHR VALVE POSITION pd .E12EC068
'E12EC069
4 ATTACHMENT G Page 7 1
h DIGITAL INPUTS ERIS SYSTEM DESCRIPTION 10/26/83 FUNCTION ID t
[
E12EC071 RHR VALVE POSITION h E12EC072 RHR VALVE POSITION
- E12EC073 RHR VALVE POSITION
. E12EC074 RHR VALVE POSITION j E12EC075 RHR VALVE POSITION
- . E12EC078 RHR B CNTMT SPRAY VALVE POSN 4
E12EC079 RHR B CNTNT SPRAY VALVE POSN
- E12EC080 RHR VALVE POSITION E12EC081 RHR VALVE POSITION F E12EC082 RHR VALVE AIR STATUS E12EC083 RHR VALVE AIR STATUS
2 E12EC086 RHR VALVE POSITION E12EC087 RHR VALVE POSITION
/ E12EC089 RHR B INRCTION CHECK VLV POSN E12EC090 RHR VALVE POSITION E12EC091 RHR VALVE POSITION
.]~( E12EC092-E12EC093 RHR C INJECTION CHECK VLV POSN RHR C INRCTION CHECK VLV POSN
, E12EC094 RHR C INACTION VALVE POSITION ;
L E12EC095 RHR C INRCTION VALVE POSITION i
! E12EC096" RHR VALVE POSITION' i RHR VALVE POSITION I E12EC097 E12EC098~ -RHR VALVE POSITION
,' E12EC099 .RHR VALVE POSITION ,
E12EC100 RHR VALVE POSITION LJ E12EC101- RHR VALVE POSITION I' E12EC102 RHR VALVE POSITION E12EC103 RHR VALVE POSITION.
E12EC104 . RHR PtMP C POOL.SUCT VALVE POSM i
-E12EC105- RHR PUMP:C POOL SUCT VALVE POSN .
'1 ~
E12EC106- RNR WATER LEG PUMP STATUS ,
- E12EC107 RHR VALVE POSITION !
L i __
- E12EC108
- RNR VALVE POSITION U
E12EC109 RHR VALVE POSITION
, 1 #@b 'E12EC110 .RHR VALVE POSITION '!
k :E12EC111 'RHR VALVE POSITION ,
8(ih y..o c /E12EC112-
.E12EC113 RHR VALVE POSITION RHR A INOP STATUS -[
-/ C# E12EC114: ~RNR 8 INOP STATUS e
$ E12EC115 :RHR C INOP STATUS
- $g$ 1 T
E21EC001 E21EC002-
- LPCS SYSTEM INITIATION STATUS
.LPCS SYSTEM INOP. STATUS ,
$t
~
E21EC003 LPCS PUMP STATUS l
.~# h- E21EC004L LPCS INJECTION VALVE POSITION E21EC005' LPCS IN RCTION VALVE POSITION-U ,
M9" ig B'I M 'c' E M CK L.FCS c"VALVE
POSITION
' ' ", q
.. _ ._..-.; -._ _ _ ..--.u.. __.- _.-._ . , , ~ . . . - _ . - ,._.a
ATTACHMENT G Page 8 DIGITAL INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION E21EC008 LPCS SUCTION VALVE POSITION E21EC009 LPCS SUCTION VALVE POSITION E21EC010 LPCS MIN FLOW TO POOL VALVE POSN
, E21EC011 LPCS MIN FLOW TO POOL VALVE POSN E21EC012 LPCS TEST RET TO POOL VALVE POSN E21EC013 LPCS TEST RET TO POOL VALVE POSN E21EC014 LPCS INJ MAINT VALVE POSITION E21EC015 LPCS INJ MAINT VALVE POSITION E21EC016 LPCS SYSTEM LINE BREAK STATUS E21EC017 LPCS WATER LEG PUMP STATUS E22EC001 HPCS SYSTEM INITIATION STATUS E22EC002 HPCS SYSTEM INOP STATUS E22EC003 HPCS PUMP STATUS E22EC006 HPCS WATER LEG PUMP STATUS E22EC007 HPCS INJECTION VALVE POSITION E22EC008 HPCS INJECTION VALVE POSITION E22EC009 HPCS TEST CHECK VALVE POSITION E22EC010 HPCS TEST CHECK VALVE POSITION E22EC011 HPCS TEST RET TO POOL VALVE POSN E22EC012 HPCS TEST RET TO POOL VALVE POSN E22EC013 HPCS MIN FLOW TO POOL VALVE POSN D E22EC014 HPCS MIN FLOW TO POOL VALVE POSN i [O E22EC015 HPCS PUMP POOL SUCT VALVE POSN
( E22EC016 HPCS PUMP POOL SUCT VALVE POSN E22EC017 HPCS PUMP CST SUCT VALVE POSN E22EC018 HPCS VALVE POSITION E22ECO23 HPCS INJ MAINT VALVE POSITION E22ECO24 HPCS INJ MAINT VALVE POSITION E22ECO25 HPCS SYSTEM LINE BREAK STATUS E22ECO26 DIV 3 DIESEL GEN INOP STATUS E31EC001 RWCU LEAK DETECTION DIFF FLOW A E31EC002 RWCU LEAK DETECTION DIFF FLOW B E51EC001 RCIC SYSTEM INITIATION STATUS E51EC002 RCIC TURB SPLY DR POT LVL STATUS l E51EC003 RCIC TURB EXH DR POT LVL STATUS E51EC004 RCIC WATER LEG PUMP STATUS E51EC005 RCIC GLAND SEAL CPRSR STATUS l
E51EC006 RCIC OUTBD ST SPLY ISLN VLV POSN E51EC007 RCIC OUTBD ST SPLY ISLN VLV POSN 6, E51EC008 RCIC OUTBD VAC BRKR ISLN VLV POS VG E51EC009 RCIC OUTBD VAC BRKR ISLN VLV POS
(, E51EC010 RCIC EXHAUST TO POOL VALVE POSN
- s 3 E51EC011 RCIC EXHAUST TO POOL VALVE POSN Y E51EC012 RCIC TRIP /0PERATOR STATUS W E51EC013 RCIC TRIP /0PERATOR STATUS b' E51EC014 RCIC TRIP / THROTTLE VALVE POSN
_ 7% E51EC015 RCIC TRIP / THROTTLE VALVE POSN V
) %'
d' E51EC016 E51EC017 RCIC ST LINE DR ISLN VALVE POSN RCIC ST LINE DR ISLN VALVE POSN C $ E51EC018 'RCIC TURB EXH DR ISLN VALVE POSN Q E51EC019 RCIC TURB EXH DR ISLN VALVE POSN Vj E51EC020 - RCIC ST LINE DR.ISLN VALVE POSN
ATTACHMENT G Page 9 DIGITAL INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION E51EC021 RCIC ST LINE DR ISLN VALVE POSN E51ECO22 RCIC TURB EXH DR ISLN VALVE POSN E51ECO23 RCIC TURB EXH DR ISLN VALVE POSN E51EC024 RCIC INBD ST SPLY ISLN VLV POSN E51ECO25 RCIC INBD ST SPLY ISLN VLV POSN E51ECO26 RCIC ST LINE WARMUP VALVE POSN E51ECO27 RCIC ST LINE WARMUP VALVE POSN E51EC028 RCIC INBD VAC BRKR ISLN VLV POSN E51ECO29 RCIC INBD VAC BRKR ISLN VLV POSN E51EC034 RCIC TURBINE TRIP STATUS E51EC035 RCIC CNDS TRAP BYP VALVE POSN E51EC036 RCIC CNDS TRAP BYP VALVE POSN E51EC037 RCIC LEAK DETECTION-DIV 1 E51EC038 RCIC LEAK DETECTION-DIV 2 E51EC039 ISLN VALVE GROUP 6-A COMMAND E51EC040 ISLN VALVE GROUP 6-B COMMAND E51EC041 RCIC TURB LUBE OIL TEMP STATUS E51EC042 RCIC INJECTION VALVE POSN E51EC043 RCIC INJECTION VALVE POSN E51EC044. RCIC POOL SUCTION VLV POSN
. E51EC045 RCIC POOL SUCTION VLV POSN
~O; E51EC046 RCIC CST SUCTION VLV POSN V E51EC047 RCIC CST SUCTION VLV POSN E51EC048 .RCIC TEST CHECK VLV POSN E51EC049 RCIC TEST CHECK VLV POSN
.-E51EC050 RCIC TEST RET TO POOL VLV POSN E51EC051 RCIC TEST RET TO POOL VLV POSN E51EC052- RCIC TEST RET TO CST VLV POSN F RCIC TEST RET TO CST VLV-POSN E51EC053 i E51EC054' .RCIC TEST RET TO CST VLV POSN L E51EC055 RCIC TEST RET TO CST VLV POSN G33EC002 RWCU. PUMP A STATUS-l~ G33EC003: RWCU PUMP B STATUS
G33EC005 -RWCU INBD ISLN VALVE POSITION G33EC006: -RWCU OUTBD ISLN VALVE POSITION E RWCU OUTBD ISLN VALVE: POSITION.
G33EC007~
_G33EC008 RWCU INBD ISLN VALVE POSITION-L ,. .:G33EC009 .RWCU INED ISLN VALVE' POSITION P
'g eg.
~G33EC012- RWCU INBD ISLN VALVE POSITION
[S ~f G33EC013, RWCU INBD ISLN VALVE POSITION.
M* G33EC014 RWCU OUTBD ISLN. VALVE POSITION
.G33EC015 RWCU OUTBD ISLN: VALVE POSITION'
$c&
^
LG33EC016 RWCU OUTBD ISLN. VALVE POSITION
.- .M IG33EC017 :RWCU OUTBD ISLN VALVE POSITION-l
. VD - G!d -.
.RWCU INBD ISLN VALVE POSITION RWCU INBD ISLN VALVE POSITIONL a fpf.G33EC020 RWCU VALVE POSITION afh;G33EC021; RWCU VALVE POSITION e -
gj G33EC024 RWCU, VALVE POSITION W
y ,4 e,,, y,, _
g p-,- ny , m e
ATTACHMENT G Page 10 h DIGITAL INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION I
G33EC025 RWCU VALVE POSITION G33ECO26 RWCU VALVE POSITION G33ECO27 RWCU VALVE POSITION G33EC028 RWCU VALVE POSITION G33ECO29 RWCU VALVE POSITION G33EC030 RWCU VALVE POSITION G33EC031 RWCU VALVE POSITION G33EC032 RWCU VALVE POSITION G33EC033 RWCU VALVE POSITION G33EC034 RWCU VALVE POSITION G33EC035 RWCU VALVE POSITION G33EC036 RWCU VALVE POSITION
-G33EC037 RWCU VALVE POSITION G33EC038 RWCU VALVE POSITION G33EC039 RWCU VALVE POSITION G33EC040 RWCU VALVE POSITION' G36EC001 FILTER /DEMIN VALVE POSITION G36EC002 FILTER /DEMIN VALVE POSITION G36EC003 FILTER /DEMIN VALVE POSITION G36EC004 FILTER /DEMIN VALVE POSITION
. , , 'G36EC005 FILTER /DEMIN VALVE POSITION G36EC006 FILTER /DEMIN VALVE POSITION
(")- G36EC007 FILTER /DEMIN VALVE POSITION G36EC008 FILTER /DEMIN VALVE POSITION G36EC009 FILTER /DEMIN VALVE POSITION G36EC010 FILTER /DEMIN VALVE POSITION G36EC011 FILTER /DEMIN VALVE POSITION G36EC012 FILTER /DEMIN VALVE POSITION, G36EC013 FILTER /DEMIN VALVE POSITION G36EC014 FILTER /DEMIN VALVE POSITION G36EC015 FILTER /DEMIN VALVE POSITION G36EC016 FILTER /DEMIN VALVE POSITION G41EC001 OUTBD FPCCU ISOLATION VALVE POSN G41EC002 OUTBD FPCCU ISOLATION VALVE POSN G41EC003 OUTBD FPCCU ISOLATION VALVE POSN
-G41EC004 OUTBD FPCCU ISOLATION VALVE POSN
~G41EC005 INBD FPCCU ISOLATION VALVE POSN G41EC006 INBD FPCCU ISOLATION VALVE POSN G42EC001 SUPPR POOL CLEANUP PUMP STATUS tf G42EC002 ISOLATION VALVE POSITION (pg G42EC003 G42EC004 ISOLATION VALVE POSITION ISOLATION VALVE POSITION M G42EC005 ISOLATION VALVE POSITION i;[ G43EC001 OUTBD ISOLATION VALVE POSITION W- G43EC002 OUTBD ISOLATION VALVE POSITION y G43EC003 OUTBD ISOLATION VALVE POSITION y G43EC004- -ISOLATION VALVE POSITION
( t , G43EC005 ISOLATION VALVE POSITION
'd V.- ' G43EC006 ISOLATION VALVE POSITION g*: OUTBD LIQ RAD SUMP ISLN VLV POSN vr:
P;. 'G50EC001 G50EC002 G50EC003 OUTBD LIQ RAD SUMP ISLN VLV POSN INBD LIQ RAD SUMP ISLN VLV-POSN' wa.
ATTACHMENT G Page 11
- DIGITAL INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID- DESCRIPTION
~
G50EC004 INBD LIQ RAD SUMP ISLN VLV POSN G50EC005 RWCU BACKWASH :WER PUMP STATUS
, G61EC001 OUTBD ISOLATION VALVE POSN G61EC002 OUTBD ISOLATION VALVE POSN G61EC003 otTTBD ISOLATION VALVE POSN-G61EC004 OUTBD ISOLATION VALVE POSN G61EC005 INBD ISOLATION VALVE POSN G61EC006 INBD ISOLATION VALVE POSN G61EC007 INBD ISOLATION VALVE:POSN G61EC008 INBD ISOLATION VALVE POSN M14IC001 CNTNT PURGE SUPPLY FAN STATUS M14EC002 CNTMT PURGE-SUPPLY FAN STATUS M14EC003- DRYWELL PURGE FAN STATUS
- DRYWELL PURGE FAN STATUS M14EC004 M14EC005 DW/CNTMT PURGE EXH FAN STATUS M14EC006 DW/CNTMT PURGE EXH FAN STATUS M14EC007 ISOL'ATION VALVE POSITION M14EC008- ISOLATION VALVE POSITION 4-
' M14EC009 ISOLATION VALVE POSITICN :
'M14EC010- ISOLATION VALVE PO3ITION EMER VENT DAMPER POSITION 4
- M14EC011
/~'- M14EC012 EMER VENT DAMPER POSITION
- , .M14EC013 EMER VENT DAMPER POSITION
. M14EC014 EMER VENT DAMPER POSITION
. M14EC015 .. - EMER VENT DAMPER POSITION M14EC016 'EMER VEE DAMPER POSITION.
. -M14EC017 ISCLATION VALVE POSITION M14EC018- ISOLATION-VALVE. POSITION
, M14EC019' . ISOLATION VALVE POSITION- '
4 M14EC020. ISOLATION-VALVE POSITION: .
LM14ECO21 ISOLATION VALVE.FCSITION 4- .M14ECO22:
. ISOLATION VALVE POSITION- s
- M14ECO23 :ISCLATION VALVE POSITION-_ -
M14ECO24~ ISOLATION VALVE POSITION-M14ECO25 -EMER-VDrr DAMPER ~ POSITION I_ . w . M14ECO26-EMER VENT' DAMPER POSITION:
- p~ LM14ECO27 'EMER VE E DAMPER-POSITION-M14ECO28
- EMER VEN DAMPER. POSITION -
,.'~ '
-g jw l.M14EC629 : ~ .EMER VENT DAMPER > POSITION.
,EMER. VENT DAMPER POSITION.
<M14EC030
~
Y 0M15EC001 'EMER VENT DAMPER POSITIONt lEMER VENT! DAMPER FOSITION M15EC002(.
h a M15EC0031 .m EMER VENT DAMPER PO3ITION.
9 - Wn .. M15EC004 L ' MMER VENT / DAMPER POSITIOli
.a 'd?
- se+
J.M15EC005> .MEMER: VENT DAMPER PCSITION
' !M15EC006 # EMER VENT DAMPER POSITION t ?N 'M15EC0071 EMER VENT DAMPER POSITION'
-W hiG:. J M15EC008'; /EMER3 VENT DAMPER ~ POSITION '
MD M" M16EC001',
'M16EC00P_
EMER; VENT. DAMPER ~ POSITION 1 ~
[Q,3fENER~VENTDAMPER, POSITION.
l l Q: e
- ^
M16EC003 M M EMER VENT DAMPED POSITION
-r JTw
.rer,1 M16EC0041 ))EMER'VDITXDAMPEEjPOSITION - P.
gg , cg --
4 m m". _ -
M ,J' * ^
h i a $nl m -..
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~
. . ~: _ . - _ ... . _ . ,
1 ATTACHMENT G Page 12 DIGITAL INPUTS ERIS SYSTEM 10/26/83 l FUNCTION ID. DESCRIPTION l M16EC005' EMER VENT' DAMPER POSITION M16EC006- EMER VENT DAMPER POSITION M16EC007- EMER VENT DAMPER POSITION M16EC008 'EMER-VENT DAMPER POSITION M17EC001 ISOLATION VALVE POSITION-M17EC002 ISOLATION VALVE POSITION M17EC003 ISOLATION VALVE POSITION
' ~
M17EC004 ISOLATION VALVE POSITION
-M17EC005 ISOLATION VALVE POSITION M17EC006 ISOLATION VALVE POSITION
.M17EC007 ISOLATION VALVE POSITION
.M17EC008 ISOLATION VALVE POSITION M17EC009 ISOLATION VALVE POSITION M17EC010 ISOLATION VALVE POSITION-M17EC011 ISOLATION VALVE POSITION
=M17EC012 ISOLATION VALVE POSITION M17EC013 ISOLATION VALVE POSITION M17EC014-- ISOLATION VALVE POSITION M17EC015' ISOLATION VALVE POSITION
, M17EC016 ISOLATION VALVE POSITION.
M17EC017 ISOLATION VALVE POSITION
</7 "
M17EC018 ISOLATION VALVE POSITION
' V ~M17EC019 ISOLATION VALVE. POSITION M17ECO20 ISOLATION VALVE POSITION M23EC001 EMER VENT DAMPER POSITION M23EC002 EMER VEE DAMPER. POSITION
.M23EC003 - EMER VEE DAMPER POSITION M23EC004 EMER-VENT DAMPER POSITION
'M24EC001 EMER VENT DAMPER POSITION M24EC002 EMER VEE DAMPER POSITION M24EC003 'EMER_ VENT. DAMPER POSITION -
M24EC004 EMER VENT DAMPER POSITION
- M24EC005 EMER VEE DAMPER' POSITION ,
M24EC006 EMER VENT DAMPER POSITION
,, , M24EC007 EMER VENT DAMPER POSITION M24EC008. .EMER VENT' DAMPER POSITION '
, M24EC009- EMER VEE DAMPER POSITION!
=M24EC010' ~EMER VEE DAMPER POSITION 4
' ig -
~M24EC011'
.M24EC012-LEMER VEE DAMPER POSITION EMER VEN DAMPER POSITION M25EC001 EMER VEN DAMPER POSITION iht +g ' EMER VENT DAMPER POSITION
.M25EC002-
~
h
- t;mJ M25EC003-
.M25EC004 EMER VENT DAMPER POSITION
-EMER VEE DAMPER POSITION
, Q M25EC005-M25EC006 EMER: VENT. DAMPER POSITION
.EMER VENT. DAMPER POSITION.
- . $j g M25EC007! -EMER_ VENT DAMPER POSITION-EMER VENT DAMPER POSITION.
.C_ .D EV" 'o g '~M25EC008i .EMER VENT DAMPER POSITION.
I M25EC009 N iM25EC010' EMER VEN DAMPER POSITION =
k M25EC011 EMER VENT DAMPER' POSITION
%gM25EC012 EMER_ VENT DAMPER POSITION' s
s , v n~n--.w.-- , w . . .e,,. y , u-n-, e,. ~.-e-e-,- g - ,,s -
. . . - .. ~
V ATTACHMENT G Page 13 D
-DIGITAL INPUTS ERIS SYSTEM- 10/26/83 FUNCTION ID - DESCRIPTION n
M25EC013 1EMER VENT DAMPER POSITION M25EC014- EMER VENT DAMPER POSITION M25EC015 EMER VENT DAMPER POSITION M25EC016 EMER VENT DAMPER POSITION M25EC017 i EMER VENT DAMPER POSITION
'M25EC018 '
EMER VENT DAMPER POSITION
. M25EC019 EMER VENT DAMPER POSITION M25EC020 EMER VENT-DAMPER POSITION M25EC021 EMER VENT DAMPER POSITION
.M25EC022" EMER VENT DAMPER POSITION M25ECO23 .EMER VENT DAMPER POSITION M25ECO24 EMER VENT DAMPER POSITION M25ECO25 ISOLATION VALVE POSITION ,
M25ECO26 -ISOLATION VALVE POSITION M25ECO27 ISOLATION VALVE POSITION
-M25ECO28 ISOLATION VALVE POSITION M26EC001 EMER VENT DAMPER POSITION M26EC002 EMER VENT DAMPER POSITION
, :M26EC003 EMER VENT DAMPER. POSITION.
M26EC004 EMER VENT DAMPER POSITION M28EC001 EMER VENT FAN STATUS- -
M28EC002 EMER . VEE FAN STATUS 3
~
M32EC001 EMER. VENT DAMPER POSITION M32EC002- .EMER VENT DAMPER POSITION ,
'M32EC003' .EMER VENT DAMPER POSITION M32EC004 EMER VENT' DAMPER POSITION M39EC001- EMER VENT. FAN STATUS M39EC002 -.EMER' VENT; FAN STATUS M39EC003 EMER' VENT FAN STATUS M39EC004 EMER VENT FAN STATUS -
M39EC005 EMER VENT FAN STATUS, l- M39EC006- EMER VENT FAN STATUS L 'M40EC0011 EMER VENT FAN STATUS o l M40EC002' cEMER VENT FAN STATUS p -M40EC003 ENER VENT FAN STATUS M40EC004- iEMER-VENT FAN STATUS M40EC005. EMER VENT' FAN STATUS ,
, -M43EC001' . EMERGENCY VENT FAN. STATUS
~-g ~
- M43EC002 ! EMERGENCY! VENT FAN STATUS C(. ' M43EC003 EMERGENCY VENT FAN: STATUS g> M43EC004 EMERGENCY VENT FAN ST'~'T, R M43EC005! EMERGENCY VENT FAN C f '
V 'M43EC006 : EMERGENCY VENT FAN SeUs 4 1 .M51EC001~ > ISOLATION . VALVE POSIMON W
, LM51EC002- ISOLATION VALVE POSITION
- @ei M51EC0031 1 ISOLATION' VALVE POSITitN - '
W .-M51EC004' -ISOLATION VALVE POSITION: .
JN
$!k - ' M51EC005. -ISOLATIONLVALVE POSITION ~
L) ; y p 'M51EC006l
~
- ISOLATION VALVE POSITION
. 9M **
M51EC007 l ISOLATION VALVE POSITION m' ISCLATION VALVE ~ POSITION
" Jsk M51EC008 M51EC009--
ISOLATION}ALVEPOSITION p >
x s
- "ti , ,b. ec &
.- . - .- - _. . . . .- .. - - . . . ~ - -. . -
ATTACHMENT G Page 14 DIGITAL INPUTS ERIS SYSTEM 10/26/83 i FUNCTION ID DESCRIPTION M51EC010 ISOLATION VALVE POSITION M51EC011 ISOLATION VALVE POSITION.
M51EC012 . ISOLATION VALVE POSITION
. M51EC013 ISOLATION VALVE POSITION
-M51EC014- ISOLATION VALVE POSITION M51EC015 ISOLATION VALVE POSITION
.M51EC016 LISOLATION VALVE POSITION M51EC017 ISOLATION VALVE POSITION ,
M51EC018 ISOLATION VALVE POSITION M51EC019 . ISOLATION VALVE POSITION:
M51EC020 ISOLATION VALVE POSITION M51EC021 ISOLATION VALVE POSITION M51ECO22 ISOLATION VALVE POSITION
.M51EC023 ISOLATION VALVE POSITION M51ECO24 ISOLATION VALVE POSITION-N21EC001' .FEEWATER HEATER VALVE POSITION N21EC002 FEENATER HEATER VALVE POSITION N21EC003 FEEDWATER HEATER VALVE POSITION.
-N21EC004 FEEDWATER HEATER VALVE POSITION N21EC005 FEEDWATER HEATER VALVE POSITION -
' ~
... N21EC006 FEEDWATER HEATER VALVE POSITION
.N21EC007 uFEEDWATER HEATER' VALVE POSITION N21EC006- FEEDWATER HEATER VALVE POSITION N21EC009- FEEDWATER HEATER VALVE POSITION N21EC010: FEEDWATER-HEATER VALVE POSITION
-N21EC011 CNDS BOOSTER. PUMP A TRIP' STATUS N21EC012- CNDS' BOOSTER PUMP C. TRIP: STATUS-N21EC013. HOWELL PUMP A TRIP! STATUS '
_ N21EC014- CNDS BOOSTER PUMP B1 TRIP STATUS
.N21EC015= HOWELL-PUMP B TRIP STATUS
'N21EC016 HOTWELL PUMP C TRIP STATUS:
- N23EC001-; CNDS FILTER'A.ON-LINE STATUS N23EC002.. _ CNDS FILTER B ON4INELSTATUS N23EC003 -CNDS FILTER C ON-LINE STATUS.
i'
-N23EC004> H CNDS FILTER D~0N4INE STATUS.
.N23EC005 ;CNDS FILTER E ON-LINE STATUS e N23EC006- fCNDS FILTER F.ON-LINE STATUS
%. N23EC007 , CNDS FILTER G ON-LINE STATUS ~
^ 7N23EC0081 - CNDS FILTER II ON-LINE STATUS:
5 'N24EC001 =CNDS DEMIN^AiON-LINE STATUS' .
, E N24EC002 CNDS'DEMIN B ON4INE STATUS 1 !N24EC003 . CNDS DEMIN C'ON4INE STATUS
,, 7 N24EC004 - 7.CNDS DEMIN D ON4INE STATUS '
~
- T- 'N24EC005 CNDS'DEMIN E ON-LINE STATUS pw N24EC006 , ;CNDS DEMIN F ON-LINE STATUS;
- dp -
N27EC001'-
- N27EC002 FEEDWATER. VALVE POSITION-FEEDWATER VALVE POSITION i['[
J'd %. (. LM27EC003 FEEDWATER VALVE POSITION-
~ '
1 c.ge L -N27EC004~ FEEDWATER VALVE POSITION-N2 N27EC005> FEEDWATER VALVE POSITION ~ ,
%wP' '
N27EC006 FEEDWATER VALVE POSITION-N27EC007; FEEDWATER. VALVE. POSITION ~
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s W -- w ..w - - r-w -
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ATTACHMENT G Page 15
- DIGITAL INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION ,
N27EC008 FEEDWATER VALVE POSITION N27EC009 FEENATER VALVE POSITION N27EC010 FEEDWATER VALVE POSITION
- N27EC011 FEEDWATER VALVE POSITION N27EC012 FEEDWATER VALVE POSITION N27EC013- FEEDWATER VALVE POSITION
'N27EC014- FEEDWATER VALVE POSITION N27EC015 FEEDWATER VALVE POSITION N27EC016 .FEEDWATER VALVE POSITION
-N27EC017 FEEDWATER VALVE POSITION
< N27EC018 FEEDWATER. VALVE POSITION N27EC019- FEEDWATER VALVE POSITION
.N27EC020 FEEDWATER VALVE POSITION N27ECO21 FEEDWATER VALVE POSITION N27ECO22 FEEDWATER VALVE POSITION v .N27ECO23 FEEDWATER VALVE POSITION N27ECO24 FEEDWATER VALVE POSITION N27ECO25L FEEDWATER'B00 STER PUMP A STATUS
.N27EC026 FEEDWATER BOOSTER PUMP B STATUS N27ECO27 FEEDWATER BOOSTER PUMP C STATUS N27ECO28 FEEDWATER BOOSTER' PUMP D STATUS 2
N27ECO29- .MDFP C STATUS 3 N32EC001 TURBINE TRIP STATUS N41EC001' ' MAIN' GEN CB S610 PH A-STATUS
-N41EC002 --MAIN GEN CB'S611 PH A-STATUS N41EC003 GENERATOR -TRIP STATUS
- N41EC004~ MAIN GEN CB S610.PH B-STATUS 1N41EC005 1 MAIN GEN CB.S610 PH C-STATUS '
N41EC006 : MAIN GEN CB S611 PH B-STATUS
-N41EC007 . MAIN GEN CB S611 PH C-STATUS P11EC001 ISOLATION VALVE POSITION'-
P11EC002 ISOLATION VALVE POSITION P11EC003 ISOLATION VALVE POSITION 1P11EC004: ISOLATION VALVE POSITION' P11EC005 ISOLATION: VALVE POSITION-P11EC006 ISOLATION VALVE POSITION
, ;P22EC001- ISOLATION VALVE POSITION P22EC002- JISOLATION VALVE: POSITION >
R . P43EC001 ;NCC'00TBD ISOLATION VALVE POSN'
% 1@% :P43EC002' NCC OUTBD ISOLATION VALVE POSN
~
?R P43EC004 NCC OUTBD? ISOLATION VALVE POSN c 'n . P43EC005- NCC-INBD ISOLATION VALVE POSN'
$,D ~ P43EC006 :NCC INBD ISOLATION VALVE.POSN e e&. 'P45EC001 DIV 1 ESW PUMP STATUS Md(. , P45EC002 iDIV 2 ESW PUMP STATUS, -
... - n Y% M P45EC003. ?DIY 3 ESW PUMP STATUS p JQ . "
P50EC001 . ISOLATION VALVE POSITIONn
. J N /: p
~ ~
P50EC002s ~ ISG.ATION VALVE' POSITION' N[k . ISOLATION VALVE ~ POSITION:
% A: P50EC0031 P50EC004' ISOLATION VALVE POSITION lP50EC005- 1 ISOLATION. VALVE. POSITION-y .~- ,
m ..
J - #
j ~g .
g t , , *. n u ,e w---~w ~ < ,
ATTACHMENT G' Page.16' IL DIGITAL INPUTS ERIS SYSTEM 10/26/83 ,
' FUNCTION ID DESCRIPTION P50EC006' ISOLATION VALVE POSITION P51EC001 -ISOLATION VALVE POSITION
-P51ECOS2 ISOLATION VALVE POSITION.
'PS2EC001 ISOLATION VALVE POSITION 1P52EC002 ISOLATION VALVE; POSITION PS2EC003 ISOLATION VALVE POSITION PS2EC004 ISOLATION' VALVE POSITION.
! P52EC005 ISOLATION VALVE POSITION ~
P52EC006 ISOLATION VALVE POSITION, P53EC001 ISOLATION VALVE POSITION P53EC002 ISOLATION VALVE POSITION
-P53EC003 ISOLATION VALVE POSITION P53EC004' : ISOLATION VALVE POSITION
- P53EC005 ISOLATION VALVE POSITION P53EC006 ISOLATION VALVE POSITION 1P53EC007 ~ ISOLATION VALVE POSITION:
ll lP53EC008 : ISOLATION VALVE POSITION L- P53EC009- . ISOLATION VALVE POSITION
! P53EC010, ISOLATIGN VALVE POSITION P53EC011 . ISOLATION VALVE POSITION
~P53EC012: -ISOLATION VALVE POSITION N
O :PS3EC013. LISOLATION VALVE l POSITION M- tP53EC014 ISOLATION VALVE POSITION e :P53EC015, LISOLATION VALVE POSITION P53EC016 ISOLATION VALVE POSITION-P53EC017 ISOLATION VALVE POSITION
^
P53EC018' -ISOLATION VALVE POSITION
'P53EC019 ISOLATION VALVE POSITION-P53EC020. ~ ISOLATION VALVE ~ POSITION F: .P54EC001 ISOLATION. VALVE POSITION L P54EC002 -ISOLATION VALVE POSITION' l P54EC003 ISOLATION VALVE POSITION:
L P54EC004 LISOLATION VALVE POSITION--
e -
-P57EC001: ISOLATION' VALVE POSITION h .P57EC002 1 ISOLATION: VALVE POSITION h4 'P57EC003: ISOLATION VALVE POSITION-
- P57EC004L ISOLATION VALVE" POSITION-
- P57EC005 -ISOLATION VALVE POSITION _
[' ' ISOLATION VALVE POSITION-h,*TA : -
P57EC007 ISOLATION VALVE POSITION:
M ;P57EC008: 3 ISOLATION-. VALVE POSITION:
- 1. 10 0 P86EC001_., :. ISOLATION: VALVE POSITION:
, ' f(@
m9
- P86EC002 LISOLATION VALVE: POSITION-P87EC001~ ISOLATION VALVE POSITION'-
$ "i . TTL $4 P87EC002:
-P87EC003, 1 ISOLATION VALVE POSITION ~
ISOLATION VALVE POSITION i;% ? ISOLATION VALVE POSITION-L A - N :.P87EC004 P87EC005L ~. ISOLATION VALVE POSITION-E11 '
- 1:P87EC006- ISOLATION VALVE: POSITION..
MiklP87EC007: (ISOLATION VALVE' POSITION ~
~
P87EC008.' -ISOLATION VALVE 1 POSITION 14gSP87EC009L
%. ISOLATION VALVE 1 POSITION:-
N W.- d.-
+ < s 1
,. -.wd
ATTACHMENT G Page.17 DIGITAL INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION P87EC010- ISOLATION VALVE POSITION P87EC011 ISOLATION VALVE POSITION P87EC012 ISOLATION VALVE POSITION 1 P87EC013 - -ISOLATION VALVE POSITION P87EC014 ISOLATION VALVE POSITION P87EC015 . ISOLATION VALVE POSITION
- .P87EC016 ISOLATION VALVE POSITION P87EC017 ISOLATION VALVE POSITION P87EC018 ISOLATION VALVE POSITION P87EC019 ISOLATION VALVE POSITION P87EC020- ISOLATION-VALVE' POSITION ~
P87ECO21 ISOLATION. VALVE POSITION P87ECO22 ISOLATION VALVE POSITION ISOLATION VALVE POSITION P87ECO23 P87ECO24- ISOLATION VALVE POSITION
- P87ECO25 : ISOLATION VALVE' POSITION .
- P87ECO26 ISOLATION VALVE POSITION
-P87ECO27 -ISOLATION VALVE POSITION.
-P87ECO28 ISOLATION VALVEfPOSITION-4 R22EC001- ALTTO XFER SWITCH' POSITION
. . . . R22EC002= EH2101.CB POSITION-R22EC003- .EH1114 CB POSITION'
-- -- . .R22EC004 EH1102 CB POSITION.
R22EC005- EH1115 CB POSITION R22EC006' EH1116'CB POSITION-R22EC007 EH1113 CB POSITION R22EC008- EH1104 CB POSITION.
R22EC009 EH1212 CB POSITION R22EC010 EH1214 CB POSITION- '
R22EC011
~EH1213 CB' POSITION R22EC012- <EH1201 CB POSITION R22EC013 EH1209 CB POSITION
'R22EC014 EH1204 CB POSITION ~
" R22EC015: EH1303 CB' POSITION- <
- R22EC016 - ;EH1302_CB POSITION:
.R22EC017- .EH1301 CB POSITION ,
.R22EC019 -Ill1A LOCKOUT R22EC020 L1003 CB' POSITION.
Y..pp
- R22ECO21 R22ECO22 4 ,L1004lCB. POSITION
.L1006 CB POSITION y R22EC023 :L1009 CB POSITION:
W -R22ECO24. :L1010 CB POSITION v4 = R22EC018. 'EH13051CB. POSITION '
R23EC001- EF1A03 CB' POSITION.
[;Q gn e
R23EC002:
'R23EC003:
-EF1B13 CB POSITION
~EF1B03-CB POSITION ~
~
-R23EC004 EF1C13 CB POSITION hlQ@4, 9 'R23EC005.- ~
. 1R23EC006..
- EF1CO3 CB POSITION :
EFID03 CB POSITIONz
.-.g f fR23EC007 BUS FIA POTENTIAL ' 4 LBUS F1B POTElfrIAL p*{1R23EC008!
R23EC009- ' BUS FIB 08 POTENTIALJ
ATTACHMENT G Page 18 DIGITAL INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION R23EC010 BUS FIC POTENTIAL R23EC011 BUS F1D POTENTIAL
- R23EC012 BUS F1D08 POTENTIAL R23EC013 BUS XF1A POTENTIAL R23EC014 BUS B1A POTENTIAL
- ' BUS VIA POTENfIAL R23EC015
- i. -R23EC016 BUS V1B POTENTIAL
- R23EC017 BUS V1C POTENTIAL U.
^
R42EC002 EDIA07 CB POSITION R42EC003 EDIA05 CB POSITION
. R42EC004 EDIA04 CB POSITION R42EC005 EDIA03 CB POSITION R42EC007 ED1B05 CB POSITION R42EC008 ED1807 CB POSITION R42EC009 ED1B04 CB POSITION R42EC010 ED1B03 CB POSITION R42EC011- DIV 3 CB 5 POSITION
, R42EC012 DIV 3 CB 10 POSITION
' ~
R42EC013~ DIV 3 CB 9 POSITION R42EC014- DIV 3 CB 6 POSITION R42EC504 ED2A04 CB POSITION J- :
R42ECSO9 ED2804.CB POSITION l ' .: - R42EC512 - DIV 3 CB 10 POSITION-U2
- c R43EC001 DIV 1 DIESEL GEN INOP STATUS R43EC002 - DIV 2 DIESEL GEN INOP STATUS E' .S11EC001 MANUAL DISCONNECT SWITCH 180
," S11EC002 MANUAL' DISCONNECT SWITCH 180 S11EC003- 100-PY-B XFORMER LOCKOUT l 4
.+
5...
('. '!! j.l . _
i .
ly $, ,??:#h(p.
2 wo ~ ..
m
~
f , ; 'l
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._ Y+ ~-v e n r w , -n ,, ,. ,.m n- , ,,,~ -,-r+ , -,,n-~!-,,.,A,~~,-a,,,,., , ,, .r,y ~ . ', ?
ATTACHMENT H Page 1
'ANAIDG. INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID ' DESCRIPTION SCAN INTERVAL (SEC)*
B21EA001. RX WIDE RANGE LEVEL C 0.033 B21EA002' RX WIDE RANGE LEVEL A 0.033
- B21EA003 RX WIDE RANGE LEVEL L 0.033 B21EA004 RX WIDE RANGE LEVEL B 0.033 B21EA005 RX FUEL ZONE LEVEL C
~B21EA006 RX FUEL ZONE LEVEL D B21EA007 RX SHUTDOWN RANGE LEVEL
~B21EA008 POST ACCIDENT MON RX PRESS A B21EA009 POST ACCIDENT MON RX PRESS B B21EA010 RX UPSET RANGE PRESSURE A B21EA011 RX UPSET RANGE PRESSURE B B21EA012 RX UPSET RANGE PRESSURE C B21EA013 RX UPSET RANGE PRESSURE D
-B21EA014- RX CORE PLATE DIFF PRESSURE 0.033 B21EA015 -REF LEG TEMPERATURE-COLUMN 1 B21EA016 REF LEG TEMPERATURE-COLUMN 2 B21EA017 REF LEG TEMPERATURE-COLUMN 3-B21EA018~ REF LEG TEMPERATURE-COLUMN 4 B21EA019 REF LEG TEMP-SHUTDOWN COLUMN.
.B21EA020 FEEDWATER LINE A TEMPERATURE 0.083 B21EA021 FEEDWATER LINE B TEMPERATURE 0.083 B21EA022- RX BOTTOM HEAD DRAIN TEMPERATURE 1.667
.O
- ~
. B21EA190
'B21EA191 RX VESSEL FLANGE TEMPERATURE RX VESSEL FLANGE TEMPERATURE-
'B33EA001 FLUX CONTROLLER INPUT 0.020
~B33EA002- .RECIRC FLOW CONT INPUT (DEMAND). -0.020
'B33EA003 RECIRC A FLOW CONT FLOW INPUT 0.011 B33EA004 .RECIRC A FLOW CONTROLLER OUTPUT- 0.020
'B33EA005 RECIRC B R.0W CONT FLOW. INPUT 0.011
- B33EA006L RECIRC B FLOW CONTROLLER OUTPUT 0.020:
B33EA007 RECIRC FLUX ESTIMATOR INPUT . 0.020 B33EA008. RECIRC FLUX ESTIMATOR OUTPUT- ~0.020 i B33EA011 ' LOAD DEMAND-RATE LIMITER OUTPUT. 0.020-B33EA012- ' LOAD ~ DEMAND ERROR /MA CONT. INPUT 0.020
, B33EA013 RECIRC FCV A VEL CONT'INP-DEMAND .0.011 B33EA014 RECIRC FCV B VEL CONT.INP-DEMAND: 0.011
'B33EA015 RECIRC FCV A VEL CONT OUTPUT: 0.011
?B33EA016' , 'RECIRC FCV B VEL CONT OUTPUT 'O.011
- n. B33EA017- RECIRC FCV A' ACTUATOR VELOCITY- 0.011 i B33EA018 iRECIRC FCV B ACTUATOR VELOCITY 0.011 e3:. -B33EA019. .RECIRC FCV A POSN CONT IN-DEMAND 0.011 7 1B33EA020t RECIRC FCV B POSN CONT INiDEMAND= 0.011,
'"4 .B33EA021- REACTOR CORE FLOW 'O.033 d.
b
- 833EA024; B33EA025-RECIRC' PUMP-A DIFF PRESSURE.
RECIRC PUMP B DIFF PRESSURE 0.033 0.033 4 B33EA026 , JET PUMP LOOP A FLOW-DOUBLE TAP . 0.011 B33EA027: JET PUMP LOOP.B FLOW-DOUBLE TAP, 0.011
'RECIRC PUMP ELBOW TAP-14A DP 0.011-
-B33EA028
'.-)-~
U,( '
- a 1 B33EA029 RECIRC PUMP ELBOW TAP.14C DP. 'O.011 Ng, 833EA030 RECIRC PtMP ELBOW TAP 24A DP
- RECIRC PUMP ELBOW TAP 24C DP 0.011 0.011 Om -B33EA031
,. 19., . B3 EA0 2
- B3};;EA0[33 JJET PUMP 1 DIFF PRESSURE 0.167
'4
.4.4 ; JET PLMP,2 DIFF PRESSURE - 'O.167E
~
, 3 Scan intervals not listed:have not yet been, determined.
ATTACHMENT H Page 2
% ANALOG INPUTS ERIS SYSTEM 10/26/83 (O
FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC)
B33EA034 JET PUMP 3 DIFF PRESSURE 0.167 B33EA035 JET PUMP 4 DIFF PRESSURE 0.167 B33EA036 JET PUMP 5A DIFF PRESSURE 0.167 B33EA037 JET PUMP 5B DIFF PRESSURE 0.167 B33EA038 JET PUMP 6 DIFF PRESSURE 0.167 B33EA039 JET PUMP 7 DIFF PRESSURE 0.167 B33EA040 JET PUMP 8 DIFF PRESSURE 0.167 B33EA041 JET PUMP 9 DIFF PRESSURE 0.167 B33EA042 JET PUMP 10A DIFF PRESSURE 0.167 B33EA043 JET PUMP 10B DIFF PRESSURE 0.167 B33EA044 JET PUMP 11 DIFF PRESSURE 0.167 B33EA045 JET PUMP 12 DIFF PRESSURE 0.167 B33EA046 JET PUMP 13 DIFF PRESSURE 0.167 -
B33EA047 JET PUMP 14 DIFF PRESSURE 0.167 B33EA048 JET PUMP 15A DIFF PRESSURE 0.167 B33EA049 JET PUMP 15B DIFF PRESSURE 0.167 B33EA050 JET PUMP 16 DIFF PRESSURE 0.167 B33EA051 JET PUMP 17 DIFF PRESSURE 0.167 B33EA052 JET PUMP 18 DIFF PRESSURE 0.167 B33EA053 JET PUMP 19 DIFF PRESSURE 0.167 i B33EA054 JET PUMP 20A DIFF PRESSURE 0.167 '
-(]
B33EA055 JET PUMP 20B DIFF PRESSURE 0.167
'- B33EA056 RECIRC LOOP A SUCT TEMP-NAR RNG 1.667 B33EA057 RECIRC LOOP B SUCT TEMP-NAR RNG 1.667 B33EA062 RECIRC FCV A POSITION 0.004
-B33EA063 RECIRC FCV B POSITION 0.004 B33EA064 RECIRC PUMP MOTOR CURRENT 0.017 B33EA065 RECIRC PUMP MOTOR CURRENT 0.017 B33EA066 RECIRC PUMP A SPEED 0.011 B33EA067 RECIRC PUMP B SPEED 0.011 B33EA089 RECIRC PUMP A VOLTAGE
.B33EA090 RECIRC PUMP B VOLTAGE B33EA091 RECIRC LOOP A SUCT TEMP-WIDE RNG B33EA092 RECIRC LOOP B SUCT TEMP-WIDE RNG B33EA093 LFMG A GENERATOR VOLTAGE B33EA094 LFMG B GENERATOR VOLTAGE
- C11EA001. CRD HCU CHARGING FLOW C11EA002 CRD HCU DRIVE FLOW-GROUP A C11EA003 CRD HCU DRIVE FLOW-GROUP B G)
W
,H ;
C11EA004 C11EA005.
CRD HCU DRIVE FLOW-GROUP C CRD HCU DRIVE FLOW-GROUP D C11EA006 CRD HCU COOLING WATER FLOW L C11EA007 CRD HCU COOLING WATER DIFF PRESS
/N * ' '
C11EA015 -SCRAM VALVE PILOT AIR HDR PRESS
\ J ., C34EA001 FEEDWATER FLOW DEMAND 0.020 C34EA002 MASTER LEVEL CONTROLLER OUTPUT ~ 0.020
~1 C34EA003- FW SU LEVEL CONTROLLER OUTPUT 0.020
. h.;; -C34EA004 . REACTOR LEVEL SETPOINT 0.020 e , e
ATTACHMENT H Page 3 O ^"^'oo "eurs ea1s s'ste" lo'26'83 FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC)
C34EA005 SINGLE ELEMENT CONTROLLER OUTPUT 0.020 C34EA006 W GAIN CHANGER OUTPUT 0.020 C34EA007 FEEDPUMP A CONTROLLER OUTPUT 0.020 C34EA008 FEEDPUMP B CONTROLLER OUTPUT 0.020 C34EA009 FEEDPUMP C CONTROLLER OUTPUT 0.020 C34EA010 FEEDPUMP A M/A STATION OUTPUT 0.020 C34EA011 FEEDPUMP B M/A STATION OUTPUT 0.020 C34EA012 FEEDPUMP C M/A STATION OUTPUT 0.020 C34EA013 TOTAL REACTOR STEAM FLOW 0.033 C34EA014 STEAM LINE A FLOW 0.033 C34EA015 STEAM LINE B FLOW 0.033 C34EA016 STEAM LINE C FLOW 0.033 C34EA017 STEAM LINE D FLOW 0.033 C34EA018 TOTAL REACTOR FEEDWATER FLOW 0.033 C34EA019 FEEDWATER FLOW A 0.033 C34EA020 FEEDWATER FLOW B 0.033 C34EA021 TDFP A FLOW TO VESSEL 0.033 C34EA022 TDFP B FLOW TO VESSEL 0.033 C34EA023 MDFP C FLOW TO VESSEL 0.033 C34EA024 RX NARROW RANGE LEVEL A 0.033 C34EA025 RX NARROW RANGE LEVEL B 0.033 O C34EA026 C34EA027 RX NARROW RANGE LEVEL C RX UPSET RANGE LEVEL 0.033 0.033 C34EA028 NARROW RANGE RX DOME PRESSURE 0.033 C34EA030 WIDE RANGE RX DOME PRESSURE 0.033 C34EA031 TURB ST FLOW (1ST STAGE PRESS) 0.033 C34EA032' TDFP A RECIRC MINIMUM FLOW 0.033 C34EA033 TDFP B RECIRC MINIMUM FLOW 0.033 C34EA034 MDFP C RECIRC MINIMUM FLOW 0.033-C34EA035 W CONT LEVEL INPUT-AFTER SWITCH C41EA002 SLCS TANK LEVEL C41EA003 SLCS PUMP A DISCHARGE PRESSURE C41EA004 SLCS PUMP B DISCHARGE PRESSURE C41EA005 SLCS TANK TEMPERATURE p C41EA006 SLCS PUMP A CURRENT C41EA007- 'SLCS PUMP B CURRENT C51EA001 APRM A ROD BLOCK 0.033 C51EA002 APRM B ROD BLOCK 0.033 I_P2 C51EA003 'APRM A FLUX 0.020 F C51EA004 APRM B FLUX 0.020 c C51EA005 APRM C FLUX 0.020 y C51EA006 APRM D FLUX .0.020
- C51EA007 APRM E FLUX 0.020
. C51EA008 APRM F FLUX 0.020
T C51EA012 LPRM B SELECT 0.020
( C51EA013 LPRM C SELECT 0.020 C51EA014 LPRM D SELECT 0.020 C51EA015 LPRM E SELECT 0.020-
, C51EA016- LPRM F SELECT 0.020 t ,
ATTACHMENT H Page 4 ANALOG INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC)
C51EA017 LPRM G SELECT 0.020 C51EA018 LPRM H SELECT 0.020 C51EA019 HEAT FLUX A 0.033 C51EA020 HEAT FLUX B 0.033 C51EA021 SRM A LOG COUNT RATE C51EA022 SRM B LOG COUNT RATE
, . C51EA023 SRM C LOG COUNT RATE C51EA024 SRM D LOG COUNT RATE C85EA001 PRESSURE SETPOINT A 0.020 C85EA002 PRESSURE SETPOINT B 0.020 C85EA003 PRESS SETPOINT ADJUSTER A OUT 0.020
. C85EA004 PRESS SETPOINT ADJUSTER B OUT 0.020 F C85EA005 PRESSURE REGULATOR A OUTPUT 0.020 i C85EA006 PRESSURE REGULATOR B OUTPUT 0.020 4
C85EA007 PRESS SET ADJR A FD FWD OUTPLIT 0.020
, C85EA008 PRESS SET ADJR B FD FWD OUTPUT 0.020 C85EA009 PRESS CONTROLLER A SENSED PRESS 0.033 '
['
C85EA010 PRESS CONTROLLER B SENSED PRESS 0.033 C85EA011 MAIN TURB TOTAL BYP VALVE POSN 0.004 L C85EA012 MAIN TURBINE BYPASS VALVE 1 POSN 0.004 C85EA013 MAIN TURBINE BYPASS VALVE 2 POSN 0.004 C85EA014 . MAIN TURBINE BYPASS VALVE 3 POSN 0.004 E- C85EA015 MAIN TURBINE BYPASS VALVE 4 POSN 0.004 C85EA016 MAIN TURBINE BYPASS VALVE 5 POSN 0.004
, C85EA017: MAIN TURBINE BYPASS VALVE 6 POSN 0.004
. C85EA018 MAIN TURBINE BYPASS VALVE 7 POSN 0.004 C85EA019 MAIN TURB BYPASS VALVE DEMAND A 0.020 C85EA020- MAIN TURB BYPASS. VALVE DEMAND B 0.020
'D17EA001 0FFGAS POST TREATMENT A-RAD MUN
'D17EA002 0FFGAS POST-TREATMENT B-RAD MON D17EA003 CNTMT VENT EXH PLEN~A-RAD MON D17EA004- CNTNT VENT EXH PLEN B-RAD MON L D17EA005 CNTNT VENT EXH PLEN-C-RAD MON
.D17EA006 CNTNT VENT! EXH PLEN D-RAD MON D17EA007 0FFGAS PRE-TREATMENT-RAD MON 1
'D17EA308. RADWASTE TO ESW-RAD MON' L
D17EA009 'NUC CLOSED COOLING WATER-RAD MON
- rap D17EA010. RADWASTE EFL TO SEWAGE-RAD MON
, W. -- D17EA011" STEAM LINE A RADIATION MON 0.011 h,.
.D17EA012 STEAM LINE B-RADIATION MON. 0.011 0.011
~D17EA013 STEAM LINE C RADIATION MON-.
W E-
- D17EA014'.
D17EA015-STEAM LINE D~ RADIATION MON
- ESK HX DISCH A-RAD MON 0.011 Y
D17EA016- ESW HX DISCH B.-RAD MON Rg .D17EA030i PLANT VENT-GAS RAD MON D. D17EA0311 PLANT VENT-IODINE RAD' MON 41- D17EA032 PLANT VENT-PARTICULATE RAD MON i(]_~~ - A D17EA033- 0FFGAS VENT-GAS RAD. MON
. N :D17EA034- 0FFGAS VENT-IODINE RAD MON'.
-k@W 1 D17EA035 0FFUAS VENT-PARTICULATE RAD MON h' Ti tD17EA036y
- D17EA037' TB/HB VENT-GAS RAD MON-
- TB/HB VENT-IODINE! RAD MON '
, 4. ;
. ,, +- -
ATTACHMENT H Page 5 ANALOG INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC)
D17EA038 TB/HB VENT-PARTICULATE RAD MON D17EA039 CONTROL ROOM-GAS RAD MONITOR D17EA040 CONTROL ROOM-IODINE RAD MONITOR D17EA041 CONTROL ROOM-PARTICULATE RAD MON D17EA042 DRWELL AM-GAS RAD MONITOR D17EA043 DRWELL ATM-IODINE RAD MONITOR D17EA044 DRWELL ATM-PART RAD MONITOR D17EA045 CNTMT ATM4AS RAD MONITOR D17EA046 CNE T ATM-IODINE RAD MONITOR D17EA047- CNTNT ATM-PARTICULATE RAD MON
-D17EA048 CNTNT VES/DW PURGE-GAS RAD MON D17EA049 CN MT VES/DW PURGE-IOD RAD MON D17EA050 CNTMT VES/DW PURGE-PART RAD MON D17EA051 AUX BLDG VENT-GAS RAD MON D17EA052 AUX BLDG VENT-IODINE RAD NOM D17EA053 AUX BLDG VENT-PART RAD MON D17EA054 0FFGAS BLDG VENT-GAS RAD MON D17EA055 0FFUAS BLDG VENT-IODINE RAD MON D17EA056 0FFGAS BLDG VENT-PART RAD MON D17EA059 STEAM PACKING EXH-GAS RAD MON D17EA060 ANNULUS EXHAUST A-GAS RAD MON
- O V
'. D17EA061 -~
D17EA065 ANNULUS EXHAUST B-GAS RAD MON FUEL BLDG VENT 4AS RAD MON D17EA066. -FUEL BLDG-VENT-IODINE RAD MON b FUEL BLDG VENT-PART RAD MON.
D17EA067 .
D17EA068 RADWASTE BLDG EXH-GAS. RAD MON i~
.D17EA069 RADWASTE BLDG EXH-IODINE RAD MON D17EA070 RADWASTE BLDG EXH-PART RAD MON D17EA071 JINTER IE.DG EXH-GAS RAD MON D17EA072 UNDERDRAIN SYS-23 EAST-RAD MON D17EA073- UNDERDRAIN SYS-20 WEST-RAD MON n _D17EA530- PLANT VENT 4AS RAD MON-U2
- D17EA531 PLANT VENT-IODINE RAD MON-U2
-D17EA532 PLANT. VENT-PART RAD MON-U2 0FFGAS VENT-GAS RAD MON-U2 l -D17EA533'
~D17EA534 0FFGAS VENT-IODINE RAD MON-U2 l
L ,?,
p D17EA535- l0FFGAS-VENT-PART RAD MON-U2 eB -D17EA536' :TB/HB VENT-GAS RAD MON-U2 CO. 'D17EA537- TB/HB VENT-IODINE RAD MON-U2
- 77.k D17EA538: TB/HB VENT-PART RAD' MON-U2 l.Q D17EA560; ANNULUS EXH A-GAS RAD' MON-U2
- s.i D17EA561 ANNULUS EXH B4AS RAD MON-U2
'.M _ iD19EA001' : DRWELL A RADIATION MON Q D19EA002: DRWELL B RADIATION MON'
'W a'
-D19EA003 PLANTJVENT4AS RAD MON ~
lD19EA004 PLANT VENT 4AS RAD MON -
L -
L9 :D19EA005 OFFGAS VENT 4AS RAD MON '
L
!A
[ _- [g*'l 'D19EA006 D19EA007
- 0FFGAS VENT-GAS RAD MON 1
- TB/HB VENT-GAS RAD MON ' ' '
M, ~ .D19EA008 TB/HB. VENT-GAS RAD MON.
" , 'D19EA012 TSC AREA RADIATION MONITOR =
D19EA013 ,
. EOF.l AREA RADIATION MONITOR' ,
- ..,w..- , , .-,, , &-n ., -e.,.., s.,,- , , , , , , , - , , - r -,e 4.~--,en ., +, ,-n, ,
ATTACHMENT H Page 6
( ANALOG INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC) 4 D19EA014 TSC-GAS RAD MONITOR D19EA015 TSC-IODINE RAD MONITOR D19EA016 TSC-PARTICULATE RAD MONITOR D19EA017 EOF-GAS RAD MONITOR D19EA018 EOF-IODINE RAD MONITOR D19EA019 EOF-PARTICULATE RAD MONITOR D19EA020 RX BUILDING A RADIATION MONITOR D19EA021 RX BUILDING B RADIATION MONITOR D19EA503 PLANT VENT-GAS RAD MON-U2 D19EA504' PLANT VENT-GAS RAD MON-U2 D19EA505 0FFGAS VENT-GAS RAD MON-U2 D19EA506 0FFGAS VENT-GAS RAD MON-U2 D19EA507 TB/HB VENT-GAS RAD MON-U2 D19EA508 TB/HB VENT-GAS RAD MON-U2 D21EA001 ARM-CRD HCU AREA EAST D21EA002 ARM-CRD HCU AREA WEST D21EA003 ARM-RWCU FLOOR DRAIN AREA D21EA004 ARM-RWCU F/D RCV TANK AREA D21EA005 ARM-TIP DRIVE AREA D21EA006 ARM-UPPER POOL AREA D21EA007 ARM-PERSONNEL AIR LOCK O '
D21EA008 ARM-AUX BUILDILG-EL 574 EAST D21EA009 ARM-AUX BUILDING-EL 574 WEST D21EA010 ARM-HP FW HEATER AREA D21EA011 ARM-FEED PUMP AREA D21EA012 ARM-TURBINE ROOM EAST D21EA013 ARM-TURBINE ROOM WEST D21EA014 ARM-H07WELL PUMP AREA D21EA015 ARM-TURBINE BUILDING SUMP AREA D21EA016 ARM-TURBINE BUILDING-EL 605-D21EA017 ARM-CONDENSATE FILTER PUMP AREA D21EA018 ARM-OFFGAS HOLDUP AREA D21EA019 ARM-OFFGAS BUILDING-EL 584 D21EA020 ARM-OFFGAS AFTER FILTER AREA-D21EA022 ARM-RADWASTE Tl.DG-EL 574-WEST D21EA023 ARM-RADWASTE BLDG-EL 574-EAST ra D21EA024 ARM-RADWASTE BUILDING-EL 602 II D21EA025 ARM-RADWASTE BLDG PRCS SAMPLE RM D21EA026 ARM-RADWASTE EVAPORATOR AREA (i.,4 D21EA027 ARM-FPCCU FLOOR DRAIN AREA D21EA028 ARM-FUEL STORE / PREP POOL AREA D21EA029 ARM-SPENT FUEL STORAGE POOL AREA D21EA030 - ARM-FUEL POOL CIRC PUMP AREA
.D21EA031 ARM-RADWASTE SRW DRUM AREA D21EA032 ARM-RADWASTE BLDG-WASTE COMP D21EA501 ARM-CRD HCU AREA EAST-U2
/ ,) ( D21EA502 ARM-CRD HCU AREA WEST-U2
, D21EA503 ARM-RWCU FLOOR DRAIN AREA-U2 D21EA504 ARM-RWCU F/D RCV TANK AREA-U2
=i .
D21EA505- ARM-TIP DRIVE AREA-U2
"" - :D21EA506 ARM-UPPER POOL AREA-U2 D21EA507 ARM-PERSONNEL AIR LOCK-U2
.. . . . _ . - - . ... ._ -- - - -.=-- -
j.- p..
ATTACHMENT H Page 7 ANALOG INPUTS ERIS SYSTEM 10/26/83 ,
, FUNCTION ID . DESCRIPTION SCAN INTERVAL (SEC)
D21EA508 ARM-AUX BLDG-EL 574 EAST-U2 D21EA509 ARM-AUX BLDG-EL 574 WEST -U2
.D21EA510 ARM-HP FW HEATER AREA-U2 D21EA511 ARM-FEED PUMP AREA-U2 D21EA512 ARM-TURBINE ROOM EAST-U2 D21EA513 . ARM-TURBINE ROOM WEST-U2 D21EA514- ARM-HO1WELL PUMP AREA-U2 D21EA515 ARM-TURBINE BLDG SUMP AREA-U2 D21EA516 . ARM-TURBINE BUILDING-EL 605-U2 D21EA517 -ARM-CNDS FILTER PUMP AREA-U2 LD21EA518 ARM-OFFGAS HOLDUP AREA-U2 D21EA519 ARM-OFFGAS BUILDING-EL 584-U2 D21EA520 ARM-OFFGAS AFTER FILTER AREA-U2
, D23EA001 CNTMT PRESS-WIDE RANGE >
.D23EA002 CNTMT PRESS-WIDE RANGE D23EA003 CNTMT PRESS-NORMAL RANGE .
, D23EA004 -SUPPR POOL WATER TEMPERATURE l , :D23EA005 SUPPR POOL WATER TEMPERATURE D23EA006 SUPPR POOL WATER TEMPERATURE D23EA007 SUPPR POOL WATER' TEMPERATURE'.
, . - : D23EA008.- ~SUPPR POOL WATER TEMPERATURE D23EA009 SUPPR POOL WATER TEMPERATURE G%. D23EA010 SUPPR-POOL WATER TEMPERATURE
=D23EA011 SUPPR POOL WATER TEMPERATURE D23EA012 DR1WELL PRESSURE-NARROW RANGE 0.033 D23EA013 DRYWELL PRESSURE-WIDE RANGE .0.033 '
! .D23EA014 :DRYWELL ATMOSPHERE TEMPERATURE
. D23EA015 DRYWELL ATMOSPHERE TEMPERATURE D23EA016- DRYWELL ATMOSPHERE TEMPERATURE D23EA017- CNTMT PRESS-NORMAL RANGE
~D23EA018. SUPPR POOL WATER TEMPERATURE D23EA019- SUPPR POOL WATER TEMPERATURE D23EA020 SUPPR POOL WATER TEMPERATURE i
'D23EA021. .SUPPR POOL' WATER TEMPERATURE
!- D23EA022 SUPPR POOL WATER TEMPERATURE-
- D23EA023- SUPPR P00L' WATER TEMPERATURE.
~
. yr-i . D23EA024 .SUPPR.P00L' WATER TEMPERATURE
- '3 .D23EA025
- SUPPR POOL WATER TEMPERATURE -
93 D23EA026 DRYWELL PRESSURE-NARROW RANGE 0.033 CW 'D23EA027 -DRYWELL PRESSURE-WIDE RANGE .0.033
, D23EA028 DRYWELL ATMOSPHERE TEMPERATURE' (f[$
ya .D23EA029
- D23EA030 DRYWELL ATMOSPHERE TEMPERATURE DRYWELL ATMOSPHERE; TEMPERATURE 4 *' D23EA031 . UPPER'CONTAllMENT TRAIN A TEMP g
1 Ma.
D23EA032 D23EA033 UPPER CONTAIIMENT TRAIN A TEMP LOWER CONTAIIMENT TRAIN A TEMP..
55 'D23EA034 LOWER CONTAIIMENT TRAIN A TEMP
]a
- C"3 iR LD23EA035 D23EA036-L UPPER CONTAIIMENT TRAIN B TEMP UPPER.CONTAIIMENT TRAIN B TEMP--
W ,. D23EA037. LOWER CONTAIIMENT TRAIN B TEMP M 'D23EA038 LOWER CONTAIISE:NT TRAIN B TEMP E12EA001 RHR XX A LEVEL CONT OUTPUT. 0.033
ATTACHMENT H Page 8 ANAIDG INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC)
E12EA002- RHR HX B LEVEL CONT OUTPUT 0.033 E12EA003 RHR HX A PRESS CONT OUTPUT 0.033 E12EA004 RHR HX B PRESS CONT CUTPUT 0.033 E12EA005 RHR A FLOW 0.033 E12EA006- RHR B FLOW 0.033 E12EA007 RHR C FLOW 0.033 E12EA008 RHR SERVICE WATER FLOW-A E12EA009 RHR SERVICE WATER FLOW-B E12EA010 RHR HX A LEVEL 0.033 E12EA011 RHR HX B LEVEL 0.033 E12EA012 RHR HX A PRESSURE 0.033 E12EA013 RHR HX B PRESSURE 0.033 E12EA017 RHR PUMP A DISCHARGE PRESSURE E12EA018 RHR PUMP B DISCHARGE PRESSURE E12EA019 RHR PUMP C DISCHARGE PRESSURE E12EA020 RHR HX 1A OUTLET TEMPERATURE E12EA021 RHR HX 1B OUTLET TEMPERATURE
.E12EA022 RHR HX 1C OlJTLET TEMPERATURE E12EA023 RHR HX 1D OUTLET TEMPERATURE E12EA024 RHR PUMP A CURRENT E12EA025 RHR PUMP B CURRENT Q
C' E12EA026 E12EA027 RHR PUMP C CURRENT RHR WATER LEG PUMP DISCH PRESS E12EA028 RCIC SUCT PRESS CONT OUTPUT 0.033 E21EA001 LPCS FLOW E21EA003 LPCS PUMP DISCHARGE PRESSURE E21EA004 LPCS PUMP CURRENT E21EA005 LPCS WATER LEG PUMP DISCH PRESS E22EA001 HPCS FLOW 0.033 E22EA004 HPCS WATER LEG PUMP DISCH PRESS E22EA005 HPCS PUMP SUCTION PRESSURE E22EA006 HPCS PUMP DISCHARGE PRESSURE 0.033 E22EA007. HPCS PUMP CURRENT-E22EA008 HPCS TEST LINE VALVE POSITION E22EA009 HPCS TEST LINE VALVE POSITION E31EA001 RCIC STEAM LINE DIFF PRESS. 0.033 E31EA002 RCIC/RHR STEAM LINE DIFF PRESS 0.033 E31EA003 RCIC STEAM LINE DIFF PRESS 0.033 93 ~E31EA004 RCIC/RHR STEAM LINE DIFF PRESS 0.033 VA E31EA005 DRYWELL UNIDENTIFIED SUMP LEVEL
. O,9 E31EA006 DRYWELL IDENTIFIED SUMP LEVEL
- 4
":3 E31EA007 RWCU RETURN FLOW TO CONDENSER
'j -E31EA008 RWCU DUMP FLOW TO FEEDWATER ib .E31EA009 RWCU INLET FLOW-RECIRC SUCTION J E32EA001 MN ST LINE A LEAKAGE FLOW.
1%
' ~ .i E32EA003. MN ST LINE B LEAKAGE FLOW
^ E32EA005 MN ST LINE C LEAKAGE FLOW f N' # E32EA006 MN ST LINE D LEAKAGE FLOW CQ E51EA001 RCIC FLOW CONTROLLER OUTPUT 0.033
$0 E51EA002 'RCIC RGSC CONTROLLER OUTPtJT 0.033 E51EA003 RCIC. SPEED CONTROLLER OUTPUT 0.033
- 3 E51EA004 RCIC. PUMP FLOW 0.033 e -
. _ - - - . . -- - . - - . . . _ ~ .- .- .. . . . - . . - . . .
ATTACHMENT-H. Page 9
{
ANALOG INPUTS ERIS SYSTEM 10/26/83 j FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC)
E51EA005- RCIC PUMP SUCTION PRESSURE 0.033 E51EA006 RCIC PUMP DISCHARGE PRESSURE- 0.033 E51EA007 RCIC TURBINE INLET PRESSURE 0.033 ,
t E51EA008 RCIC TURBINE EXHAUST PRESSURE 0.033
. E51EA011 RCIC TURBINE GOVERNOR VALVE POSN 0.033 :
E51EA012 RCIC STEAM ADMISSION VALVE POSN 0.020
.E51EA013 RCIC RUPTURE DISK STATUS 1
E51EA014 RCIC TURBINE SPEED 0.033 ,
, G33EA002 RWCU NON-REGEN HX OUTLET TEMP G33EA003 - RWCU REGEN HX OUTLET TEMP G36EA001 RWCU FLTR/DEMIN 1A FILTER DP G36EA002 RWCU FLTR/DEMIN IB FILTER DP i G43EA001 SUPPR POOL LEVEL-EXTENDED RANGE-
~G43EA002 SUPPR POOL LEVEL-EXTENDED RANGE 1
G43EA003 SUPPR POOL LEVEL-NARROW RANGE i F '
G43EA004 SUPPR POOL LEVEL-WIDE RANGE
.G43EA005 . UPPER CNTMT~ POOL WATER LEVEL A
, G43EA006' SUPPR POOL LEVEL-NARROW RANGE-G43EA007- SUPPR POOL LEVEL-WIDE RANGE-G43EA008 UPPER CNTNT POOL. WATER LEVEL B F; ~
.G50EA001 FUEL POOL F/D B/W RCV TANK LEVEL G50EA002 CNDS FLTR BACKWASH RCV TANK LVL r
. G50EA003 RWCU FLTR/DEMIN B/W RCV TANK LVL
~M33EA001 PLANT VENT FLOW M33EA002 . PLANT VENT FLOW-U2 i
M36EA001 0FFGAS VENT FLOW L- , M36EA501 0F7 GAS VENT FIDW-U2 M41EA001: TB/HB VENT FLOW
~M41EA501 -TB/HB VENT. FLOW-U2 :
M51EA001 CNTNT HYDROGEN CONCENTRATION
- M51EA002 L CNTNT. HYDROGEN CONCENTRATION -
!~ :N11EA001 .TDFP A LP. STEAM FLOW. 0.033 ~ l
- .N11EA002 TDFP B LP STEAM FLOW 0.033
- l. N11EA003 TDFP HP STEAM FLOW : 0.033 ,
i s ',N11EA004 REHEAT STEAM PRESSURE TO TDFP A 0.033- ,
N11EA005- REHEAT STEAM PRESSURE TO TDFP.B 0.033
, . g% . <
N11EA006 WS 1A 2ND STAGE STEAM FLOW " 0.033 <
M i N11EA007 WS 1B 2ND STAGE STEAM FLOW 0.033-1%KY;3 N11EA008 WS 2A 2ND' STAGE STEAM FLOW -0.033'
.N11EA009 WS 2B 2ND STAGE STEAM FLOW .0.033 e 1,4 N11EA010 WS 1A:2ND STAGE PRESSURE 0.033
'em N11EA011 WS IB 2ND STAGE PRESSURE -0.033 iO N11EA012 WS 2A 2ND STAGE PRESSURE 0.033-
- 4-
.N11EA013- . WS 2B 2ND STAGE PRESSURE ' .0.033 MS -N11EA014J WS 1A -1ST STAGE STEAM FLOW -0.033 J' - WS '1B IST STAGE STEAM FLOW N11EA015: 0.033
. N' v' U{: .N11EA016
%g;( N11EA017.
WS 2A' IST STAGE STEAM FLOW --
WS 2B -1ST STAGE STEAM FLOW - '
0.033 0.033-b N11EA018 WS 1A IST STAGE PRESSURE 0.033
, ^ " -N11EA019 WS -18:1ST STAGE PRESSURE - 0.033 p N11EA020 WS 2A IST STAGE PRESSURE. -0.033
'.'Y'
ATTACHMENT H .Page 10 ANALDG INPWS ERIS SYSTEM '10/26/83
[ . FUNCTION ID DESCRIPTION ' SCAN INTERVAL (SEC)
N11EA021 WS 2B IST STAGE PRESSURE - 0.033
- . N11EA022- WS .1A 2ND STAGE PRESS CONT OUT 0.020 N11EA023 WS 1B 2ND STAGE PRESS CONT OUT. 0.020 N11EA024 WS 2A 2ND STAGE PRESS CONT OUT 0.020
- N11EA025: WS 2B 2ND STAGE PRESS C0!(T OUT 0.020 4- CONDENSER A LEVEL 0.033 N21EA001 N21EA002 CONDENSER B LEVEL 0.033 N21EA003 CONDENSER C LEVEL 0.033 4
- N21EA004 CONDENSATE SYS FLOW CONT OUTPUT 0.020 <
N21EA005 CONDENSER A TEMPERATURE '
1.667-N21EA006 CONDENSER B TEMPERATURE 1.667 N21EA007 CONDENSER C TEMPERATURE 1.667 N21EA008 W HEATER VALVE POSITION N21EA009 PTV VALVE POSITION 0.011 0.033
' N21EA010 HOT SURGE TANK TEMPERATURE N21EA011 HONELL LEVEL 0.033 N21EA012- EMER HOWELL LEVEL CONT OUTPUT 0.020 N21EA013 NORM HONELL LEVEL CONT OUTPUT- 0.020 4
N21EA014 EMER HO WELL MAKEUP.LVL CONT OUT 0.020 N21EA015 AUXILIARY CONDENSER A LEVEL 0.033 N21EA016 AUXILIARY CONDENSER B LEVEL 0.033 L
h- N21EA017 N21EA018 AUX COND A LEVEL CONT OUTPUT AUX COND B LEVEL CONT OUTPUT 0.020 0.020
- N21EA019 CONDENSER PRESSURE-A 0.167 N21EA020 CONDENSER PRESSURE-B 0.167 N21EA021 CONDENSER PRESSURE-C 0.167 N21EA022 W REJECTION FLOW TO CST 0.033 N21EA023 HONELL MAKEUP FLOW FROM CST 0.033
, N21EA024 HOT SURGE TANK LEVEL 0.033 L N21EA025 HOT. SURGE TANK LEVEL CONT OUT 0.020 L N21EA026 CONDENSATE FLOW .O.167
- N21EA027: 'COND BSTR PUMP A DISCH PRESS 0.167 N21EA028- COND BSTR PUMP B DISCH PRESS 0.167 ,
L . N21EA029- COND BSTR PUMP C DISCH PRESS 0.167
( N21EA030 HONELL PUMP. A DISCH PRESSURE - 0.033 N21EA031.. HOWELL PUMP B DISCH PRESSURE-' O.033-
-, N21EA032 HONELL PUMP C DISCH PRESSURE 0.033 IL ; N21EA033 COND BSTR PUMP A SUCTION PRESS- 0.167; 1, '
N21EA034 COND BSTR PUMP B SUCTION PRESS 0.167 N21EA035 COND BSTR PUMP C SUCTION PRESS; -0.167 .
(f 1 N21EA036 ' W IEATER OWLET FLOW ' O.033 i , N21EA037l DC HEATER TEMPERATURE 0.033 -
0.033 N21EA038 . AUXILIARY CONDENSER A VACUUM
- N21EA039 AUXILIARY CONDENSER B VACUUM 0.033 o - N21EA040 HUT SURGE TANK PRESSURE s - N21EA041 NORM HOWELL MAKEUP LVL CONT OUT 0.020 L N23EA001' CONDENSATE FILTER SYSTEM DP 0.033 ,
r 4 N23EA002 ~CNDS FLTR SYS OUT TO DP CONT .0.020
' .[VN- r N23EA003 CNDS FLTR SYS OUT TO FLOW CONT :0.020
'y N24EA001' CONDENSATE DEMIN SYSTEM DP 0.033
'-% N24EA002 CONDENSATE DEMIN DP CONT OUTPUT 0.020 ,
N25EA001 WS REHEATER TANK 1 LEVEL 0.033-
ATTACHMENT H Page 11 ANALOG INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC)
N25EA002 WS REHEATER TANK 2 LEVEL 0.033 N25EA003 WS REHEATER TANK 3 LEVEL 0.033 N25EA004 WS REHEATER TANK 4 LEVEL 0.033 N25EA005 WS 1B TANK EMER LEVEL CONT OUT 0.020 N25EA006 WS IB TANK NORM LEVEL CONT OUT 0.020 N25EA007 WS 1B IST STG DRAIN TANK LEVEL 0.033 N25EA008 WS 1B IST STG EMER LYL CONT OUT 0.020 N25EA009 WS 1B 1ST STG NORM LVL CONT OUT 0.020 N25EA010 WS 1B 2ND STG DRAIN TANK LEVEL 0.033 N25EA011 WS 1B 2ND STG EMER LVL CONT OUT 0.020 N25EA012 WS 1B 2ND STG NORM LVL CONT OUT 0.020 N25EA013 WS 1A TANK EMER LEVEL CONT OUT 0.020 N25EA014 WS 1A TANK NORM LEVEL CONT OUT 0.020 N25EA015 WS 1A IST STG DRAIN TANK LEVEL 0.033 N25EA016 WS 1A 1ST STG EMER LVL CONT OUT 0.020 N25EA017 WS 1A 1ST STG NORM LVL CONT OUT 0.020 N25EA018 WS 1A 2ND STG DRAIN TANK LEVEL 0.033 N25EA019 WS 1A 2ND STG EMER LVL CONT OUT 0.020 N25EA020 WS 1A 2ND STG NORM LVL CONT 00T 0.020 N25EA021 W HTR 6A EMER LEVEL CONT OUT 0.020
.N25EA022 W ER 6B EMER LEVEL CONT OUT 0.020
.N25EA023- WS 2B TANK EMER LEVEL' CONT OUT 0.020 0.020 N25EA024 WS 2B TANK NORM LEVEL COE OUT N25EA025 WS 2B 1ST STG DRAIN TANK LEVEL 0.033 N25EA026 WS 2B IST STG EMER LVL CONT OUT 0.020 N25EA027- "WS 2B 1ST STG NORM LVL' CONT OUT 0.020 N25EA028 WS 2B 2ND STG DRAIN TANK LEVEL 0.033 N25EA029- WS-2B 2ND STG EMER LVL COE OUT 0.020 tN25EA030. WS 2B 2ND STG NORM LVL CONT OUT - 0.020 N25EA031 W HTR-6A NORM LEVEL CONT OW 0.020 N25EA032 W ER 6B NORM LEVEL CONT 007 0.020 N25EA033 l W HTR SA EMER LEVEL CONT OUT: 0.020
.N25EA036- W ER 5B NORM LEVEL COE OUT 0.020 N25EA037 -WS"1B DRAIN TANK LEVEL ' O.033
, LN25EA038_ :WS:2B DRAIN TANK LEVEL _0.033 5'*2 .N25EA039 :WS 1A DRAIN TANK LEVEL 0.033 M' N25EA040- WS 2A DRAIN TANK LEVEL _0.033
, Nc3 '
fbl 1N25EA041 N25EA042'
' WS 2A TANK EMER LEVEL COE OUT WS 2A TANK NORM LEVEL COE OUT-0.020-0.020 iW .N25EA043 . WS-2A IST STG EMER LVL CONT OUT 0.020
- i1 N25EA044 WS 2A IST STG NORM LVL CONT OW 0.020-
- % TN25EA045 - WS 2A 2ND STG DRAIN TANK' LEVEL - 0.033 Q
M R-N25EA046 N25EA047 WS 2A 2ND STG EMER LVL CONT 0UT.
WS 2A 2ND STG NORM LVL COPT OW l0.020 0.020
@ N25EA048 FEEDWATER~ HEATER 6A LEVEL 0.033.
.gp FEEDWATER HEATER 6B LEVEL 0.033-
{.'-
N25EA049 ro M N25EA050 FEEDWATER HEATER 5A LEVEL 0.033
_ 'Pc N25EA051 FEEDWATER HEATER 58 LEVEL 0.033
^
4 EA .
- WS 2A IST STG DRAIN TANK LEVEL 0.033-1- W HTR 2A EMER LEVEL CO E OUT- 0.020
ATTACHMENT H Page 12
' (] ANALOG INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCHIPTION SCAN INTERVAL (SEC)
N26EA002 W HTR 2B EMER LEVEL CONT GUT 0.020 N26EA003 W HTR 2C EMER LEVEL CONT OUT 0.020 N26EA004 W HTR 2A NORM LEVEL CONT OW 0.020 N26EA005 W HTR 2B NORM LEVEL CONT OUT 0.020 N26EA006 W HTR 2C NORM LEVEL CO E OUT 0.020 N26EA007 W ER 1A EMER LEVEL CONT OUT 0.020 N26EA008 W HTR 1B EMER LEVEL CONT OUT 0.020 N26EA009 W WR 1C EMER LEVEL CONT OUT 0.020 N26EA010 W HTR 1A NORM LEVEL CONT OW 0.020 N26EA011 W WR 1B NORM LEVEL CONT OUT 0.020 N26EA012 W HTR 1C NORM LEVEL CONT OLIT 0.020 N26EA013 FEEDWATER HEATER 2A LEVEL 0.033 N26EA014 FEEDWATER HEATER 2B LEVEL 0.033 N26EA015 FEEDWATER HEATER 2C LEVEL 0.033 N26EA016 FEEDWATER HEATER 1A LEVEL 0.033 N26EA017 FEEDWATER HEATER 1B LEVEL 0.033 N26EA018 FEEDWATER HEATER 1C LEVEL 0.033 N26EA019 FEEDWATER HEATER 3A LEVEL 0.033 N26EA020 FEEDWATER HEATER 3B LEVEL 0.033 N26EA021 W HTR 3A EMER LEVEL CONT OUT 0.020 N26EA022 W HTR 3B EMER LEVEL CONT OUT 0.020
- N26EA023 W HIR 3A NORM LEVEL CONT OUT 0.020 v N26EA024 0.020 W HTR 3B NORM LEVEL CONT OUT N27EA001 TDFP A MIN FLOW CONT OUTPUT 0.020 N27EA002 TDFP B MIN FLOW CONT OUTPUT 0.020 N27EA003 MDFP C MIN FLOW CONT OUTPUT 0.020 N27EA004 FW HTR SA OUTLET TEMPERATURE N27EA006 W HTR SB OUTLET TEMPERATURE N27EA008 W HTR 6A OUTLET TEMPERATURE N27EA010 W HTR 6B OUTLET TEMPERATURE N27EA012 TDFP A TURBINE SPEED 0.020 N27EA013 TDFP B TURBINE SPEED 0.020 N27EA014 TDFP A TURB CONT VALVE POSITION 0.020 N27EA015 TDFP B TURB CONT VALVE POSITION 0.020 N27EA016 W STARTUP VALVE POSITION 0.020 N27EA017 W PUMP SUCTION HEADER PRESSURE 0.033
- e. N27EA018 LOW FEEDWATER FLOW 0.033 I N27EA019 LOW W FLOW CONTROLLER OUTPUT 0.020 Y. N27EA020 W BOOSTER PUMP A SUCTION PRESS 0.033 C N27EA021 FW BOOSTER PUMP B SUCTION PRESS 0.033
, . N27EA022 FW BOOSTER PUMP C SUCTION PRESS 0.033 y N27EA023 - W BOOSTER PUMP D SUCTION PRESS 0.033 r N27EA024 W BOOSTER PUMP A DISCH PRESS 0.033 m N27EA025 W BOOSTER PUMP B DISCH PRESS 0.033 EE N27EA026 N27EA027 W BOOSTER PUMP C DISCH PRESS FW BOOSTER PUMP D DISCH PRESS 0.033 0.033
'7 ,, e N27EA028 TDFP A SUCTION FLOW 0.033
) 473 N27EA029 TDFP B SUCTION FLOW 0.033 O N27EA030 MDFP C SUCTION FLOW 0.033 Q N27EA032 N27EA033 MDFP C DISCHARGE PRESSURE MDFP C SUCTION PRESSURE 0.033 0.033 N27EA034 TDFP A DISCHARGE PRESSURE 0.033
m_. _ . _ , - - _ _ _ _ . . _ . _ _ . - _ _ . . _ . . . _ _ __ . _ _ - . _ _ _ _ _ _ --
is 2~
ATTACHMENT H Page 13 ANALOG INPUTS ERIS SYSTEM 10/26/83 j FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC) 4 N27EA035 TDFP A SUCTION PRESSURE 0.033 N27EA036 TDFP B DISCHARGE PRESSURE 0.033 N27EA037 TDFP B SUCTION PRESSURE 0.033 N27EA040 MDFP C MOTOR CURRENT N27EA041 FEEDWATER INJECTION PRESSURE A 0.033 N27EA042 FEEDWATER INJECTION PRESSURE B 0.033 ;
N27EA043 TDFP A COUPLING BEARING VIB ATER
- . N27EA044 TDFP B COUPLING BEARING VIB ATER r
- N27EA045 TDFP A FRONT BEARING VIB ATER C N27EA046 TDFP B FRONT BEARING VIB ATER i i N27EA047 MDFP C SUCTION END BEARING VIB ATER N27EA048 MDFP C DISCH END BEARING VIB ATER i N27EA050 MDFP C FLOW CONT VALVE POSITION 0.020 i L N31EA001 MAIN TURBINE SPEED 0.020 '
. N31EA002 MAIN TURBINE TOTAL CV POSITION 0.004 0.004 :
- N32EA001 MAIN TURBINE.STOP VALVE 1 POSN j' N32EA002 MAIN TURBINE STOP VALVE 2 POSN 0.004 l N32EA003 MAIN TURBINE STOP VALVE 3 POSN 0.004 l 2
N32EA004 MAIN TURBINE STOP VALVE 4 POSN 0.004 !
- - N32EA005 MAIN TURBINE CONT VALVE 1 POSN 0.004 N32EA006 MAIN TURBIE CONT VALVE 2 POSN 0.004 i
, ' N32EA007 ' MAIN TURBINE CONT VALVE 3 POSN 0.004 l1 ..
N32EA008 MAIN TURBINE CONT VALVE 4 POSN LOAD REFERENCE 0.004 r.020 i
t N32EA009 _
1 N32EA010 MAIN TURB CONTROL VALVE DEMAND .020 L~ N32EA011 . MAIN TURBINE STEAM FLOW DEMAND 0.020 i i
N32EA012 MAIN TURBINE FLOW REFERENCE- 0.020
- N32EA013 MAIN TURBINE SPEED LOAD DEMAND A 0.020
- - N32EA014 MAIN TURBINE SPEED LOAD DEMAND B 0.020 l LN33EA001 STEAM SEAL EVAPORATOR LEVEL 0.033 *
. N33EA002 : STEAM SEAL EVAP LEVEL CONT.0UT 0.020 .
1 0.033 N33EA003 STEAM SEAL EVAP DRAIN TA E LEVEL N33EA004 :SSE DR TANK EMER LEVEL CONT OUT 0.020
. 1 N33EA005 SSE DR TAE NORM LEVEL CONT OUT 0.020 ,
N33EA006 STEAM SEAL EVAP TUBE. PRESSURE 0.033- ;
I '
'N33EA007 STEAM SEAL EVAP SEET PRESSURE 0.033 -!
'j N33EA008 STEAM SEAL EVAP PRESS' CONT OUT 0.020 ' l
! pf, N33EA009' STEAM SEAL EVAP PRESS CONT OUT 0.020- l
.nd. N33EA010: STEAM SEAL PRESSURE 0.033 W N33EA011- ST SEAL AUX'ST PRESS CONT 00T 0.033 ','
M.
N36EA001 DC HTR 4 AUX STEAM PRESSURE- 0.033
~L3 M1EA001 < GEN STATOR WINDING TEMPERATURE '
4 Myn MIEA002. ' GEN STATOR WINDING TEMPERATURE M MIEA003- . GEN STATOR WINDING TEMPERATURE ,
M1EA004 : GEN STATOR WINDING TEMPERATURE '
.~ *h:4 MIEA005 M1EA006 GEN STATOR WINDING TEMPERATURE =
GEN STATOR WINDING TEMPERATURE I O. TB M1EA007 GEN STATOR WINDING TEMPERATURE-
' ' V 42 migA008 ' GEN STATOR WINDING TEMPERATURE i
.V"$ MIEA009. > GEN STATOR WINDING TEMPERATURE.
W .M1[A010
.a ~ GEN STATOR WINDING TEMPERATURE s MIEA011
' GEN STATOR WINDING TEMPERATURE ,
t
+
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ATTACHMENT H Page 14 ANALOG INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC)
N41EA012 GEN STATOR WINDING TEMPERATURE M1EA013 GEN STATOR WINDING TEMPERATURE N41EA014 GEN STATOR WINDING TEMPERATURE M1EA015 GEN STATOR WINDING TEMPERATURE N41EA016 GEN STATOR WINDING TEMPERATURE N41EA017 GEN STATOR WINDING TEMPERATURE N41EA018 GEN STATOR WINDING TEMPERATURE N41EA019 GEN STATOR WINDING TEMPERATURE N41EA020 GEN STATOR WINDING TEMPERATURE N41EA021 GEN STATOR WINDING TEMPERATURE N41EA022 GEN STATOR WINDING TEMPERATURE N41EA023 GEN STATOR WINDING TEMPERATURE N41EA024 GEN STATOR WINDING TEMPERATURE M1EA025 GEN STATOR WINDING TEMPERATURE
- M1EA026 GEN STATOR WINDING TEMPERATURE
. M1EA027 GEN STATOR WINDING TEMPERATURE N41EA028 GEN STATOR WINDING TEMPERATURE MIEA029 GEN STATOR WINDING TEMPERATURE' MIEA030 GEN STATOR WINDING TEMPERATURE MIEA031 GEN STATOR WINDING TEMPERATURE MIEA032 GEN STATOR WINDING TEMPERATURE M1EA033 GEN STATOR WINDING TEMPERATURE MIEA034 GEN STATOR WINDING TEMPERATURE MIEA035 GEN STATOR WINDING TEMPERATURE MIEA036 GEN STATOR WINDING TEMPERATURE MIEA037 GEN STATOR WINDING TEMPERATURE.
HIEA038 GEN STATOR WINDING TEMPERATURE MIEA039 GEN STATOR WINDING TEMPERATURE HIEA040 GEN STATOR WINDING TEMPERATURE MIEA041 GEN STATOR WINDING TEMPERATURE' M1EA042 GEN STATOR WINDING TEMPERATURE
. MIEA043 GEN STATOR WINDING TEMPERATURE M1EA044 . GEN STATOR WINDING. TEMPERATURE MIEA045 GEN STATOR WINDING TEMPERATURE MIEA046- GEN STATOR WINDING TEMPERATURE M1EA047 GEN STATOR WINDING TEMPERATURE (t .
-Lfi MIEA048 MIEA049' GEN STATOR WINDING 1TMPERATURE
' GEN STATOR WINDING TEMPERATURE PO MIEA050 GEN STATOR WINDING TEMPERATURE-
-dd M1EA051 GEN STATOR WINDING TEMPERATURE-tj '
M1EA052 GEN STATOR WINDING TEMPERATURE W
M1EA053 GEN STATOR WINDING TEMPERATURE
- h4 MIEA054 . GEN STATOR WINDING TEMPERATURE vW M1EA055 GEN STATOR WINDING TEMPERATURE M N M1EA056 MIEA057 GEN STATOR WINDING TEMPERATURE GEN STATOR WINDING TEMPERATURE
& MIEA058 GEN STATOR WINDING TEMPERATURE (l.a MIEA059 GEN STATOR WINDING TEMPERATURE-vF wd. -
Miu0e0 MIEA061 GEN STATOR WImIm m PEnTURE-
~ GEN STATOR WISING TEMPERATURE MIEA062 GEN STATOR WISING TEMPERATURE:
M1EA063 GEN STATOR WINDING TEMPERATURE
_ _ - - _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ m
_ . _ - . - _ . - - _ _ _ . _ . . . - - - . - _ . ____..m . . . - - __ __-_
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- ATTACHMENT H Page 15
};
ANALOG INPUTS ERIS SYSTEM 10/26/83
[
I FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC) l- N41EA064 GEN STATOR WINDING TEMPERATURE I N41EA065 GEN STATOR WINDING TEMPERATURE i N41EA066 GEN STATOR WINDING TEMPERATURE I
j M1EA067 N41EA068 GEN STATOR WINDING TEMPERATURE GEN STATOR WINDING TEMPERATURE j
j N41EA069 GEN STATOR WINDING TEMPERATURE
! M1EA070 GEN STATOR WINDING TEMPERATURE i N41EA071 GEN STATOR WINDING TEMPERATURE ic N41EA072 GEN STATOR WINDING TEMPERATURE l
g L N41EA075 GEN STATOR COIL LIQ OUTLET TEMP l N41EA076 GEN STATOR COIL' LIQ OUTLET TEMP i i N41EA077 GEN STATOR COIL LIQ OUTLET TEMP l
- N41EA078 GEN STATOR COIL LIQ OUTLET TEMP i N41EA079 GEN STATOR COIL LIQ OUTLET TEMP i N41EA080 GEN STATOR COIL LIQ OUTLET TEMP I N41EA081 GEN STATOR COIL LIQ OUTLET TEMP ,
GEN STATOR COIL LIQ OUTLET TEMP ;
! N41EA082 r
k M1EA083' GEN STATOR COIL LIQ OUTLET TEMP D ... N41EA084 GEN STATOR COIL LIQ OUTLET TEMP ,
MIEA085 GEN STATOR COIL LIQ OUTLET TEMP ;
',./
L. - N41EA086 GEN STATOR COIL LIQ OUTLET TEMP j N41EA087 GEN STATOR COIL LIQ OUTLET TEMP <
i MIEA088- GEN STATOR COIL LIQ OUTLET TEMP i N41EA089 GEN STATOR COIL LIQ OUTLET TEMP N41EA090 GEN STATOR COIL LIQ OUTLET TEMP -!
. .N41EA091 GEN STATOR COIL LIQ OUTLET TEMP I
.- .N41EA092 GEN STATOR COIL LIQ OUTLET-TEMP j .M1EA093 GEN STATOR COIL LIQ OUTLET TEMP :
t M1EA094 GEN STATOR COIL LIQ.0UTLET TEMP M1EA095 GEN STATOR COIL LIQ OUTLET TEMP' N41EA096 GEN STATOR COIL LIQ OUTLET TEMP F
~
. M1EA097- ' GEN STATOR COIL' LIQ OUTLET TEMP 1
.N41EA098 GEN STATOR COIL LIQ OUTLET TEMP 1 b M1EA099 GEN STATOR COIL LIQ OUTLET TEMP N41EA100 GEN STATOR COIL LIQ OUTLET TEMP N41EA101 GEN STATOR COIL LIQ OUTLET TEMP- ,
MIEA102 GEN STATOR COIL LIQ OUTLET TEMP-i
- yd- MIEA103 GEN STATOR' COIL LIQ OUTLET TEMP (H ' M1EA104 GEN STATOR COIL LIQ OUTLET TEMP NO- MIEA105' . GEN STATOR COIL LIQ OUTLET TEMP - l
@ MIEA106 . GEN STATOR COIL LIQ OUTLET TEMP' 4
ti M1EA107 GEN STATOR COIL LIQ OUTLET TEMP .
,-c-'
%3 er MIEA108 M1EA109L GEN STATOR COIL LIQ OUTLET TEMP
GEN STATOR COIL LIQ OUTLET TEMP- c 1
C; W1EA110 GEN STATOR COIL LIQ OUTLET TEMP e ;L
- MIEA111! GEN STATOR. COIL LIQ OUTLET TEMP-p ;--
.e* 'A' M1EA112 MIEA113 GEN STATOR COIL LIQ OUTLET TEMP 10EN STATOR COIL LIQ OUTLET TEMP. 3 p" MitA114 GEN STATOR COIL LIQ OUTLET TEMP -
a A MIEA115 GEN STATOR COIL' LIQ OUTLET TEMP :
t
{
ATTACIMENT H Page 16 ANALOG INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC)
H1EA116 GEN STATOR COIL LIQ OUTLET TEMP N41EA117 GEN STATOR COIL LIQ OUTLET TEMP N41EA118 GEN STATOR COIL LIQ OUTLET TEMP M1EA119 GEN STATOR COIL LIQ OUTLET TEMP N41EA120 GEN STATOR COIL LIQ OUTLET TEMP M1EA121 GEN STATOR COIL LIQ OUTLET TEMP N41EA122 GEN STATOR COIL LIQ OUTLET TEMP M1EA123 GEN STATOR COIL LIQ OUTLET TEMP N41EA124 GEN STATOR COIL LIQ OUTLET TEMP N41EA125 GEN STATOR COIL LIQ OUTLET TEMP N41EA126 GEN STATOR COIL LIQ OUTLET TEMP N41EA127 GEN STATOR COIL LIQ OUTLET TEMP MIEA128 GEN STATOR COIL LIQ OUTLET TEMP M1EA129 GEN STATOR COIL LIQ OUTLET TEMP N41EA130 GEN STATOR COIL LIQ OUTLET TEMP MIEA131 GEN STATOR COIL LIQ OUTLET TEMP N41EA132 GEN STATOR COIL LIQ OUTLET TEMP MIEA133 GEN STATOR COIL LIQ OUTLET TEMP
- N41EA134- GEN STATOR COIL LIQ OUTLET TEMP M1EA135 GEN STATOR COIL LIQ OUTLET TEMP M1EA136 GEN STATOR COIL LIQ OUTLET TEMP (a M1EA137~ GEN STATOR COIL LIQ OUTLET TEMP
- M1EA138 GEN STATOR COIL LIQ OUTLET TEMP M1EA139 GEN STATOR COIL LIQ OUTLET TEMP N41EA140 GH STATOR COIL LIQ OUTLET TEMP M1EA141 GEN STATOR COIL LIQ OUTLET TEMP
' M1EA142 GEN STATOR COIL LIQ OUTLET TEMP N41EA143 GEN STATOR COIL LIQ OUTLET TEMP MIEA144 LGEN STATOR COIL LIQ OUTLET TEMP-MIEA145 GEN STATOR COIL LIQ OUTLET TEMP' N41EA146' GEN STATOR COIL LIQ.0UTLET TEMP MIEA147- GEN STATOR COIL LIQ OUTLET TEMP N41EA148 GEN STATOR COIL LIQ OUTLET TEMP
. N41EA149 - GEN STATOR COIL LIQ OUTLET TDfP 4
M1EA150 GEN STATOR COIL LIQ OUTLET TEMP
! MIEA151 GEN STATOR COIL LIQ OUTLET TEMP MIEA152- G U STATOR COIL LIQ OUTLET TEMP
+
r" M1EA153 . GEN STATOR COIL LIQ OUTLET TEMP ,
M ' M1EA154 GU STATOR COIL LIQ OUTLET TEMP MIEA155= GEN STATOR COIL LIQ OUTLET TEMP
}/(c-MIEA156- G U STATOR COIL LIQ OUTLET TEMP r
i,~ MIEA157 G H STATOR COIL LIQ OUTLET TEMP
-; V MIEA158 G U STATOR. COIL LIQ OUTLET TEMP '
.r MIEA159 G H STATOR COIL LIQ OUTLET TEMP Ti MIEA160 MIEA161 GH STATOR COIL LIQ OUTLET TEMP G H STATOR COIL LIQ OUTLET TEMPc
.t t MIEA162 GM STATOR COIL LIQ OUTLET TEMP QM
[a'
.MIEA163
. M1EA164 GEN STATOR COIL LIQ OUTLET TEMP.
0 5 STATOR COIL LIQ OUTLET TEMP n i 'MIEA165 G R STATOR COIL LIQ OUTLET TEMP
' 1"?
M1EA166' 05 STATOR COIL LIQ OUTLET TEMP M1EA167 0 5 STATOR COIL LIQ OUTLET TEMP
__.h_-._m_ -
ATTACIMENT H .Page 17 ANALOG INPUTS ERIS SYSTEM 10/26/83
.h FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC)
M1EA168 GEN STATOR COIL LIQ OWLET TEMP N41EA169 GEN STATOR COIL LIQ OUTLET TEMP M1EA170 GEN STATOR COIL LIQ OUTLET TEMP N41EA171 GEN STATOR COIL LIQ OUTLET TEMP M1EA172 GEN STATOR COIL LIQ OUTLET TEMP M1EA173 GEN STATOR COIL LIQ OUTLET TEMP M1EA174 GEN STATOR COIL LIQ OWLET TEMP N41EA175 GEN STATOR COIL LIQ OUTLET TEMP M1EA176 GEN STATOR COIL LIQ OWLET TEMP M1EA177 GEN STATOR COIL LIQ OUTLET TEMP M1EA178 ' GEN STATOR COIL LIQ OUTLET TEMP N41EA179 GEN STATOR COIL LIQ OUTLET TEMP N41EA180 ' GEN STATOR COIL LIQ OWLET TEMP M1EA181 GEN STATOR COIL LIQ OUTLET TEMP M1EA182 GEN STATOR COIL LIQ OUTLET TEMP M1EA183 GEN STATOR COIL LIQ OUTLET TEMP N41EA184 GEN STATOR COIL LIQ OWLET TEMP M1EA185 GEN STATOR COIL LIQ OUTLET TEMP
- M1EA186. GEN STATOR COIL LIQ OUTLET TEMP N41EA187 GEN STATOR COIL LIQ OUTLET TEMP M1EA188 GEN STATOR COIL LIQ OUTLET TEMP-MIEA189 GEN STATOR COIL LIQ OUTLET TEMP-M1EA190 GEN STATOR COIL LIQ OUTLET TEMP M1EA191 GEN STATOR COIL LIQ OUTLET TEMP M1EA192' GEN STATOR COIL LIQ OUTLET TEMP' HIEA193 GEN STATOR COIL LIQ OUTLET TEMP MIEA194 GEN STATOR COIL LIQ OWLET TEMP MIEA195' GEN STATOR COIL LIQ OUTLET TEMP M1EAl% GEN STATOR' COIL LIQ OUTLET TEMP M1EA197 GEN STATOR COIL LIQ OUTLET' TEMP M1EA198 GEN STATOR COIL LIQ OUTLET TEMP M1EA199 GEN STATOR COIL LIQ OUTLET TEMP M1EA200 GEN STATOR COIL LIQ OUTLET TEMP.
f M1EA201 GEN.STA1DR COIL' LIQ OUTLET TEMP MIEA202 GEN STATOR COIL LIQ OWLET TEMP .
M1EA203 GEN STATOR C0IL' LIQ'0UTLET TEMP.
d M1EA204 GEN STATOR COIL LIQ OUTLET TEMP
. M1EA207 GEN STATOR C0IL LIQ OUTLET TEMP-3- MIEA206 GEN STATOR COIL LIQ OUTLET TEMP
' , ; MIEA209 GEN STATOR C0IL-LIQ OUTLET. TEMP i
MIEA210 GEN STATOR COIL LIQ OUTLET TEMP
,; . MIEA211: GEN STATOR COIL' LIQ OWLET TEMP' 7 MIEA212- GEN STATOR COIL LIQ OUTLET TEMP
,,3 MIEA213 GEN STATOR COIL LIQ OUTLET TEMP, a ~
MIEA214~ GEN STATOR COIL LIQ OUTLET TEMP-
.^/-
(wl m J MIEA215- GEN STATOR COIL LIQ OUTLET TEMP'
- (EN STATOR COIL LIQ OUTLET TEMP.
MIEA216 MIEA217J GEN STATOR COIL LIQ OUTLET TEMP-h h $$ '
ATTACINENT H Page 18 ANALOG INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC)
N41EA220 GEN STATOR COIL LIQ OUTLET TEMP N41EA221 GEN STATOR COIL LIQ OUTLET TEMP N41EA222 GENERATOR STATOR PHASE CURRENT N41EA223 MAIN GENERATOR GROSS MWE 0.020 N43EA001 GEN STATOR CLG WATER INLET TEMP P11EA001 CONDENSATE STORAGE TANK LEVEL P20EA010 CLEARWELL LEVEL P21EA001 TWO BED TANK LEVEL P22EA001 MIX BED TANK LEVEL P33EA001 CNDS DEMIN EFTLUENT CONDUCTIVITY 0.033 P41EA001 COOLING TOWER BASIN LEVEL P42EA001 ECC HX A OUTLET FLOW P42EA002 ECC HX A OUTLET TEMPERATURE P42EA003 ECC HX B OUTLET TEMPERATURE P42EA004 ECC HX B OUTLET FLOW P43EA001 NCC SYS NON-REGEN HX OUTLET TEMP-P45EA001 ESW PUMP A DISCHARGE TEMPERATURE P45EA002 ESW FLOW FROM ECC HX A P45EA003 ESW FLOW FROM DIESEL GEN HX A P45EA004 ESW FLOW FROM HPCS DIESEL GEN HX P45EA005 ESW PUMP B DISCHARGE TEMPERATURE P45EA006 ESW FLOW FROM DIESEL GEN HX B P45EA007 ESW FLOW FROM ECC HX B P51EA001 SERVICE AIR HEADER PRESSURE
-PS2EA001 INSTRUMENT AIR HEADER PRESSURE P57EA001 ADS AIR SUPPLY PRESSURE A P57EA002 ADS AIR SUPPLY PRESSURE B P61EA001 DC HTR 4 AUX ST PRESS CONT OW 0.020
-R22EA001 BUS TH-21 VOLTAGE' R22EA002 BUS TH-1 VOLTAGE R22EA004 BUS EH-11 VOLTAGE 0.011 R22EA005 DIV 1 DIESEL GENERATOR VOLTAGE R22EA007 BUS EH-12 VOLTAGE 0.011 R22EA008 DIY'2 DIESEL GENERATOR VOLTAGE R22EA009 BUS EH-13 VOLTAGE 0.011
,.m p ?, R22EA010 DIV 3 DIESEL GENERATOR VOLTAGE v y!, R22EA011 BUS TL-21 VOLTAGE-U3 R22EA012- : BUS L-10 VOLTAGE
- d .. R22EA013 100-PY-B TRANSFORMER VOLTAGE
'MO i.
'R22EA014 R22EA015 BUS L-11 VOLTAGE BUS L12 VOLTAGE LJC R23EA001 . BUS EF-1-E1 VOLTAGE 0.011 M R23EA002 BUS EF-1A VOLTAGE 0.011 R23EA003~ BUS EF-18 VOLTAGE' O.011
- eM' R23EA004 BUS EF-1C VOLTAGE. 0.011 c7 R23EA005 BUS EF-ID -VOLTAGE .
0.011
.. . gf. .
- R W 001 BATTERY E-1A CURRENT'
- rj .R42EA002 CHARGER EFD-1A OWPUT VOLTAGE
. RW003 CHARGER EFD-12A OWPW VOLTAGE
+4 R42EA004 DC BUS ED-1A VOLTAGE R42EA005 ' BATTERY E-1A VOLTAGE 1R42EA006 BATTERY E-1B CURRENT
ATTACHMENT H Page 19
-r ANALOG INPUTS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION SCAN INTERVAL (SEC)
R42EA007 CHARGER EFD-1B OUTPUT VOLTAGE R42EA008 CHARGER EFD-12B OUTPUT VOLTAGE R42EA009 DC BUS ED-1B VOLTAGE R42EA010 BATTERY E-1B VOLTAGE R42EA011 CHARGER EFD-12C OUTPUT VOLTAGE R42EA012 DC BUS D-1A VOLTAGE R42EA013 DC BUS D-1B VOLTAGE R42EA014 DC BUS ED-1C VOLTAGE R42EA015 CHARGER EFD-1C OLITPUT VOLTAGE R42EA016 BATTERY E-1C CURRE}fT R42EA017 BATTERY E-1C VOLTAGE R42EA504 DC BUS ED-2A VOLTAGE R42EA509 DC BUS ED-2B VOLTAGE R42EA513 DC BUS D-2B VOLTAGE R42EA514 DC BUS ED-2C VOLTAGE I
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ATTACHMENT I Page 1 CONTROL ROD POSITIONS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION C11EJ001 CONTROL ROD 22-03 C11EJ002 CONTROL ROD 26-03 C11EJ003 COUROL ROD 30-03 C11EJ004 CONTROL ROD 34-03 C11EJ005 CONTROL ROD 38-03 C11EJ006 CONTROL ROD 14-07 C11EJ007 CONTROL ROD 18-07 C11EJ008 CONTROL ROD 22-07 C11EJ009 CONTROL ROD 26-07 C11EJ010 CONTROL ROD 30-07 C11EJ011' CONTROL ROD 34-07 C11EJ012 CONTROL ROD 38-07 C11EJ013 CONTROL ROD 42-07 C11EJ014 CONTROL ROD 46-07 C11EJ015 CONTROL ROD 10-11 C11EJ016 CONTROL ROD 14-11 C11EJ017- COEROL ROD 18-11 C11EJ018 -CONTROL ROD 22-11 C11EJ019 CONTROL ROD 26-11 C11EJ020 ' CONTROL ROD 30-11 C11EJ021' CONTROL ROD'34-11
- C11EJ022- CONTROL ROD 38-11 C11EJ023- CONTROL ROD 42-11'
' >~ C11EJ024- LCONTROL ROD-46-11 C11EJ025 CONTROL ROD 50-11 C11EJ026 CONTROL ROD 06-15 C11EJ027 .COUROL ROD 10-15
- C11EJ028 . CONTROL ROD _14-15 C11EJ029' CONTROL ROD 18-15 C11EJ030- CONTROL' ROD 22-15 C11EJ031 COEROL ROD 26-15 C11EJ032 - COEROL' ROD 30 C11EJ033 CONTROL ROD 34-15
'C11EJ034 CONTROL ROD 38 C11EJ035 CONTROL ROD 42-15 C11EJ036- ~ CONTROL ROD 46-15 C11EJ037 CONTROL' ROD 50 C11EJ038 CONTROL-ROD 54-15 C11EJ039 CONTROL ROD 06-19 ,
C11EJ040i CONTROL ROD 10-19
% C11EJ041 C11EJ042 CONTROL ROD'14-19 CONTROL ROD 18-19 A
C11EJ043 CONTROL ROD 22-19~
- >$ C11EJ044 CONTROL' ROD 26-19 C11EJ045 CONTROL ROD 30-19 W -C11EJ046 COUROL ROD 34-19
' > C11EJ047 LCONTROL' ROD 38-19 4 C11EJ048 CONTROL ROD 42-19i 7
Y-C11EJ049; CONTROL ROD 46-19
<. . C11EJ050 CONTROL ROD 50 c9 C11EJ051 CONTROL ROD 54-19 M ".h . 'C11EJ052 ' CONTROL-ROD 02-23 C11EJ053 ' CONTROL ROD 06-23
W ATTACHMENT I Page 2
( COUR0L ROD POSITIONS ERIS SYSTEM 10/26/83
.MJNCTION ID DESCRIPTION C11EJ054 CONTROL ROD 10-23 C11EJ055 CONTROL ROD 14-23 C11EJ056 CONTROL ROD 18-23
~C11EJ057 CONTROL ROD 22-23 C11EJ058 CONTROL ROD 26-23 C11EJ059 CONTROL ROD 30-23 C11EJ060 COFIPOL .P.0D 34-23
- C11EJ061 CONTROL RCD 38-23 C11EJC62 CONTROL ROD 42-23 C11EJ063 C0!! TROL ROD 46-23
- C11EJ064 CONTROL ROD 50-23 C11EJ065 CONTROL ROD 54-23
-C11EJ066 COEROL ROD 58-23 C11EJ067 '
CONTROL ROD 02-27 C11EJ068 CONTROL ROD 06-27 C11EJ069, CONTROL ROD 10-27 C11EJ070 CCNTROL ROD 14-27 C11EJ071- ' CONTROL ROD 18-27 -
C11EJ072 COWROL ROD 22-27 ,
C11EJ073 .-CONTROL ROD 26-27 C11EJ074~ CONTROL ROD 30-27
' (]V - C11EJ075 C11EJ076 ,
CONTROL ROD 34-27 CONTROL ROD 38-27 C11EJ077 ' CONTROL ROD 42 C11EJ078 CONTROL ROD 46-27 C11EJ079 CONTROL ROD.50-27 C11EJ080 CONTROL" ROD 54-27 C11EJ081 CONTROL ROD 58 _ C11EJ082 CONTROL ROD 02-31 C11EJ083 CONTROL FOU 06-31 C11EJ084 CONJROL NOD 10-31 C11EJ085 . CONTROL ROD 14-31 C11EJ086 CONTROL ROD 18-31 J. C11EJ087 CONTROL ROD 22-31 C11EJ088 CONTROL ROD 26-31 C11EJ089 CONTROL ROD 30-31 C11EJO90 CONTROL J.0D 34-31 C11EJO91 CONTROL. RCD 38-31 4 -C11EJO92 CONTROL-ROD 42-31 r .C11EJO93 CONTROL ROD 46-31
, C11EJO94 CONT.90L-ROD 50-31 C11EJO95 CONTROL ROD 54-31 , -
C11EJO96. CONTROL ROD 58-31, C11EJO97- -CONTROL ROD 02-35 -a
, C11EJO98 CONTROL ROD 06-35 4 C11EJO99 CONTROL; ROD 10-35
. C11EJ100 CONTROL _ ROD 14-35 N. "
T-i ., C11EJ101- CONTROL ROD 18-35 "i .C11EJ102-
"C11EJ103 CONTROL ROD _22-35 CONTROL ROD .IS-35 FC11EJ104 C0hTROL ROD %-35
- C11EJ105 CONTROLROD$4-35 2
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ATTACHMENT I Page 3 CONTROL ROD POSITIONS ERIS SYSTEM 10/26/83 FUNCTION ID DESCRIPTION C11EJ106 COUROL ROD 38-35 l C11EJ107 COEROL ROD 42-35 C11EJ108 CONTROL ROD 46 C11EJ109 CONTROL ROD 50-35 C11EJ110 CONTROL ROD 54-35 C11EJ111 CONTROL ROD 58-35 C11EJ112 CONTROL ROD 02-39 C11EJ113 CONTROL ROD 06-39 C11EJ114 CONTROL ROD 10-39 C11EJ115 CONTROL ROD 14-39 C11EJ116 CONTROL ROD 18-39 C11EJ117 CONTROL ROD 22-39 C11EJ118- CONTROL ROD 26-39 C11EJ119 CONTROL ROD 30-39 C11EJ120 CONTROL ROD 34-39 C11EJ121 CONTROL-ROD 38-39 C11EJ122 CONTROL ROD 42-39 C11EJ123- COUROL-ROD 46-39 C11EJ124 CONTROL ROD 50-39
'C11EJ125 CONTROL ROD 54-39
. . - - C11EJ126 CO EROL ROD 58-39
- C11EJ127 -
CONTROL ROD 0643 -
~ :- C11EJ128 CONTROL ROD 10-43 C11EJ129 CONTROL ROD 14-43 C11EJ130. CONTROL ~ RCD 18-43 C11EJ131 - CONTROL. RCD 2243 C11EJ132- COUROL ROD 2643 C11EJ133 COUROL ROD 3043 C11EJ134 'CO EROL ROD 34-43 C11EJ135 CONTROL' ROD 3843 C11EJ136 CONTROL ROD .4243'-
C11EJ137- 'COUROL ROD 46-43 C11EJ138 CONTROL RCD 50-43 C11EJ139 LCONTROL ROD 5443 C11EJ140- . COUROL ROD 0647 '
C11EJ141' CONTROL ROD 1047
.C11EJ142 CONTROL ROD 1447.
C11EJ143- COUR0L RCD 1847
' .A*
C11EJ144 C11EJ145 CONTROL ROD 2247.
CONTROL R0D 2647 C11EJ146' CONTROL RCD 3047-:
' ;gg C11EJ147 CONTROL RCD 34-47J
'C11EJ148. CONTROL ROD 3847:
g@QiN T . .C11EJ149 CONTROL _ ROD 4247 C11EJ150 COUROL RCD 4647 Q' %g % C11EJ151 COERCL ROD. 5047.-
~-
- C11EJ152 CONTROL RCD 5447 A C11EJ153 CONTROL' ROD 10-51L
'Cs] V[M* ,C11EJ154 -
COUR0L RCD 14-51
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C11EJ155 C11EJ156 COU ROL ROD 18-51.
CONTROL ROD 22-51 C11EJ157. CO U ROL RCD 26 ' "
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ATTACliMENT I Page 4 0 CONTROL ROD POSITIONS ERIS SYSTEM 10/26/83 I' FUNCTION ID DESCRIPTION
!~
C11EJ158 CONTROL ROD 30-51 C11EJ159 CONTROL ROD 34-51 C11EJ160 CONTROL ROD 38-51 C11EJ161 CCHROL ROD 42-51 C11EJ162 CO'47ROL ROD 46-51 C11EJ163 CONTROL ROD 50-51 C11EJ164 CONTROL ROD 14-55 C11EJ165 CONTROL ROD 18-55 C11EJ166 CONTROL ROD 22-55, C11EJ167 CONTROL ROD 26 C11EJ168 CONTROL ROD 30-55 C11EJ169 CONTROL ROD 34-55
C11EJ170 CONTROL ROD 38-55 C11EJ171 CONTROL ROD 42-55 C11EJ172 CONTROL ROD 46-55 C11EJ173 CONTROL ROD 22-59 C11EJ174 CONTROL ROD 26-59 C11EJ175 CONTROL ROD 30-59 C11EJ176 CONTROL ROD 34-59 C11EJ177 . CONTROLt0D 38-59 6 ,
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