ML20212M943

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Rev 0 to MR-FC-84-203, Final Design Package ATWS Rule Mods. W/54 Oversize Drawings
ML20212M943
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 10/25/1986
From: Miller S
OMAHA PUBLIC POWER DISTRICT
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ML20212M918 List: ... further results
References
RTR-REGGD-01.097, RTR-REGGD-1.097 MR-FC-84-203, MR-FC-84-203-R, MR-FC-84-203-R00, NUDOCS 8703120268
Download: ML20212M943 (135)
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r MR-FC-84-203 FINAL DESIGN DESCRIPTION TABLE OF CONTENTS EAG1 1.0 Design Basis 1.1 Statement of Problem 5 l 1.2 Functional Requirements 6 1.3 Requirements for the Diverse Scram System 1.3.1 Codes, Standards, and Regulatory Requirements 7 1.3.2 USAR Requirements 10 1.3.3 Environmental Qualification 11 1.3.4 Seismic Qualification 12 O ' C/ 1.3.5 Regulatory Guido 1.97 Requirements 13 1.4 System Response Time 14 l l 1.5 Technical Specification Requirements 14 1.6 Diversity 14 1.7 Licensing Commitments 14 2.0 Technical Description 2.1 Summary 15 2.2 Reactor Coolant System Pressure Octection 15 l 2.3 Pressure Signal Processing 16 l 2.4 Overpressure Detection 17 l 2 O Rev. O 10/25/86 v

MR-FC 84-203 FINAL DESIGN DESCRIPTION un 2.5 Initiation of Reactor Trip 18 2.6 Reactor Trip 19 l 2.7 Diverse Scram System Setpoints 19 i i l 2.8 Plant Computer Interface with DSS 20 1 2.9 Electrical Equipment Specifications 20 l 1 3.0 Design Analysis I 3.1 Regulatory Guidance Comparison 21 l 3.2.1 Power Supply 29 3.2.2 Separation Criteria 30 1 i j 3.2.3 Regulatory Guide 1.97 31 l Table ! Comparison of NRC Guidance for DSS and Fort Calhoun 23 DSS Design 3.2 Component Level Comparison of DSS and RTS 29 [ Table !! Component Comparison between Olverse Scram System and 32 l Reactor Protection System i 3.3 System Response Time 37 3.4 Impact of DSS on Existing Systems f 3.4.1 Fire Protection Review 37 l j 3.4.2 Environmental Qualification 38 3.4.3 Seismic Analysis 38 3.4.4 Electrical System Analysis 38 l 3.4.5 Iluman factors Review 39 3.4.6 Security Review 39 1 3 !lQ Rev. 0 10/25/86

MR FC 84-203 FINAL DESIGN DESCRIPT!0N' O eau 3.4.7 Materials Compatibility 39 3.4.8 ALARA 39 4.0 Safety Analysis 5.0 Plant Document Update 6.0 Work Outline 6.1 Installation 6.2. Testing Attachments A. Drawing List B. Work Order C. Material List D. Purchase Orders E. Material Specification F. Regulatory Guide 1.97 Submittal 4 Rev. 0 10/25/86

~MR FC-84 203 FINAL DESIGN DESCRIPTION O O 1.0 DESIGN BASIS 1.1 STATEMENT OF PROBLEM The modifications described in this Design Package are being implemented to comply with the requirements of 10CFR50.62. From 10CFR50.62: "For purposes of this section " Anticipated Transient Without Scram" (ATWS) means an anticipated operational occurrence as defined in Appendix A followed by the failure of the reactor trip portion of the Protection System... Each pressurized water reactor must have equipment from sensor output to final actuation device, that is diverse from the Reactor Trip System, to automatically initiate the Auxiliary (or emergency) Feedwater System and initiate a turbine trip under conditions indicative of an ATWS. This equipment must be designed to perform its function in a reliable manner and be independent (from sensor output to the final actuation device)... from the existing Reactor Trip System. Each reactor manufactured by Combustion Engineering must have a Diverse Scram O System from the sensor output to interruption of power to the control rods. This Scram System must be designed to perform its function in a reliable manner and be independent from tae existing Reactor Trip System (from sensor output to interruption of power to r the control rods)." The Auxiliary feedwater Actuation System has been installed and sufficient diversity exists between this system and the Reactor Protection System to satisfy the requirements of 10CFR50.62. The Turbine Trip System is initiated when power is interrupted to the clutch power supplies. A Olverse Scram System operates to interrupt power to the clutch power supplies. Since the Diverse Scram System is to initiate a reactor trip upon detection of conditions indicative of i an A1WS event, it will automatically initiate a turbine trip under these sarre conditions. The Turbine Trip System, by virtue of its desiga, will require no modification to comply with the rule. A Olverse Scram System (055) will need to be added to meet the requirements of 10CFR50.62. The DSS needs to be able to perform its function in a reliable manner and be Independent from the RPS. Equipment diver:,i ty to the extent reasonable and practicable to minimize the potential for common cause failures between the two i systems is required from the sensors up to and including the components used to interrupt rod drive clutch power. j Rev. 0 10/25/06 i i t h

MR FC-84 203 FINAL DESIGft DESCRIPTI0ft 4 1 'V 1.2 FUtiCT10flAL REQUIREMErlTS The Diverse Scram System augments the Reactor Trip System. The DSS uses components that are diverse, independent, and separate from the Reactor Trip System to initiate a reactor trip for anticipated operational occurrences which result in an overpressurization of the Reactor Coolant System. The DSS introduces diversity into the Reactor Trip System, thereby reducing the probability of a Reactor Coolant System overpressurization ATWS event. The DSS assures that an ATWS will not cause the stress in the Reactor Coolant System components to exceed ASME Level C stresses. Tho 055 must be designed to initiate a reactor trip for all Anticipated Operational Occurrences (A00's) with a concurrent failure of the RTS to trip the reactor which cause an overpressurization of the Reactor Coolant System. These increasing pressure A00's include the following events: Zero Power Control Element Assembly (CEA) Withdrawal p Loss of Reactor Ccolant System (RCS) flow (complete or partial) v Loss of load (completo or partial) Loss of main feedwater (completo or partial) Uncontrolled boron dilution Loss of offsito power Asymmetric steam generator pressure the limiting ATWS events are typified by a rapid Reactor Coolant System heatup and pressurization to abovo 3200 PS!A before the moderator reactivity feedback substantially reduces reactor pcwor. This type of event is classified as a severo ATWS event. The initiation of a Reactor Scram by a DSS must be accomplished by utilizing system parameters which are indicativo of ATWS ovents. Combustion Enginocring has performod analysos and has determined that either high pressurizar I pressure, high pressurizer level, or low steam generator water levol would provido adequato indication. Tho DSS automatically initiates a reactor scram under conditions indicativo of an ATWS. The implementation of the DSS reduces the probability of coro damage and release of fission products to the I environs duo to an ATWS. The existing RTS also providos the low steam G Rev. 0 10/25/86

MR-FC-84-203 FINAL DESIGN DESCRIPTION l l generator water level, asymmetric steam generator, and high pressurizer pressure trips. The DSS provides added assurance of tripping the reactor for those events listed above. 1.3 REQUIREMENTS FOR TiiE DIVERSE SCRAM SYSTEM 1.3.1 Codos, Standards, and Regulatory Requirements The NRC has issued guidance regarding 10CFR50.62 system and equipment l specifications (49FR26043,26044). The guidance is not a Regulatory l Requirement. In speci fying design requirements for the Fort Calhoun l

DSS, however, the NRC's equipment guidanco is treated as a set of requirements and, thereforo constitutes a significant portion of the design basis for the DSS.

The NRC Guidance is presented in this package in Tabic 1. The DSS is not required to be safety related, but due to the fact that I the system has the potential for causing a reactor trip, the need for system reliability, and for convenience in locating equipment, the system will be purchased and installed as a Class IE, CQE System. In instances where existing support systems such as the DC Distribution

System, instrument buses, cable tray system and existing panels do not conform to the latest codes and standards, the original plant design criteria will be followed, l

To assure that the DSS does not degrado other existing safety systems, the Regulatory Requirements and industry codes and standards portaining to protection systems, instrument tubing applications, and Class IE electrical systems will also be used as design bases for the DSS. The applicable codes, standards, and associated Regulatory Guidos ar.. as follows: Regulatory Guide Physical Independence of Electrical Systems 1.75, Rev. 2 IEEE STD 304-1974 Criteria for Independence of Class IE Equipment and Circuits IEEE STO 323 1974 Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations 1 Regulatory Guido Qualification of Class IE Equipment for Nuclear 1.89 Power Plants OO 7 Rev. 0 10/25/86

i NR-FC-84-203 FINAL DESIGN DESCRIPTION I O i IEEE STD 344-1975 hecevaended Practices for Seismic Qualification of Class IE Equipment for Nuclear Power ( Gen: rating Stations Regulatory Guide Seismic Qualification of Electrical Equipment 1.100 for Nuclear Power Plants Regulatory Guide Instrumentation for Light Water Cooled Nuclear 1.97, Rev. 2 Power Plants to Assess Plant and Environs Conditions During and following an Accident i ASME Section !!, Ferrous Material Par.tA(19831985) ASME Section II, Welding Rods, Electrodes, & Filler Material PartC(19831985) A ASME Section III, General Requirements U NCA(19831985) ASME Section !!!, Nuclear Power Plant Components, Class 2 NC(1983-1985) ASME Section V Non Destructive Examination I (19831985) ASME Section IX Welding & Brazing Qualifications (19831985) l HSSSP61(1985) Pressure Testing of Steel Valves ANSIB16.11(1980) Forged Steel Fittings, Socket Welding and Threaded ANSIB16.34(1981) Valves Flanged and Buttwelding Ends l ANSIN45.2.1(1980) Cleaning of Fluid Systems and Components during Construction Phase of Nuclear Power Plants ANSIN45.2.2(1978) Packaging, Shipping, Repairing,

Storage, and i

llandling of Items for Nuclear Power Plants t 8 O Rev. 0 10/25/86

MR-FC 84 203 L FINAL DESIGN DESCRIPTION q I l l + I 10CFR21 Reporting of Defects and Noncompliances i 10CFR50.49 Environmental Qualification of Electric Equipment important to Safety for Nuclear Power Plants 10CFR50.59 Changes Tests and Experiments i 10CFR50.62 Requirements for Reduction of Risk 'from Anticipated Transients Without Events for Light Water Cooled Nuclear (ATWS) Scram Power Plants 10CFR50.71 Maintenance of Records, Making of Reports ) 10CFR50 Appendix 8 Quality Assurance Criteria for Nuclear Power i Plants and fuel Reprocessing Plants j Other codes and standards which will be used as guidance are as l l follows: [ l IEEE STD 603 1980 Criteria for Safety Systems for Nuclear Power h Generating Stations f i IEEE STD 379 1977 Standard Application of the Single Failure j Criterton to Nuclear Power Generating Station I Class IE Systems [ j i j IEEE STD 338 1977 Criteria for the Periodic Testing of Nuclear Power Generating Station Safety Systems Reg. Guido 1,53 Application of the Single Failure Criterion to Nuclear Power Plant Protection Systems. Reg. Guido 1.62 Manual Initiation of Protective Actions. Reg. Guide 1.47 Bypassed and Inoperable Status Indication for i Nuclear Power Plant Safety Systems ISA567.02(1980) Nuclear Safety Related Instrunknt Sensing Line i Piping and Tubing Standard for use in Nuclear l j Power Plants 9 l

A Rev. 0 i

{ U 10/25/86 1 ~

MR-FC-84-203 FINAL DESIGN DESCRIPTION j NUREG 0460 Anticipated Transients Without Scram for Light Water Reactors. NUREG 0700 Guidelines for Control Room Design Review. 10CFRSO Appendix R Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979 IEEE STD 279 1971 Criteria for Protection Systems for Nuclear Power Generating Stations 1.3.2 USAR Requirements Section 7.2 of the USAR provides the design basis for the Reactor Protection System. These requirements are in accordance with the codes and standards listed in Section 1.3.1 and, in some cases, are more rostrictivo. To maintain the reliability of the 05S and prevent the degradation of existing plant safety systems, the following bases have pd been selected as applicable to the 055. It should be noted that some bases listed here are not listed in the USAR. These havo been included as added requirements for tho OSS which may not necessarily be imposed upon the Reactor Protection System, a. Instrumentation that conforms to the provisions of the IEEE Standard for Nuclear Power Plant Protectivo Systems, i b. No single component failuro can provent the safety action. c. Four independent measurement channels complete with sensors, sensor power supply units, amplifiers, and bistables are provided for the actuation paramotor. d. The channels are provided with a high degree of independence by separato connection of the sensors to the process system and of the channels to instrument power supply busos. Separate raceways are used to segregato cablo systems. I o. The four measurement channels provide trip signals to in<fependent I trip paths, f. A trip signal from any two out of four protectivo channels causes a reactor trip. l 10 ! O' Rov. 0 L 10/25/86 S

MR-FC-84-203 FINAL DESIG;l DESCRIPTION p , () g. The system A C power is supplied from separate instrument buses. h. Loss of power supply for the channel logic initiates a channel trip. 1. The system can be tested with the reactor in operation or shutdown. J. Provisions are made for manual bypass of individual channels. Indication shall be continuously and automatically indicated in the control room when a channel is in bypass. k. Once initiated, the protective action at the system level shall go to completion. Return to operation should require deliberate operator action. l l

1.. The 055 shall provide the operator with accurate, complete, and l

timely information pertinent to its own status, m. The system shall assume a two out of-three logic when a channel is deliberately placed in bypass, n. Provisions are mada at the channel level for trip and bypass of individual channels. o. Hatrices may be tripped or bypassed without the installation of l electrical jumpers. 1.3.3 Environmental Qualification l in general, the equipment to be installed for this modification can be classified into two distinct groups; equipment located insido reactor containment and equipment located in the mild environments of the Auxiliary Building. l 1.3.3.1 Equipment Inside Reactor Containment As specified in Regulatory Guide 1.97, the pressure transmitters,

cables, and electrical penetration food througis associated with the pressure indicators need to meet the established Electrical Equipment Qualification Standards.

Service conditions for this equipment from Specification GSEE 0803 are as follows: 11 Rev. 0 10/25/86 l

MR-FC-84-203 FINAL DESIGN DESCRIPTION NORMAL SERVICE CONDITIONS Temperature 40*F to 122*F llumidity 15 to 100% Radiation 1 R/i1R Pressure Atmospheric (Subject to 60 PSIG Test Every 3 Years) ACCIDENT SERVICE CONDITIONS Temperature & Pressure As Shown in Figure 1 of GSEE-0803 Integrated Radiation Dose Expected Dose for Life of Plant 1 R/ R/40 Years Accident Dose Gamma Radiation 2x10 Rads Accident Dose Beta Radiation 2x10 Rads Doric Acid Spray 2500 PPM Bcron Chemical Spray Buffered with Sodium fN llydroxide for a d pil of 9.0 at 0.6 GPM Per Square Foot 1.3.3.2 Equipment in Hild Environment Electrical equipment installed for the DSS, with the exception of the transmitters and associated cabling, shall be qualified for operation within the following limits as stated in specification ETS 001: NORMAL SERVICE CONDITIONS Temperature 40'F to 122*F llumidity 15 tog 5% Radiation 10 Rads Pressure Atmospheric 1.3.4 Seismic Qualifications Pressure transmitters, tubing, valve manifolds, and electrical conduit are to be installed to meet seismic requirements. The electrical components are to be purchased with seismic qualification as a requirement, instrument racks and panels which will be modified or loading increased by this modification are to be analyzed. This analysis will be performed so that it can be verifi " that seismic cualification of existing equisment will not be signif aantly degraded O cue to the alterations made by tils modification. U 12 Rev. 0 10/25/86

MR-FC-84-203 FINAL DESIGN DESCRIPTION ll N Appendix F of the USAR, Classification of Structures and Equipment and Seismic Criteria, gives the required response spectra for various locations at Fort Calhoun. _ For the DSS, the areas of interest are Mass l 4 (Auxiliary Building) and Mass 5 (Mat and Internal Masses of the Containment Structure). Response spectra for operating and design basis earthquakes are provided in Appendix F. The curves which will be used for the DSS (unless noted otherwise on individual purchase orders) are presented in Figures F-12, 13, 15, 16, 22 and 24 of Appendix F. 1.3.5 Regulatory Guide 1.97 Requirements Regulatory Guide 1.97, Revision 2 (Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident) requires that Reactor Coolant System pressure indication is to be provided in the Control. Room for a pressure range in accordance with the pressure anticipated for an ATWS event. Existing instrumentation measures Reactor Coolant System pressure from 0-2500 PSIA. The maximum expected pressure from an ATWS event with a DSS installed is 2600 PSIA. To comply with Regulatory Guide 1.97, at least two pressure indicators which envelope the 2600 PSIA range need to be installed. Regulatory Guide 1.97 recommends that CE plants install instrumentation to monitor primary pressure up to 4000 PSIG. OPPD Licensing has obtained approval from the NRC (Docket #50-2856/18/86) to install instrumentation with a range in accordance with the resolution of the ATWS issue if pressures are found to exceed those currently presented in the USAR. The equipment necessary to support the requirements of Reg. Guide 1.97 is classified as Category I equipment by that document. Category I equipment is required to meet the following requirements: 1. Environmental Qualification - 10CFR50.49 2. Seismic Qualification Reg. Guide 1.100 or Original Plant Construction 3. Redundancy Reg. Guide 1.75 (Two Channels) 4. Power Source - Class IE Source 5. Availability - Technical Specifications 6. Quality Assurance - District QA Plan 7. Display Continuous 8. Recording - ERF Computer 13 Rev. 0 10/25/86

MR-FC-84-203 FINAL DESIGN DESCRIPTION Il v 1.4 SYSTEM RESPONSE TIME To assure that the ASME Level C stress limits for the Reactor Coolant System piping are not challenged, Combustion Engineering has established a OSS response time requirement. The Functional Design Specification for the Diverse Scram System (CE0G Task 494) defines and establishes an overall system response time. System response time, from the instant of detection of high pressurizer pressure until the interruption of power to the clutch power supplies, shall be less than 2 seconds. 1.5 TECHNICAL SPECIFICATION REQUIREMENTS Test, maintenance, and inoperable bypass conditions for the DSS will be subject to the same requirements as those listed in Technical Specifications, Section 2.15 for "High Pressurizer Pressure." If one channel becomes inoperable, that channel may be bypassed for 48 hours from time of discovery of loss of operability. If not returned to operable status within this time frame, the channen must be placed in the tripped condition. If two channels become inoperable, one A inoperable channel must be placed in the tripped condition within one U hour from the time of discovery of loss of operability. The remaining channel may be bypassed for 48 hours, and if an inoperable channel is not returned to operable status within this time frame, a unit shutdown must be initiated. 1.6 DIVERSITY Equipment diversity to the extent reasonable and practicable to minimize the potential for common cause failures is required from the sensors up to and including the components used to interrupt power to the clutch power supplies. Olversity between the DSS and the RPS will be achieved based upon employing different operating principles (e.g., energize-to-actuate vs. deenergize-to-actuate) and different hardware (e.g., Foxboro vs. General Atomic) wherever feasible. 1.7 LICENSING COMMITMENTS As stated in 10CFR50.62, the final implementation of the modifications associated with the rule needs to be accomplished no later than the second refueling outage after July 26, 1984 unless suitable justification is provided. For fort Calhoun a commitment has been made (LAD #840345) to complete implementation during the 1987 refueling outage. 14 Rev. 0 10/25/86

=- MR-FC-84-203 FINAL DESIGN DESCRIPTION Licensing Action Document #850143 has been prepared ~ to track the Regulatory Guide 1.97 commitment protion of this modification. This document requires that construction be implemented during the 1987 refueling outage. 2.0 TECHNICAL DESCRIPTION 2.1

SUMMARY

The Diverse Scram System is composed of four independent instrumcnt loops, each having a fressure transmitter and a bistable trip unit. The bistable trip unit output contacts are configured into two independent two-out-of-four logic matrices. Each matrix has a lock out rel.ay which, whe energized, deenergizes the undervoltage trip coils on the reactor trip breakers. 2.2 REACTOR COOLANT SYSTEM PRESSURE DETECTION ( The DSS is initiated upon detection of high pressurizer pressure. New pressure sensors and transmitters, independent from the Reactor Protection System but sharing the save instrument sensing lines are 4 installed for the DSS. The pressure transmitters produce a 4-20 MA output from a 24 VDC instrument loop which derives its power from the safety related Auxiliary Feedwater Actuation System instrument cabinets (Al-196,

197, 198, and 199). These cabinets are supplied with power from the plant's safety-related inverters.

4 The pressure transmitters are Rosemount Model 1154 transmitters. The transmitters and associated instrument tubing are seismically installed l in the reactor containment. The instrument tubing and vent / drain valve manifolds for the transmitters meet the criteria for ASME III Class II i piping. A more detailed description of the :nanifolds is provided in " Specification for 3-Valve Manifolds" which has been prepared for this i modification. The transmitters are located on seismic instrumentation j racks (AI-127A,B,C,D) which are outside the shield wall that surrounds the primary system on the intermediate level (elev. 1013') inside containment. The instrument tubing for the transmitters tees into the instrument tubing for the existing PT-102 Series transmitters. Tubing runs are i field routed and seismically supported. i 15 i Rev. 0 ] 10/25/86

MR-FC-84-203 FINAL DESIGN DESCRIPTION ,l 1 -Each transmitter has a specially designed conduit seal attached to the. i transmitter housing which prevents moisture from entering the transmitter.- Two.22 gauge wires penetrate the seals and are spliced to i a shielded instrument cable (W57) which carries the.4-20mA output F signal to the instrument cabinets. The instrument cables link up to [ environmentally qualified containment penetration assemblies located in canisters All, A4, 05, and DIO. All cable splices are qualified splice connections in accordance with procedure GSEE-0512. All butt-splice joints are soldered. 2.3 PRESSURE SIGNAL PROCESSING The signals generated from the pressure transmitters are converted to voltage signals and compared against a predetermined setpoint in the bistable trip unit. The bistable trip units are located in the Auxiliary ~Feedwater Actuation System cabinets and are comprised of l Foxboro Spec 200 modules..The modules used for. the DSS are: current-i to-voltage converters, bistables (trip and pretrip), and contact output isolators. The bistable trip unit has provisions for bypass and test to allow the instrument loop to be tested at power. The current-to-voltage converter module takes the 4-20 mA signal from i; the transmitter and converts it to a 0-10 volt signal. The 0-10 volt l signal is then used as the input to the alarm module. Channels A and B of the DSS also use the 0-10 volt signal to provide Control Room indication for Reactor Coolant System pressure for the range of l 1900-2900 PSIA. The information is displayed on pressure indicators (PI-120A, PI-1208) located on AI-66A and AI-668. l A key-lock switch with 3 positions is provided (NORMAL, TRIP, BYPASS) l for each channel to facilitate the TRIP, TEST, and BYPASS features. l The channel key-lock switches are located in instrument cabinets i AI-196,

197, 198, and 199. All of the key-locks are keyed alike and j

only one key is available for the system. Once inserted, the key may be removed from the NORMAL position only. This assures that only one l channel may be placed in the BYPASS mode at any given time. When i

bypassed, the contact output circuits are opened and the output of the bypassed channel is effectively blocked.

This permits testing and calibration operations while the plant is on-line. When placed in the TRIP position, the key-lock switch interrupts power to the channel's output relays. The output contacts of the relay close to trip the t channel. i 16 i Rev. 0 1 10/25/86 a 1 .m

MR-FC-84-203 FINAL DESIGN DESCRIPTION

O Alarms are generated to indicate PRETRIP, TRIP, DSS IN TEST, and DSS IN BYPASS conditions.

The PRETRIP and TRIP alarms are generated whenever l the predetermined setpoints are. reached. When a setpoint level is detected in the alarm card, the output contacts of this card energize a relay on the contact output isolator card to actuate the annunciator in the main Control Room. The condition of DSS IN BYPASS is annunciated whenever one of the channel key-lock switches is placed in the BYPASS position. The annunciator is actuated by a set of contacts on the key-lock switch in the instrument rack which, when closed, energize a contact output relay. Indication of DSS IN TEST is provided through the use of a switched test jack which changes contact configuration when-a test plug is inserted. The test jack contacts are also wired to the contact output isolator card to drive the Control Room annunciators. All of the mentioned alarms.are displayed in the Control Room on the auxiliary feedwater annunciator boards (A66A and A668). Channels "A" and "C" share. annunciator windows on A66A and Channels "B" and "D" have common windows on A668. Indication of channel TEST and BYPASS.is provided by indicating lights as well as through the use of annunciators. Whenever a test plug is inserted or-a channel is placed in BYPASS, a corresponding blue light (located on AI-66A and AI-668) is illuminated and an annunciator is activated. The blue light and annunciator remain energized until the test plug has been removed and the channel key-lock has been placed in a position other than BYPASS. The blue light aids the Control Room operator in determining which channel -is in TEST / BYPASS. The annunciator itsel f does not indicate which channel is in TEST or BYPASS. The blue light and annunciator also serve to prevent the possibility of inadvertently leaving a test source connected to the E channel. 2.4 OVERPRESSURE DETECTION f The primary function of the bistable trip unit is to place a channel in the TRIPPED condition whenever high pressurizer pressure is detected. A voltage setting equivalent to the voltage which would correspond to a high pressurizer pressure is dialed into the alarm bistable card in the i bistable trip unit. The process value of the pressurizer pressure is continuously compared against the fixed setting. Whenever the process value exceeds the fixed, setting, output relays on the alarm bistable are energized which in turn de-energize the matrix relays on the i i contact output isolator cards. The output contacts are normally held

open, and close to trip when the trip setpoint is reached or power is failed to the trip unit. At this point the channel is said to be in a TRIPPED condition.

Rev. O 10/25/86 t s s ~. - - - - -. - - - - - - -

MR-FC-84-203 FINAL DESIGN DESCRIPTION The output contacts are configured into two redundant logic matrices. To minimize inadvertent actuation of the DSS, a two-out-of-four logic is used. The matrices are configured in matrix boxes JB-672A and JB-673A. The matrix boxes are located in the lower electrical penetration room and in the air compressor bay. The logic catrices.are equipped with supervisory lamps and relays (located in Control Room panels Al-66A and AI-66B) which provide the operators with a quick indication of the status of the DSS. The supervisory lamps are normally energized and give indication if an abnormal condition exists which could affect the operation of the matrix. If an interconnecting wire is lifted or a channel assumes a TRIPPED state, the affected matrix lights will be extinguished. A supervisory relay is used to verify that power is available in the matrix circuit. In the event of a loss of power to the circuit, the undervoltage supervisory relay acts to energize the appropriate DSS TROUBLE window on either A66A or A668 annunicator boards. 2.5 INITIATION OF REACTOR TRIP Once the two-out-of-four coincidence logic is satisfied, the lock-out ( s \\ relay in the matrix is energized. The lock-out relay in turn energizes the tripping relays (94-A/ DSS, 94-B/ DSS) which deenergize the under-voltage trip coils on the reactor trip breakers in AI-57. The lock-out and tripping relays are located in AI-66A and 668. The lock-out relays require deliberate operator action to be reset following an initiation event. Provisions have been made at the system level in the design of the DSS actuation circuitry to allow for on-line testing and maintenance. Two redundant matrices allow for one matrix to be out of service for a limited period of time. Each matrix is provided with a three position (NORMAI., BYPASS, AND TEST) key-lock switch to facilitate on-line testing and/or maintenance. The matrix key-lock switches are located at panels AI-66A and B. The key-lock switches are keyed alike and only one key is available. The keys are removable from the NORMAL position only. This assures that only one matrix will be BYPASSED or in TEST at any time. When a matrix is bypassed, annunciation is provided on the associated annunciator board (A66A or A66B). The key-lock switch will remain in the BYPASS position until it is returned to NORMAL at which time the annunciator will clear. When the key-lock switch is placed in the TEST 18 Rev. 0 10/25/86

i l MR-FC-84-203 FINAL DESIGN DESCRIPTION c

position, blocking relays are energized. Once energized, the blocking relays output contacts close to prevent deenergization of the undervoltage coils on the reactor trip breakers.

This blocking action allows the lockout and tripping relays to be functionally tested without causing a reactor trip. The blocking relays are located in panels Al-66A and Al-668. Manual reactor trip switches with two positions (TRIP AND NORMAL) are provided on Al-66A and AI-668 for manual actuation of the DSS at the system level. Once placed in the TRIP position, the reactor trip switch energizes the associated lockout relay which in turn energizes the tripping relays to interrupt power to the undervoltage coils on the reactor trip breakers. 2.6 REACTOR TRIP Deenergizing the undervoltage trip coils causes a trip of the reactor trip breakers. Once open, these breakers interrupt power to the clutch power supplies, which in turn causes a release of the clutch mechanisms , ( and a subsequent shutdown of the reactor. The reactor trip breakers ( b] have undervoltage,

thermal, and mcgnetic trips. The DSS utilizes the undervoltage trip coils to trip the breakers.

l 2.7 DIVERSE SCRAM SYSTEM SETPOINTS The pressurizer pressure trip setpoint for the DSS is below the setting for the code safety relief valves (2500 to 2545 PSIA) and above the setting for the Reactor Protection System (2400 PSIA). The setpoint for the DSS is 2450 PSIA and is based upon a square root of the sum of the squares of the involved uncertainties of the DSS instrumentation considering such factors as sensitivity, ambient temperatures, drift, etc. To give the Control Room operators advanced warning of increasing pressurizer pressure a DSS PRETRIP annunciator is provided. The setting for the pretrip alarm is 2400 PSIA. This value should provide the operator with sufficient warning that a reactor trip is approaching. 19 Rev. 0 O 10/25/86 V l

HR-FC-84-203 ~ FINAL DESIGN DESCRIPTION 'i. I i 2.8 PLANT COMPUTER INTERFACE WITH DSS The plant computer system is linked with' the output of the DSS transmitter._and bistable outputs. _The 0-10 VDC signal generated from the' current-to-voltage converter modules in AI-196 and AI-197 is fed directly to-the Qualified Safety Parameter Display System (QSPDS)' computer (AI-208A and AI-2088). The computer then interprets the signal, displays it, and transmits the corresponding pressure value to -the Emergency Response Facility (ERF) computer.via an optical link. -The computer points corresponding to these two pressure inputs are P0120A and P01208. The QSPDS and ERF computers both utilize _these point designations. A separate set of. inputs to the ERF computer (points P120A, B, C, and D),are used to monitor the status of the output contacts on the DSS channels. The computer's sequence of events program scans these points periodically. -In the event of a channel-trip, contact closure would noti fy the computer of the channel's tripped status. Since the computer is tied to the trip output, during testing of individual channels the associated computer points will be activated. Indication of DSS trip is provided via existing relays BW19, BW20, CW19, and CW20 on the clutch power supplies. 2.9 ELECTRICAL-EQUIPMENT SPECIFICATIONS i-The major components used in constructing the Diverse Scram System are listed below. More detailed information may be obtained by reviewing - j the referenced specification sheets. j PRESSURE TRANSMITTERS A/PT-120, B/PT-120, C/PT-120, D/PT-120 I Range: 0-3000 PSIG Accuracy: 10.25% of Cal. Span Output: 4-20 mADC Flanges: 316SS Power Supply: 12-45 VDC Housing: 316SS Response Time: <0.2 Sec Connections: 3/8" Swagelock Specification 499 (Rosemount Model 1154GPR9A) CURRENT-TO-VOLTAGE CONVERTER A/PM-120, B/PM-120, C/PM-120, D/PM-120 l Input: 4-20 mADC Output: 0-10 VDC Power Supply: 15 VDC Accuracy: 10.25% of Output Span Specification 499 (Foxboro N-2AI-I2V) 20 Rev. 0 10/25/86 t l

MR-FC-84-203 FINAL DESIGN DESCRIPTION 7() BISTABLE ALARM OUTPUT A/PC-120, B/PC-120, C/PC-120, D/PC-120 Input: 0-10 VDC Response Time: 15 i5 msec Output: Two SPDT Outputs (One for Each Setpoint) Power Supply: 15 VDC-Accuracy: 12% of Input Span Specification 496 (Foxboro N-2AP+ ALM) CONTACT OUTPUT ISOLATOR A/PA-120-1,2, B/PA-120-1,2, C/PA-120-1,2, D/PA-120-1,2 Input: 10V Minimum (4 Inputs) Output: IDPDT Output for Each Input Power Supply: 15 VDC Response Time: 0.010 see Specification 497 (Foxboro N-2A0-L2C-R) Other components of interest used in the DSS are: LOCK 0UT RELAY General Electric Model 12HEA61A223 Lockout Relay 125 VDC Coil 3NO, 3NC Contacts TRIPPING RELAY, BLOCKING RELAY General Electric Model HGA111J2 Auxiliary Relay 125 VDC Coil 2NO, 2NC Contacts KEY-LOCK SWITCHES Microswitch P/N PTKEB2331C, PTKEB2332C, PTSBC202C 3.0 DESIGN ANALYSIS 3.1 REGULATORY GUIDANCE COMPARIS0N l The NRC has published an equipment guivance which establishes criteria in areas such as diversity, testability, electrical independence, etc. for a DSS design that the NRC staff believes will comply with i 10CFR50.62. This document - 49FR26043,26044 " Guidance Regarding System ~ 21 l Rev. 0 10/25/86

-MR-FC-84-203 FINAL' DESIGN DESCRIPTION Ov and~ Equipment -Specification" is not a regulatory requirement. It describes one option for meeting the ATWS Rule requirements. In specifying design requirements for the Fort Calhoun DSS, however, the NRC's equipment guidance is treated as a set of requirements. Table I lists the NRC's-guidance and the method in which the DSS design for Fort Calhoun meets the guidance. The implementation of a DSS provides an inherent diverse turbine trip. When the DSS causes a reactor trip, it also causes.the turbine to trip because the DSS interrupts power to the Control Element As:embly (CEA) coils. The turbine trip is then initiated when clutch power supply relays BW19, BW20, CW19, and CW20 are deenergized. When power is interrupted to the coils the undervoltage relays on the clutch power supplies are de-energized and a turbine trip is initiated. With the implementation of the DSS, the existing turbine trip becomes a diverse turbine trip due to the diversity between the DSS and the existing Reactor Trip System. O 1 1 i 4 22 Rev. 0 (} 10/25/86 8

MR-FC-84-203 FINAL DESIGN' DESCRIPTION mQ TABLE I Comparison of NRC Guidance for DSS and Fort Calhoun DSS Design NRC GUIDANCE FOR FORT CALHOUN DESIGNED SUBJECT DIVERSE SCRAM SYSTEM DIVERSE SCRAM SYSTEM Safety Related Not required, but the implementation Equipment for the DSS will be (IEEE-279) must'_be such that the existing Pro-purchased,. installed, and main-tection System continues to meet all tained as Class IE, Critichl applicable safety related criteria. Quality Elements. This is done to improve reliability and avail-ability of the system. hdundancy Not Required Redundancy has been incorporated in the design to facilitate on-line testing of the logic

matrices, lock-out relays, and signal processing circuitry.

Diversity from Equipment diversity to the extent See Table II for a detailed the Existing reasonable and practicable to minimize comparison of DSS and Reactor Trip System the potential for common cause fail-Trip System components. Suffic-ures is required from the sensors to tent diversity exists to mini-and including the components _used to mize the potential for common interrupt control rod power or vent cause failures. the scram air header.- Circuit O breakers from different manufacturers alone are not sufficient to provide the required diversity for interrup-tion of control rod power. All Di-verse Reactor Trip System instrument channel components (excluding sensors, but including all signal conditioning and isolation devices) must be diverse from the existing RTS. Acceptable methods of achieving required divers-ity include use of energize-to-actuate versus deenergize-to-act%te trip logic and use of devices erbioying dif-ferent operating princip1re (e.g., use of electromechanical deQces versus electronic devices). Use of AC versus DC power and components fCm different manufacturers should be* considered. 23 r ~ Rev. O 10/25/86 O ~

MR-FC-84-203 ~ FINAL DESIGN DESCRIPTION. rm NRC GUIDANCE FOR-FORT CALHOUN DESIGNED z SUBJECT DIVERSE SCRAM SYSTEM DIVERSE SCRAM SYSTEM Qiversity From The use of rotary versus standard

he Existing pull-in type relays, denergize-to-frip System actuate versus deenergize-to-actuate (Cont'd) relays and AC versus DC relays, regard-less of manufacturer is sufficient to satisfy the diversity requirements of the ATWS Rule.

Printed Circuit (PC) cards must be from a different manufac-turer than that of PC cards performing similar. functions .(signal condi-

tioning, logic, etc.) in the existing RTS.

The sensors need not be of a diverse New sensors are used for the design or. manufacturer. Even though DSS. The new sensors are from a sensor diversity is not necessary, it different manufacturer than the is desirable that sensors in the exist-ones 'used for the Reactor Trip i.ng Reactor Trip System not be used to System. provide diverse equipment required by the ATWS Rule. Use of the same sensor for the existing Reactor Trip System and the diverse equipment would result-in interconnections between the two O-systems that are difficult to analyze I and which could increase the potential for common cause failures affecting both systems. Since the sensors for i the equipment required by the ATWS Rule do not have to be safety related, there should be considerable flexibil-ity for using existing sensors without using Reactor Trip System sensors. In cases where existing Protection System sensors are used to provide signals to the diverse equipment, particular emphasis should be placed on the i design of the method used to isolate the signal from the existing Protec-tion System to minimize the potential for adverse electrical interactions. i I I 24 Rev. 0 l 10/25/86 lO i _,._,,_ma, _n.,_,..---m.,,-,.m-

MR-FC-84-203 FINAL DESIGN DESCRIPTION ' d, SUBJECT NRC GUIDANCE FOR FORT CALHOUN DESIGNED DIVERSE SCRAM SYSTEM DIVERSE SCRAM SYSTEM Giversity from Existing Protection System instrunent The sensors for the DSS share the Existing sensing lines should be selected such the same sensing lines as the trip System that adverse interactions with exist-pressure transmitters used for (cont'd) ing control systems are avoided. the Reactor Trip System. Electrical Required from sensor output to the The DSS is electrically indepen- !adependence final activation device at which point dent from the Reactor Trip I.om the nonsafety related circuits must be System. The DSS circuitry is nisting Reactor isolated from safety related circuits. safety related and all wiring 1.ip System and cabling associated with the DSS meet the requirements of IEEE STD 384-1974 or original plant design criteria. Physical Not required unless redundant divi-The DSS is physically separated M aration from sions and channels in the existing from the Reactor Trip System

ne Existing Reactor Trip System are not physically with the exception of the cables Wactor Trip separated.

The implementation must be and trip coils which are an ijstem such that separation criteria applied integral part of the Reactor to the existing Protection System are Trip breakers. not violated. (~3ironmental For anticipated operational occur-DSS equipment is qualified for b lification rences only, not for accidents, normal service conditions. utsmic Not Required. Equipment used in the DSS is jualification seismically qualified per IEEE STD. 344-1975. Junction boxes, conduit and other associated equipment for the DSS are seismically mounted as required for safety related equipment. 5: lity As required by Generic Letter 85-06, The DSS is installed,

tested, usurance for "Ouality Assurance Guidance for ATWS and maintained as a Class IE
iest, Equipment that is not Safety Related".

System.

aintenance, and sarveillance Sa fety-Rel ated Not required, but must be capable of The DSS signal processing and

(;E) Power performing safety functions with loss instrument loop circuitry wpply of offsite power. Logic and actuation derives its power from the nest power supplies in the Auxiliary 25 Rev. 0 10/25/86 O

MR-FC-84-203 FINAL DESIGN DESCRIPTION pO NRC GUIDANCE FOR FORT CALHOUN DESIGNED SUBJECT DIVERSE SCRAM SYSTEM DIVERSE SCRAM SYSTEM Safety-Related device power must-be from an instru-Feedwater Actuation System (IE) Power ment power supply independent from the instrument racks. The instru-Supply (Cont'd)- power supplies for the existing ment racks are powered from the Reactor Trip System. Logic and plant's safety related inverters actuation device power should be via individual breakers on the supplied from a station battery other AC instrument bus distribution than those used in the existing RTS. panels. These panels also sup-The batteries and/or inverters used ply power to the Reactor Pro-for Diverse Reactor Trip System tection System. Matrix power is components need not be diverse from, opplied from the station DC but must be electrically independent Suses. of the existing RTS. Existing RTS sensor and instrument channel power Equipment and design diversity supplies may be used only if the between the DSS and the Reactor possibility of common mode failures is Protection System assures prevented. against common mode failures. (See Design Analysis Section 3.2 for a more detailed discussion). Testability at Required. The Diverse Reactor Trip The DSS is designed with the i'ower System function may be by-passed to capability to test from the (V3 prevent inadvertent actuation during sensor output to the trip coils testing at power. The bypass condition on the Reactor Trip breakers must be automatically and continuously with the plant on-line. The indicated in the main Control Room. trip coils will be tested when the plant is shut down. When a channel is placed in bypass, contacts on the bypass switches energize annunciators in the main Control Room. Indication of inserted test jacks is also provided. t inadvertent The design should be such that the A 2-out-of-4 coincidence logic ictuation frequency of inadvertent reactor trips is used for the DSS to minimize and challenges to other safety systems inadvertent reactor trips. is minimized. <aintenance The system design may permit bypass of The DSS design permits the by-apasses the diverse trip function to allow pass of individual channels and maintenance,

repair, test or cali-of the redundant logic matrices bration during operation to avoid to permit maintenance and test-inadvertent actuation of protective ing of the system.

The use l action at the system. 26 Rev. 0 10/25/86 l

1 l MR-FC-84-203 FINAL DESIGN DESCRIPTION NRC GUIDANCE FOR FORT CALHOUN DESIGNED SUBJECT DIVERSE SCRAM SYSTEM DIVERSE SCRAM SYSTEM

4:intenance level.

The use of maintenance of key-lock by-pass switches Jypasses bypasses. shall be restricted as permit only one channel or (Cont'd) governed by Technical Specification matrix to be bypassed at any out of service times and limiting given time. When a channel or conditions for operation. The bypass matrix is placed in bypass, condition should be continuously indication is provided through indicated in the Control Room. continuous annunciation in the Control. Room. Technical Speci-fication requirements allow a channel to be bypassed for up to 48 hours before it is either returned to service or placed in the trip condition. ]perating Where operating requirements neces-The DSS' is actuated by high 3ypasses sitate automatic or manual. bypass of pressurizer pressure. There is the-Diverse Reactor Trip System, the not a need to have an operating design should be such that the bypass b.vpass for this parameter, will be removed autc.natically whenever permissive conditions are not met. Removal of the bypass condition should be indicated in the main Control Room. O Indication of If the protective action of some part An annunciator is wired to each snasses of the Diverse Reactor Trip System has bypass switch to provide indi-been bypassed or deliberately rendered cation when the switch has been inoperative for any purpose, this fact placed in bypass. Annunciators should be continuously and automat-are also provided to indicate ically indicated in the Control Room. DSS in test. 4eans for The use of a maintenance bypass should A permanently installed key-lock 3ypassing not involve installing

jumpers, bypass switch is used to bypass lifting leads, pulling fuses, tripping a channel or matrix.

breakers or blocking relays. A perma-nently installed bypass switch or similar device should be used.

ompletion of The design should be such that, once A lock-out

~ relay requiring 'rotective initiated, the protective action at manual reset will be used to i~ iction Once it the system level shall go to comple-trip the relays which energize is initiated tion. Return to operation should the undervoltage trip coils on require subsequent deliberate operator the reactor trip breakers. action. 27 Rev. O j 10/25/86 lO i l.

. - ~ - _ - -.. -.. .-- =_ T MR-FC-84-203 FINAL DESIGN DESCRIPTION NRC GUIDANCE FOR FORT CALHOUN DESIGNED SUBJECT DIVERSE SCRAM SYSTEM DIVERSE SCRAM SYSTEM unual Manual initiation capability of the The DSS may be manually acti-t Initiation Diverse Reactor Trip System at the vated in the Room using switches j control system level should be provided. that act to deenergize the'under-Manual initiation should-depend upon voltage coils on the reactor s the operation of a minimum of trip breakers. l equipment. !nformation The Diverse Reactor Trip System should Supervisory indication at the 4

!eadout be designed to provide the operator system
level, trip indication with accurate,
complete, and timely lights on the tripping relays, information pertinent to its own pretrip.and trip annunciators

. status. and lights all provide suffic-ient information to ascertain the status of the DSS. 1 i O i. - i I 1 5 l l 28 Rev. 0 l 10/25/86 i.lO i -s- --w-y-,r-wr-,---e--wmvw,,,-,--, rec,,-rv --,-wrv>vo m - e w, w.w r y,e- ,#m-r-e---wwe--er-ww--= .-.m,wy,---ry---==wem,y+-r----w,,eymye=

MR-FC-84-203 FINAL DESIGN DESCRIPTION g 3.2 COMPONENT LEVEL COMPARISON OF DSS AND RTS The physical separation, independence and diversity of the DSS equipment from the Reactor Trip System protects against common mode failures. Table II gives a detailed comparison, at the component level, of the DSS and the Reactor Trip System. 3.2.1 Power Supply As shown in Table II, the DSS exhibits a high degree of diversity from the Reactor Protection System. The only area in which diversity is not shown is in the use of a common AC and DC power source for the two systems. The AC power sources for both the DSS and the Reactor Protection System are the 4 vital AC instrument buses. The DC power sources are the two station DC buses. These buses provide the systems with

reliable, uninterruptable power.

The DSS and the Reactor Protection System are fed from separate breakers on the instrument buses. The Reactor Protection System is not directly connected to the DC buses, but it is indirectly connected to the DC buses through the instrument inverters. In analyzing possible common cause failures for the AC power sources, four possible causes of failures are of primary concern. The possible scenarios are: transient overvoltage conditions, loss of power, ~N (d grounding of the power source, and short circuit events. The DSS utilizes the 120 VAC vital instrument buses to supply power to the bistable trip units as stated in the Technical Description portion of this design

package, the bistable trip unit consists of the current-to-voltage converter, alarm module, and contact output cards.

Each bistable trip unit is supplied with power from 15 VDC power supplies. These power supplies, which are diverse from those which serve the Reactor Protection System, obtain their power from the 120 VAC vital buses. A transient overvoltage condition from the 120 VAC system would be isolated at the cabinet power supply. Since the power supplies are diverse from those used for the Reactor Protection System, diverse rosponses to the transient overvoltage would occur. Loss of 120 VAC power would result in a trip at the channel level of the DSS since the contact output relays deenergize to trip. A ground on either leg of the 120 VAC power would not cause a failure of the DSS since the system 29 Rev. 0 10/25/86 0 4 4 i r--,

MR-FC-84-203 FIfML DESIGN DESCRIPTION j is isolated from the station's grounding system. A ground on both legs would result in a loss of power to the channel. A short circuit in the 120 VAC power supply would ultimately result in a loss of power to the affected channel. The two-out-of-four matrices and the trip actuation devices use 125 VDC from the station's 125 VDC systen. Possible common cause failures for this system are the same as for the 120 VAC systen: transient overvoltage, loss of power, grounding, and short circuit conditions. Transient overvoltage conditions would not produce common cause failures between the DSS and the Reactor Protection System because none of the Reactor Protection System components obtain power directly from the DC system. Loss of power to one of the DC buses would cause a reactor trip from the DSS since two channels would assume a TRIPPED status and the redundant logic matrix would initiate a reactor trip. If both DC buses lost power, the reactor would trip because the clutch power supplies would have no power. A ground on either leg of the DC supply would not affect the DSS since the system is isolated from the station's grounding system. Grounding of both legs of the DC system would result in the loss of DC power. A short circuit in the DC system would ultimately result in the loss of DC power to the affected matrix in the CSS. OV It is concluded, therefore, that due to component and design diversity between the DSS and the Reactor Protection Sys tera, there is no potential for a common cause failure due to common power supplies. 3.2.2 Separation Criteria Physical separation and segregation within instrument panels is maintained whereever possible by the DSS. It should be noted that existing inner-panel wiring does not strictly comply with the recommended segregation guidelines stated in IEEE-384. No attempt will be made by this modification to correct existing wiring runs for compliance with IEEE-384. The DSS installation will maintain existing degrees of separation. To a certain extent, segregation by means of physical separation already exists in the Auxiliary Feedwater Actuation System instrument cabinets and in the AI-66A and Al-66B panels. Cables of different safety grade channels enter the Auxiliary Feedwater Actuation System cabinets from either right or left and above or below and are terminated on adjacent terminal blocks maintaining physical separation. Inner-panel wiring is separated through the use of plastic runways where possible. All four safety grade cable classes (EA, EB, EC, and ED) have terminations in each of the cabinets. 30 Rev. O p 10/25/86 V

MR-FC-84-203 FINAL DESIGN DESCRIPTION In.the Al-66A and AI-668 panels, cables enter from the bo'ttom left and right. sides. Cables on the left side are one safety grade channel and cables on the right are of a different channel. Primarily EA and EC cables are in AI-66A and EB and ED cables are in AI-668. In these panels metal barriers are used, in conjunction with physical distance i between wire classes, to separate inner-panel wiring. A metal pass-through box connects the AI-66A -and Al-668 panels to allow i different cable classes to connect to either panel. l To help insure reliability, the DSS is isolated.from the station's grounding system. The butt-splices used at the containment penetrations. and conduit seals are soldered and shielded cable is used to minimize the possibility of electromagnetic interference. 3.2.3 Regulatory Guide 1.97 The new ATWS instrumentation has been included in the District's revised response to Regulatory Guide 1.97. A summary of compliance with Reg. Guide 1.97 is provided in Attachment F. f i i i i i h t G [ 31 Rev. 0 1 10/25/86 ,!O

O O O TABIE II Ccr1ponent caparison Between Diverse Scram System and Reactor Protection System Otzponent Design Reactor Diverse Cwaxisit Tyce Descriction Protection System-Scram System Diversity Sensors High Maralfacturer Foxboro Transmitter Prv:amnunt Transmitters Yes Pressurizer Pressure Sensors High Model No. N-EllGi-HIE 2-AD-L ll54GP9RA Yes Pressurizer Pressure Sensors High Design Principle Force Balance Device, Capacitance, 4-20 FA 'Yes Pressurizer lO-50mA Output '2W Pressure 100 OHM Resistor = 1 to 5 Volts to RPS Sensors High D.C. Power Supply: General Electric GE/MAC Foxboro Yes Pressurizer Manufacturer )$/570-01 +/-15VDC Nest Pressure Power Supply Sensors High D.C. Power Supply: Single Plug-In N-2ARPS-6 Yes Pressurizer Part No. 2177K61G700 Pressure Sensors High A.C. Power Source Channelized Instrument Channelized No(l) Pressurizer Bus A,B,C,D Instrument Pressure Bus A,B,C,D Cistables Single Manufacturer Gulf Electronic Systems Foxboro Yes Omparison TYPE (1) Sufficient diversity exists between %= ads of the Reactor Protection System and the Diverse Scram System that the potential for <wnmnn cause failures due to shared AC power sources is minirized. 32

O O O CWnt Design Reactor Diverse Conmet Type Description Protection System Scram System Diversity Cistables Single Model No. ELD 240-0000F N-2AP& AIM-AR Yes Cecparison (Dual Absolute Alarm) Type Bistables Single Design Principle OP-AMP: Motorola MC1433P OP-AMP: Nat'l. Yes Camparison (EM) Relay Out (Trip): IM301A, (IM) Relay Type Clare HGSM51113R01 Out: Foxboro Input 0-10 VDC Signal and HiN0279CT a Setpoint Signal - Each Input 0-10VDC Signal Input to a Differential and a variable Set-OP-AMP, Analog Switch, to point Signal are a Relay out each Input to a Differential Analog Switch, to a Relay Output Carti Pi.Dgaik Wiring Determines Input Bistables Single D.C. Power Supply: Power Mate +/-15VDC Foxboro +/-15VDC Yes caparison Manufacturer Supplies Nest Power Supply Type Bistables Single D.C. Power Supply: P1048 EPA 15.750/15.750/15 N-2ARPS-A6 Yes Camparison Part No. Type Bistables Single A.C. Power Source 120VAC Via Omnnelized 120VAC Via Channelized No(l) Caparison Instrument Bus A,B,C,D Instrument Bus A,B,C,D DTS Matrix Manufacturer Douglas Randall Foxboro Yes Relays Matrix Model No. 378907 N-2AO-I2C-R Yes Relays 33

O O O Ccepr.ent Design Reactor Diverse Ctyponent Type Description Protection System Scrari System Diversity Hatrix Design Principle Eler_hwechanical Relays Electr mechanical Yes Relays Relays N0152K(Fo:dx>ro), 172-DIP-55 (MAGNACEAET),F81-1083 (GORDOS) Matrix D.C. Power Supply: Power Mate +28VDC Power Foxboro +15VDC Yes Relays Manufacturer Supplies Nested Power Supply Matrix D.C. Power Supply: RB28-1.5 N-2ARPS-6 Yes Relays Part16. Matrix A.C. Power Source 120VAC Via Channelized 120VAC Via Qiannelized No(l) Relays Instrument Bus A,B,C,D Instrument Bus A,B,C,D t Initiation Interposing Manufacturer AGASTAT General Electric Yes Relay Relay (IR) Initir_ tion Interposing Model 16. IX;PIOO1 HEA61A223 Yes Relay Relay (IR) Initiation Interposing Design Principle The IR Coil is De-energized 'Ihe IR Coil is Yes Relay Relay (IR) (120VAC) when the 2/4 Energized (125VDC) Matrix Relay contacts open. When the 2/4 Matrix 'Ihis opens the IR contact contacts close. This connected to the PR coil. closes the IR contact unia.,-ted to the PR coil. Initittien Interposing D.C. Power Source N/A 125VDC Frm Yes Relry Relay (IR) DC Bus #1, #2 34

O O O C @ = sit Design Reactor Diverse G 3=L TVDe Description Protection System Scram System Diversity i Initiation Interposing A.C. Power Source 120VAC via irLemt bus N/A Yes l Relay Relay (IR) A/B or C/D for channels A,B or C,D 1 ) Actuatim Primary Mamfacturer Allen Bradley (M Cbntactor) General Electric Yes j Relay Relay (PR) i ~ Actuation

  • Primary Mn@1 No.

702-DAD-94 HGA11LT2 Yes Relay Relay (PR) !j Actuatim Primary Design Principle The PR (M Contactor) Coil. The Primary 0011 Yes Belay Relay (PR) is De-energized utwn the Energizes when the IR IR Contact is Tripped, Contact Closes, this 1 This causes 1205'AC Power deenergizes the under-to be renoved frm the voltage trip coil on the clutch power supp'i m.. reactor trip breaker to open the breaker I and release the control rods. Actuation Primary D.C. Power Source N/A 12SVDC Bus #1,82 Yes l Relay Relay (m) \\ 9 J I i i I 35 -,. ~

O O O Ctmiponent Design Reactor Diverse Otzmorent Tvoe Description Protection System Scram Systen Diversity Actuation Prirary A.C. Power Source 120VAC Via Instument Bus N/A Yes Relay Relay (PR) A/B or C/D for Qannels A,B or C,D Power Manufaoh Allen Bradley Westingtvu m Yes Internpt (M Contactor) (Undervoltage Trip) To Clu*d Power Supplies Power Model !b. 702-DTD-94 JA22000 Yes Internpt To Clutch Power Supplies Power Design Principle Openirq of IR Contact Undervoltage Trip Yes In'anpt Causes Power Ioss to M Coil is Deenergized To Clutch Contactor and 9them=nt by PR Relay and Trips Power Supplies Removal of Ibwer to the Reactor Trip Breaker Clutch Power Supplies. to Interrupt Power to the Clutd1 Power Supplies. Power A.C. Ibwer Source 120VAC Via Instrument Bas 120VAC Via lb(1) Interrupt Channels Instrument Bas A/B or To Clutch A,B, or C/D C/D for 01annels A,B, or Power Supplies C,D 36

o MR-FC-84-203 FINAL DESIGN DESCRIPTION v' 3.3 SYSTEM RESPONSE TIME System response time for the DSS is expected to be less than the 2 second requirement stated in the design basis. Response times for various components in the DSS are as follows: Pressure Transmitter at 100*F < 0.2 Sec. Alarm Cards 0.015 1 0.005 Sec. Relay Output Cards 0.010 Sec. Lock-Out Relay < 0.015 Sec. Tripping Relay < 0.0166 Sec. Undervoltage Trip Coil < 0.05 Sec. Deenergize Clutch Power Supplies 0.5 Sec. + Cable - Neoliaible Overall System Response 0.81 Sec. Assuming a step change in pressure, the system would be expected to respond in this amount of time. All values given are for step changes in input. The system response time for the DSS is well within the two second requirement. 3.4 IMPACT OF DSS ON EXISTING SYSTEMS d,fm 3.4.1 Fire Protection Review This modification (addition of DSS) does not prevent or alter present fire detection or suppression systems. Existing instrument racks or panels will be used to house the majority of the electrical equipment. Junction boxes which are to be installed will be placed in locations which do not block or change the flow paths of adjacent fire suppression systems. During the construction phase of this modification, permanent fire barriers will be penetrated in accordance with station procedures to permit the installation of new electrical cables. The addition of the DSS does not adversely impact the station's design bases for compliance with Appendix R of 10CFR50. Segregation and separation criteria are satisfied in the DSS design. The DSS is not required for the safe shutdown of the plant. 37 Rev. 0 10/25/86 (3 o

MR-FC-84-203 FINAL DESIGN DESCRIPTION (7 l The addition of instrumentation to the alternate shutdown panel has been considered and found to be unnecessary. The increased pressure range (1900-2900 PSIA) that the DSS monitors is not information which i is required to accomplish safe shutdown from this control panel. Indication is provided for 0-2500 PSIA. The addition of the higher pressure range would be used only if two failures occurred; a Control Room fire coupled with a failure of the Reactor Protection System to mitigate the high primary pressure. 3.4.2 Environmental Qualification All components added by this modification, with the exception of the junction boxes and indicating lights, are considered to be Critical Quality Elements (CQE). The junction boxes are limited CQE. The CQE list shall be updated to reflect these additional components. The pressure transmitters, conduit seals, associated cabling inside containment, and the containment penetrations are environmentally qualified equipment and will be included in the District's EEQ Program. Testing and analysis have demonstrated a qualified life of 10 years at 120*F for the transmitters. If the electronics boards in the transmitters are replaced after 10 years, the qualified life of the transmitter can be extended to 15 years at 120'F. The conduit seals are qualified for 40 years at 120*F. 3.4.3 Seismic Analysis The addition of equipment to instrument racks and panels will be reviewed for seismic concerns prior to equipment instailation. All seismic supports for conduits and instrument tubing associated with the DSS will be constructed on an "As Needed" basis at the time of instal-lation. 3.4.4 Electrical Systems Analysis The loading on the AC and DC instrument buses will be increased by this modification. Buses A, B, C and D will see a load increase of approximately 125mA. Instrument bus 8 is the most heavily loaded with a current of approximately 40 AMPS. Each of these buses have a 7.5 KVA inverter which can supply 62.5 AMPS at full load. The additional loading on these buses will not create adverse loading conditions. The DC buses, I and 2, will see a load increase of 285 mA during normal conditions, 355 mA when the DSS trips, and 430 mA when the DSS is in test. DC bus #2 is the most heavily loaded bus with approximately 225 AMPS of load current. This bus can normally carry up to 380 AMPS of 38 Rev. 0 10/25/86

MR-FC-84-203 FINAL DESIGN DESCRIPTION / i v._/ load. Under conditions of station blackout, the increased load on the batteries would be a maximum of 3 AMP-hours. The additional loading on the DC buses does not significantly affect the design margin for the buses or the station batteries. Upon completion of the AC and DC distribution system load studies, the loads added by this modification will be incorporated into the appropriate database. 3.4.5 Human Factors Review The Preliminary Design Package for this modification was submitted to General Physics to facilitate a Human Factors Review. The review was conducted to assess the conformance of the DSS design to NUREG-0700 requirements. Exceptions to the guidelines were noted by General Physics and have been addressed. Prior to implementation of this modification the General Physics comments, none of which will greatly affect the design as shown on the attached drawings, will be resolved. 3.4.6 Security Review This modification will have no impact on security procedures presently in use at the plant. g V 3.4.7 Naterials Compatibility The transmitters and associated instrument tubing are constructed of 316SS. This material is compatible with that used in the primary system. The transmitters will be factory cleaned to prevent possible contamination of the primary system fluid. 3.4.8 ALARA The DSS has been designed to keep personnel radiation exposures n low n reasonably aghievable. The pressure transmitters are located outside the bioshield wall inside reactor containment. The tubing for the transmitters will be installed in such a manner as to minimize the potential for crud traps. The transmitters themselves were selected with ALARA considerations in mind. The Rosemount transmitter are said to require less calibration time than the competing transmitter models. Personnel exposure to radiation is unavoidable in the implementation phase of this modification. Plant procedures and health physics recommendations will be used to keep exposures n low n reasonably achievable. 39 Rev. 0 10/25/86 O V

MR-FC-84-203 FINAL DESIGN DESCRIPTION 4.0 SAFETY ANALYSIS 4.1 Is the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Safety Analysis Report increased? No. The addition of the Diverse Scram System is in direct response to 10CFR50.62. The system is intended to reduce the probability of an overpressurization accident which might occur if, for some reason, the reactor protection system failed to function properly. The Diverse Scram System will act to minimize the possibility for a release of primary coolant to the containment atmosphere and possibly to the public environment. The Diverse Scram System has been designed to be independent from the Reactor Protection System. In the event of a failure of some portion of the Diverse Scram System, the Reactor Protection System would be able to perform its intended function. The two accident scenarios listed in the USAR which result in an increasing pressure event are as follows: 14.9 Loss of Load 14.10 Malfunctions of the Feedwater System In both cases, the Reactor Coolant System pressure increases to 2400 (n'] PSIA and is then reduced through the actuation of the Reactor Protection System. In the event of a failure of the Reactor Protection System, Combustion Engineering has determined that the maximum Reactor coolant System pressure in both cases is 2600 PSIA with a DSS installed. The applicable sections of the USAR should be reviewed by Technical Services to determine if a revision is necessary to include this new scenario. This would be a case where two failures are assumed to occur. The DSS has been designed in accordance with the USAR Requirements regarding independence and separation of safety systems. Therefore, the probability of previously analyzed failures in instrument and electrical systems will not be increased. 4.2 Is the possibility for a malfunction of a different type than any evaluated previously in the Safety Analysis Report created? 40 Rev. 0 10/25/86 0

=- MR-FC-84-203 1 FINAL DESIGN DESCRIPTION ,b No. No new possibilities are created. If the DSS should fail or assume a tripped condition the largest affect that could be normally expected is a reactor trip. If a fire were to be generated by an electrical component associated with the DSS, the only system which would be immediately affected would be the Auxiliary Feedwater Actuation System. Sufficient redundancy and physical separation exists in the Auxiliary Feedwater Actuation System that if a fire should occur in a single cabinet, the system would still be able to perform its intended function. If the Auxiliary Feedwater Actuation System were rendered inoperable, operators would be able to assume manual control at the emergency feedwater control panel. This situation has been previously analyzed in the Safety Analysis Report. The Reactor Protection System, being physically separated from the DSS, would not be affected immediately in the event of a fire. The DSS acts to minimize the peak pressure and reduce component stress levels in an overpressuriz; tion event which may be undetected by other safety systems. The overpressurization event could possibly occur during the following previously analyzed malfunctions: Zero power control element assembly withdrawal Loss of Reactor Coolant System flow (complete or partial) g Loss of load (complete or partial) Loss of main feedwater (complete or partial) Uncontrolled boron dilution Loss of offsite power Asymmetric steam generator pressure 4.3 Is the margin of safety as defined in the basis for any Technical Specification reduced? No. By adding the DSS the margin of safety is increased in the basis for Technical Specification 1.2.

Now, in addition to the reactor high-pressure trip and the Reactor Coolant System safety valves, the DSS helps to assure that the nuclear steam supply system pressure does not exceed the safety limit of 2750 PSIA.

The Diverse Scram System meets the same requirements established for the Reactor Protection System's high pressurizer pressure parameter which are delineated in Section 2.15. 41 Rev. 0 10/25/86

i MR-FC-84-203 FINAL DESIGN DESCRIPTION q V When one of the channels of the DSS is taken out of service for maintenance, the Protective System logic can be changed to a two-aut-of-three coincidence for a reactor trip by bypassing the channel. If in the 2 of 4 logic system of the DSS, one channel is bypassed and a second channel manually placed in a tripped condition, the resulting logic is 1 of 2. 5.0 PLANT DOCUMENT UPDATE As a result of this modification, several plant documents will require revisions. In some cases, new procedures will need to be generated. The following list of documents will be affected: USAR Section 7 USAR Section 14 (Possible Revision) Technical Specification Section 2.15 Technical Specification Section 1.2 Calibration Procedures - loops 120A, B, C, and D (New) Surveillance Tests - DSS (New) System Description - DSS (New) Champs CQE List EEQ Manual q]' Technical Data Book - Electrical Loads Operating Procedure OP Annunciators A66A, A668 6.0 WORK OUTLINE The following installation and testing outlines have been provided to assist in scheduling activities associated with this modification. Since this is an entirely new and independent system, many parts of the installation may be performed simultaneously depending on manpower support. The testing sections, however, will be performed in a sequence similar to the one provided below. 6.1 INSTALLATION a. Install pressure transmitters and tubing, b. Install conduit and cable in containment. c. Install new modules in auxiliary feedwater cabinets. d. Make wiring changes in auxiliary feedwater cabinets. e. Install junction boxes for matrix configuration. 42 Rev. 0 10/25/86 O I i e ,.----.v---. ---.-.-----------v.-,

.-.e.-

MR-FC-84-203 FINAL DESIGN DESCRIPTION V(x f. Install conduit and cable between auxiliary feedwater cabinets and the Control Room. g. Install new devices in'Al-66A and AI-668. h. Make wiring changes in AI-66A and AI-668. 1. Make wiring changes in Al-57. 6.2 TESTING a. Pressure Transmitter Calibration b. Channel Calibration c. Matrix Actuation Relay Test d. Matrix " Trouble" Test e. Two-0ut-Of-Four Logic Test f. Matrix Supervisory Lamp Test g. Response Time Test h. Matrix Bypass Test 43 Rev. 0 10/25/86 0 I ,__mm -,

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/ O i ) ATTACHMENT A O [ l ) O f ,ov--mw ~ - - - -. - - ,-.,.,..-n,--.

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[ ).Pyeliminary Design p [X] Final Design [ ] Construction Package y t. I 's Fort Calhoun Unit No. I Station Location and Unit No. 2 DRAWING LIST e GSE TASK /MR # FC-84-203 Steve Miller Design Engineer s Ns Date Drawing List Issued: 5/14/86 Revision 1 1 Drawings Incl. This File # Oftwino l', , Issue # Vendor Descriotion [_qE Transmittal 40239 Il405-EM-120' B OPPD Instrument & Control X X ' Sh. 1-Equipment List-DSS l O ' 40 .'11405-EM-120B OPPD Instrument & Control X X ~ 4 02 ~ Sh. 2,

  • Equipment List-DSS 40230' Spec. Sh. 495 B

OPPD Specification-Current X X to Voltage Converter Spec) Sh. 496 B OPPD Specification-Nest X X 40231 Sh. 1 Alarms ^-l' 4 'i32 Spec. Sh. 496 B OPPD Specification-Nest X X Sh. 2 Alarms 40233 Spec. Sh. 497 8 OPPD Specification-Contact X X Sh. 1 Output Isolator 40234 Spec. Sh. 497 B OPPD Specification-Contact X X Sh. 2 i Output Isolator 40235 .Sphc. Sh. 498 Is OPPD Specification-Power X X xSh.<1 Distribution Component 40236 Spec. Sh. 498 9 OPPD Specification-Power X X Sh. 2 Distribution Component \\ ' Page 1 of 4 O j 4 - E, ,,-r -,,.---------,..-e-- - ~ - - ~ - -,,

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T ~ l-Appendix B-3-2' Rev 10/85 [-] Preliminary Design. [X] Final Design [ ] Construction Package -Fort Calhoun Unit No. 1 Station Location and Unit No. DRAWING LIST GSE TASK /MR # FC-84-203 Steve Miller Design Engineer Date Drawing List Issued: 5/14/86 Revision 1 Drawings Incl. This File # Drawina # Issue # . Vendor Description faE Transmittal 40237 Spec. Sh. 499 B OPPD Specification-Pressure X X' Sh. 1 Transmitter 0238 Spec. Sh. 499 8 OPPD Specification-Pressure X X Sh. 2 Transmitter 40245 E-4083 8 OPPD Schematic Diagram-DSS X X 40241 81N30237-BD-009A B OPPD Channel "A" Block X X Diagram 40242 81N30237-BD-009B B OPPD Channel "B" Block X X Diagram 40243 81N30237-BD-OllC B OPPD Channel "C" Block X X Diagram '40244 81N30237-BD-0110 B OPPD Channel "D" Block X X Diagram 22653 NL-1A B Foxboro AI-196 Nest Load X X 22654 NL-1B B Foxboro AI-197 Nest Load X X 22655 NL-lC B Foxboro AI-198 Nest Load X X 22656 NL-10 B Foxboro AI-199 Nest Load X X ( Page 2 of 4

4 j, Appendix B-3-2 Rev 10/85 I [ ] Preliminary Design [X]-Final Design [ ] Construction Package I: l' Fort Calhoun Unit No.1 Station Location and Unit No. l DRAWING LIST GSE TASK /MR # FC-84-203 Steve Miller ] Design Engineer Date Drawing List Issued: 5/14/86 Revision 1 2 l Drawi,. Incl. -is File # Drawina # Issue'# Vendor'. Descriotion L.QE Transm ttal 22657 SC-1AD B Foxboro Channel A,B,C, & D X X i Test Panel l 587 E-23866-411-013 8 CE Reactor Protective X X f Sh. 4 System Schematic 4 23598 11405-E-404 B GHDR AI-66A Panel X X Sh. 1 Arrangement 23592 Il405-E-404 8 GHDR AI-66A Annunciator X X j Sh. 5 Arrangement 23599 Il405-E-405 B GHDR AI-668 Panel X X Sh. 1 Arrangement 23596 Il405-E-405 B GHDR AI-66B Annunciator X X i Sh. 5 Arrangement - 10475 E-23866-210-Il0 B CE Reactor Coolant X X System P & ID i 43313 Specification A OPPD Receiver Instrument X X i Sh. 524 Specifications i I I I Page 3 of 4 t --.-s -+., - -., _ _.,

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I ~- ' Appendix B-3-2 Rev 10/85 i [ ] Preliminary Design [X] Final' Design- [ ] Construction Package Fort Calhoun Unit No. 1 Station Location and Unit No. DRAWING LIST GSE TASK /MR # -FC-84-203 ' Steve Miller Design Engineer Date Drawing List Issued: 5/14/86 Revision 1 Drawings Incl. This File # Drawina # Issue # Vendor Description faE Transmittal 43066 CD-009A A OPPD Channel A Connection Diag. X X. $3067 .CD-0098 A OPPD Channel B Connection Diag. X .X 43068 CD-OllC A OPPD Channel C Connection Diag. X X 43069 CD-011D A OPPD Channel D Connection Diag. X X 12303 11405-E-72 A GHDR Tray & Conduit Layout X El. 989'-0" 40254 11405-E-73 A OPPD Tray & Conduit Layout X Sh. 2 El. 1013'-0" & 1101'-0" 12314 11405-E-92 A GHDR Tray & Conduit In Cont. X El. 994'-0"' 40251 Il405-E-93 A OPPD Tray & Conduit In Cont. X Sh. 2 El. 1013'-0" i .22700 E-4055 A OPPD Cable Risers to AI-66A & B X i AI-65 A & B l 1 23315 D-4132 A OPPD Details for Cond. Entering X AI-196, AI-197, AI-198 and AI-199 l 43105 C-4160 A OPPD Cable Block Diagram (DSS) X i O ~ Page 4 of 4 h

m-z. 1 , --+ +a a m., m h O 1 l l ATTACHMENT B , O l s I t I i O-

l - d' a 4 - CSE Form 42-2031 WORK ( T ~.ER 6 - FC Stction w.o go. 1994 1 - FC Storeroom OMAHA PUBLIC POWER DISTRICT 1 - NO Station a l No. 66000 Nuclear EST. NO 4ISION Fort Calhoun Station LOCATION MR-FC-84-203 ro,_ ATWS Rule Modifications This work order covers labor and material costs for installing a diverse reactor trip system. OAft w 0 NO Stem 6124 1994 22 accouwe "o'"" '00 "o"#M HIIHmtNM stoHs Numttt l{[M NUmste on CO$f QM CeQat sa( ge atm ;t at '4'20 Pressure Transmitters ' 4 20.000 8 i Sinnal Processinn & Comparator I 8 Circuitry (Foxboro Spec 200) i I ' lot l12.000 1 8 Lockout Relays 8 2i 1.000 I Kev-lock Switches 8 I 6; 5.000 I l i Suoervisorv Relays 8 i 2* 600 8 l Reactor Trio Breakers w/ Cert. i i Ir 2 5.000 I l 8 Matrix Boxes i i I' 2 500 e i 8 Misc. Cable. Indic. Lichts etc. 8 I : lot

  • 5.000 8

I I Seismic conduit Supports Ofati.) 1 I slot 5.000 I I I I I I 1 l l 1 1 1 1 1 1 1 1 1 9 l 1 i l i e i e i i i i 1 e i TOTAL MATERIAL 1 1 I 54.100 1 I TOTAL LABOR 2000MH 0 $30/hr 60.000 8 i OVERHEAD COSTS 0 30% 8 34.230 i I TOTAL I e I I I i 148.330 i COMPLEilON REPORT

l. PROPERTY ADDiflONS h48,336 PREPARED av lS. Miller #T DATE DATE STARTED
2. REMOVAL COST DATE COMPttiED
3. S ALVAG E CHECKED Qg

[ 4 4 DATE flNAL CHARGE 5 4 NET COST ti.2-si I48,330 DONE A5 PLANNED

5. SERV., METERS & if R5 g'P P R O V,E D

'E NOTE ON REVERSE $10E 6 SUNDRYACCT5 ENGINEERING .N E Di

7. PROJECT COST 5 :4.s.e> l48.330 FINANCIAL
8. circuli NO.

DATE flELD CHECKED 9 ATLAS PAGE APPROVED ENGR. Olv. 10 15 Bill 1NG REQLNED? _g DATE CLEARED AUTHORIZED \\ { DATE APPROVED ACCf. DEPT. 6f[Offb m

-,--.--e-- aaa A-na.- ---,-a- -a-, m,m-a ---a&, m a-a aea-. &a_- J ,-.s + O i l 3 ATTACHMENT C O I l O . - - e

.i: N V( MATERIAL LIST MR-FC-84-203 ATWS RULE MODIFICATIONS OUANTITY DESCRIPTION .C.QE P.O.#/ STORES 4 Foxboro Model N-2AI-I2V+P with CQE S011618 N-ECEP-900ll Dual Input Converter for 4 to 20mA Input Conversion to 0 to 10 Volts with Test Plug 4 Foxboro Model N-2AP+ ALM-AR Dual CQE $011618 Absolute Alarm Card and Nest Module 8 Foxboro Model N-2AO-L2C-R with CQE S011618 N-ECEP-10273 Contact Output Isolator with DPDT Relay Outputs 2 Foxboro Model N-2ANU-D Nest CQE S011618 Unit for Mounting Spec 200 Modules 2 Foxboro Model N-2AX+DP10 Power CQE S011618 Distribution Component for D.C. Power to Nest Buses 2 Foxboro Model D1026WM CQE S011618 Wiring Harness 200'. Foxboro Model A3304BV Wire CQE S011618 fm Spec 200 Systems.

  1. 22AWG 200' Foxboro Model P0170BR Wire CQE S011618 for Wiring Spec 200 Terminals to Termination Blocks #16AWG 2

General Electric Type 12HEA61A223 CQE S012159 Lockout Relay 10 General Electric Type HGAlllJ2 CQE S012159 I 125VDC Relay i 4 Microswitch Keylock Switch CQE S013191 i P/N PTKEB2331C 2 Microswitch Keylock Switch CQE S013191 P/N PTKEB2332C

p. - ) 5 DO !@_t01T1 DESCRIPTION- [QE P.O.#/ STORES 2 Microswitch Switch CQE S013191 P/N PTSBC202C 2 Hoffman Type A20H16 ALP Limited C097373 Junction Box 4 General Electric EB-25 CQE 631.8521 12 Point Terminal Block 26 General Electric ET-16 Non-CQE Indicating Light 4 Bussman IB0002 2-Pole CQE Fuse Block 8 1 AMP Non Fuse CQE 4 10 AMP Non Fuse CQE O-4 Pressure Transmitter CQE S012551 0-3000 PSIG Rosemount Model 1154GP9RA 4 3-Valve Manifold CQE S012514 Anderson Greenwood P/N MlHS-3-N 4 Conduit Seal CQE S013186 Rosemount flodel 353C 2 Pressure Indicator CQE S013194 Foxboro Model N-257H-lK 2 Housing for Indicator CQE S013194 Foxboro Model N-2AX4H096 2 Retaining Bar for Indicator CQE S013194 Foxboro Model N-2AX+RB01 l l !!o i

.--4-a-a a-* u.. d--- .a.d. a hs A -.Aa h i O i i n ATTACHMENT D O } O

c C-e ese REPRINT *** C097373 UF/24/so 1 24515001 ts.tCTRIC FIXTURE & SUPPLY FORT CALHOUN STATION IOC6 N 20TH STREET FOMT CALHOUN, NEURASKA 68023 P.O. Sou 898 OOWNTOwN STATION

  • DesAHA NE 64IOl GEMEN A T INta STATION ENG.,

ANOMA. NN BEST NAV u.cos O NET 30 3OOFHASER S330/5. WILL CONFIRMING ORDER DO NOT DUPLICATE. GROUP I CONO!TIONS FOR SELLER REQUIRED FOR asR-FC-84-203 ATw5 RULE asODIFICATIONS eeeeee. N - lim!TED CRITICAL QUALITY ELEneENT FI E .. L.... NOTES: 1 A CERTIFICATE OP COesPLIANCE I5 REOu! RED w!TH THE SHIPesENT STATING ALL MATERIAL FURNISHED COesPLv5 WITH THE PURCHASE ORDER SGATERIAL DESCRIPTION. 2. OPPo*5 PURCHASE ORDER NuGISER 15 TO DE REFERENCED ON ALL DOCuuCNTS FOR TRACEASILIiv PURPOSES. I 2.00 EACH 888 306st 1994 OF 324200 122.72 5144.44 ENCLO5uRE ELECTRICAL NEMA TYPE 4 5 INGLE DOOR 20 x 36* x 6* HOFFesAN CATALOG NO. A2OH16 ALP MEED DATE : 08/15/86 PROesISE DATE : 08/sh/6e 2 2.00 EACH 888 306/t 8994 UT 324200 13.23 522.46 PANEL ELECTRICAL ENCLO50RE HorFMAN CATALOG #A20P16 NEED DATE : 0s/15/86 Prom!$E DATE a OutIS/86 FREIGHT PktPAIU AND ADO STAIE SALES TAX 3.5% 5.:t,o. f.td

O f% i' ~ s. j

      • REPRINT ***

5011619 l 08/12/86 1 27160021 FORSORO CO FCRT CALHOUN STAT!DN 86 NEPONSET AVE FORT CALHOUN. NE8RASKA 65023 FOXBCRO MA 02035 e BOS POLICE 402-536-4353 fox 50RO. MA SEE BELOM 8 0.00% 0 NET 30 306FRASER 5330/5 $1 L GROUP 1 CONO!TIONS FOR SELLER NRC REGULATION 10 CFR 21 IS APPL 1CESLE 10 TH15 00CastNT PACKAG1NG. SHIPPING. STORAGE. AND NANOLING SHALL MEET OR EXCEED THE REQUIREMENTS OF ANSI N45.2.2 LEVEL B MATERIAL MuST BE INSPECTED PRIOR TO PA* MENT REQUIRED FOR MR-FC-84-203 ATMS ROLE MCO!FICATION eeees x - CRITICAL OuALITV ELEMENT FILE e...e X - APPROVED VENDOR eeeee NOTES: 1. REFERENCE FOxBORO QUOTATION NO. 308-2077 OAYED 5/28/86 FROM FRED AVRES (fox 80RO) TO STEVE MILLER (OPPD). 2. ALL ITEMS SHALL MEET OR EXCEED GSEE SPECIFICATION GSEE-0801 FOR ENVIRON-MENTAL CONDITIONING. SEE PAR AGR APts 3.0 8 CF G5EE-0801. 3. A CERTFICATE OF COMPT!ANCE 15 RE-CUIRED MITH THE SHIPMENT FOR EACH UN!I FURNISHED. THE CERTIFICATE OF COMPLIANCE SHALL REFERENCE THE APPLIC-ASLE FOxBORO TEST REPORTS. 4 THIS MATERIAL / SERVICE IS NUCLEAR SAFETY RELATED. QUALITY PROVISION OF IOCFR50. APPENDIX 8. OR DISTRICT APPROVED EQUIVALENT SHALL BE APPLIED. 5. NONCOMPORMING ITEMS NOT IN ACCOR-CANCE MITH PHOCUREMENT SPEC. 5 HALL DE 5EE ENCLOSED FHEIGHT INP STATE SALES TAM 3.5% CCNTINuED

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      • REPRINT ***

$0:168 C8/12/86 2 2T160021 ~ tum60RO CO FORT CALHouN STA110N SG MEP3NSET AVE FORT CALHOUN, NEBRA5mA 68023 FOsSORO MA 02035 e 808 POLICE 402-536-4353 FOxBORO. MA SEE BELOW 8 0.00% 0 NET 30 306FRASER 5330/5. MILL REVIEmED AND APPROVED By THE DISTRICT PRIOR TO SHIPMENT. 6. CPPD*5 PURCHASE ORDER NUMBER IS TO BE REFERENCED ON ALL DOCUMENTS FOR TRACEASILITY PURPOSES. T. CURRENT OA/QC MANUAL ON FILE !$ REv. C. IF YOUR LATEST REVISICN O!FFERS. CONTACT OPPD PROCUREMENT QA. (402) 536-4822. 8. ALL CERTIFICATIONS AND TESTING REPORTS REQUIRED 8v THE PURCHASE ORDER AN3 GSEE-0803 ARE TO BE INCLUDED w!TH THE SHIPMENT OR PRIOR TO THE SHIPMENT. eeeeee 1 4.C0 EACH 888 WlwS4399's/ J06/1 1994 OT 324200 857.00 53423.00 CONVERTER DUAL INPUT 4 TO 20 NA INPUT CONVERSION TO O TO 10 VOLTS. ISOLATED INPUT w!TH ISOLATED 24WDC TRAN$ MITIER POmER SUPPLV. CUSTOM TERMINATION TEST PLUG ON INPUT FOR INSERTION OF TEST JACE. FOxBORO MOCEL NO. N-2Al-I2V+P w!TH N-ECEP-900tl. NEED DATE : 11/14/86 PROMISE DATE : 11/14/86 2 4.00 EACH 888 W199433957 306/8 1994 07 ?24200 655.00 52604.00 CARD DUAL ABSOLUTE ALAHM AND NEST MODULE RELAY CUTPUT CONTACTS RAIED 100MA AT 28vDC FOR REh!5TIVE LOADS. IwO INCEPEN-CENT ASSOLUTE ALARM FUNCTIONS. FOXBORO i MODEL NO. M-2AP+ ALM *AR. r I SEE ENCLOSED FREIGHT INF t STATE SALES tax 3.5% CONTINUED

y f'% [' $ O \\ b \\ ) 'v/ (,/

      • REPRINT ***

5011618 08/12/86 3 2716C021 tOA80RO CO PONT CALHOUN STATION 86 NEPONSET AVE FOkT CALHOUM. tatBRA5dA 68023 ru=80NO MA 02035 e hva PGLICE 402-536-4353 FOsuoNO. wa SEE BELCw 8 0.00% 0 NET 30 306FRA5Ek 5330/5. MILL NEED Daft : 11/94/86 kNOu!SE DATE : 11/14/86 { 3 8.00 EACH 888 wt99439957 306/4 1994 07 324200 5b0.00 544eu.Ou 150LATOa5 CONTACT OUTPUT. ACCEPTS 4 (FOUR) CONTACT INPUTS (FROM N-2AP+ A*" CADOS) AND HAS CUSTOu OPOT RELAY OUTPUTS r6., garH INPUT. DUTPut CCNTACTS RATEu 5A A6 12*.wAC OH 2avDC. ALSO RATED O.5A AT 125vDC. NLGO!*FS 2 UNITS OF mIOTH FOR MOUNTING. fox 80Ru NOCEL NO. N-2AO-L2C-R w!TH N-ECEP-40273. NEED DATE : II/84/u6 PRoutSE DATE : 11/14/86 4 2.00 EACH 885 m 994JuuS/ Job /t 1994 01 324200 3Je.Ou $6#2.00 fyhPESTUNITFORWOuMT!nGIN 1 SPEC 20u N-2E5 NUCLEAR RACW. PROVIDES MOUNTING FOR 10 UNITS OF w! Din CF SPEC 200 j kODULES PLUS ONE power DI5tRIBUTION MODULE. FOABCRO NODEL NO. N-2ANu-0. MEED DATE : 11/l4/86 PROMISE DATE : 31/14/a6 5 2.00 EACH 888 Wl994393SF 306/1 1994 07 324200 108.00 5216.00 1 ) POWER OISTRIBUTION COMPONENT FCR DISTRIBUTION OF *tSWDC AND -15VDC POwtR TO NEXT SUSES. USED IN RACK WITH uuLTI-NEST PCwER SUPPLV. fox 80RO MODEL NO. N-2AX+0Plc. { HEED DATE : II/14/86 PROW!SE DATE 4 11/14/86 4 SEE ENCLOSED PREIGHT INF STATE SALES tax 3.5% CoteTIhufD

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S012159 09/02/86 1 2847504T GENERAL ELECTRIC C0 FORT CALHOUN STATION 205 GREAT VALLEY PAREMAY FORT CALHOUN, NEBRASKA 68023 MALVERN PA 19355 306FRASER5330/,S$.fb BOS POLICE 402-536-4353 CESTINATION SEE BELow-7 0.00% 0 NET 30 .A GROUP I CONDITIONS FOR SELLER P AC KACI NG, SHIPPING, STORAGE, AND HANDLING SMALL MEET CR EXCEED THE REQUIREMENTS OF ANSI N45.2.2 LEVEL 8 NRC REGULATICM 10 CFR 21 IS APPLICASLE TO THIS DOCUMENT REQUIRED FOR MR-FC-84-203 ATMS RULE M3OIFICAT10N eeeeeee. K - CRITICAL CUALITV ELEMENT FILE X - APPROVED VENDOR eeeeeeee NOTES: 1. REFERENCE CENERAL ELECTRIC PRCPOSAL s265-44028 CATED 7/9/86 FRCM PAUL SCOERHOLM (CE) TO STEVE MILLER (OPPD). 2. THE REQUIREMENTS OF SPECIFICATION GSEE-0804 APPLY TO THIS PURCHASE ORDER. 3. A CERTIFICATE OF CONFORMANCE PER SPECIFICATICM GSEE-0804 PARAGRAPH 9.2 15 REQUIRED WITH THE SHIPMENT FOR EACH ITEM FURNISHED. 4 OPPD* S PURCHASE CROER NUMSER IS TO SE REFERENCED ON ALL DOCUMENTS FOR TRACEASILITY PURPOSES. 5. THIS MATERIAL / SERVICE IS NUCLEAR SAFETY RELAIfD. QUALITY PROVISION CF 10CFR50 APPENDIX S CR DISTRICT APPROVED ECUIV4 LENT SMALL SE APPLIED. 6. NONCONFORMING ITEMS NOT IN ACCORD-ANCE MITH PROCUREMENT SPEC. SMALL BE REVIEnED AND APPROVED BY THE DISTRICT ~ PRIOR TO SHIPMENT. 7. CURRENT CA/CC MANUAL CN FILE I$ SEE ENCLOSED FREIGHT INF STATE SALES tax 3.5% CONTINUED

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wt99442326 306/1 1994 07 324200 375.00 5:113.00 I 3.00 EACH SSS RELAYS Aux!LIARY GENERAL ELECTRIC TYPE HEA61A223 (125VDC) NEED CATE : 11/03/86 PRCMISE DATE : 13/03/86 wt99442326 306/1 1994 07 324200 207.00 52ASA.C0 2 12.00 EACH 888 RELAYS AUXILIARY GENERAL ELECTRIC TYPE NGA111J2 CENTURY SERIES (125vDC) NEED DATE : 11/03/86 PRCMISE DATE 88/03/86 i I SEE ENCLOSED FREIGHT INF STATE SALES TAX 3.5% l 53597.00 l

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5012514 09/17/86 1 11842502 Ah0E45C?e GREEMwCCD USA INC FCRT CAL 210cM STATIDM 5425 LDUTM RICE AVENUE FCRT CALHCuM. NEBRASWA E8023 NCuSTCM TX 77401 e SGS PCLICE 4C2-536-4353 CESTINATION SEST WAV O.00% 0 hET 33 306 FRASER 5330/N. NIM GROUP I CONDITIONS FCR SELLFR PACAAGIkG. SHIPPING. STCRAGE. AND HANDLING SMALL NEET CR EXCEED TnE REcu!REwENTS CF ANSI M45.2.2 LEVEL C mRC REGutATICM to CFR 21 15 APPLICASLE TO TMIS DOCuugNT E REQUIRED FOR MRTF h84 203 ATuS RULE NCOIFICATIONS

  • N x - CRITICAL QUALITV ELEMENT FILE K-

"INDIv! DUAL APPROVED e. MOTES: 1. CPPD'S PURCHASE ORDER NUMBER IS TO BE REFERENCED ON ALL 00CuuENTS FnA TRACEASILITY PURPOSES. 2. THIS NATERIAL/ SERV!CE 15 NUCLEAR 5AFETV RELATED. QUALITY PROVISION OF 10CFR50. APPENDIX 8. CR DISTRICT APPROV-ED EQUIVALEhi SMALL BE APPLIED. ~~ 3. NONCCNFORu!NG ITEMS NOT IN ACCORD-ANCE w!TH PROCUREMENT SPEC. SMALL BE REVIEWED AND APPROVE 3 SV TME DISTRICT PRICR TO SHIPufMT. ~ 4. CERTIFICATI0M5 IN ACCORDANCE WITH A5mE AMD CPPD SPECIFICATIONS ARE TO BE INCLUCED IN DOCUMENTATION PACKAGE. eeeeee REFERENCE OPPD INQUIRY NO. 6110 AND REQ. CM PURCNA5ING h0. 1027 OATED 9/15/86. FCS: HOUSTCN, TX t - 4.C0 EACH 888 wt9944382: 306/8 1994 07 324200 1500.00 56000.C0 SEE ENCLOSED FREIGHT INF STATE SALES tax 3.5% CONTINUED I

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      • REPRInf ***

10/13/86 3 27tECC21 FCASCRO CO FC4T CALHCUM STATICM 86 hEPon5ET Avt FORT CALHOum hESRassa 68023 FOasCRO mA C2035 BCS POLICE 432-536-4353 CESTIhAT!cg BEST way 0.00% 0 >ET 33 306 FRASER 5330/u!LLER >RC REGuLAT10s to CFR 21 15 APPLICASLE TO THIS DCCuwENT GROUP I CONDITICMS FCR SELLER PACEAGIh0. SHIPPING. STORACE. AND HAhCLING SMALL MEET GR EuCEED THE REQutREwENTS CF Ah5I h45.2.2 LEVEL 8 USE UPS SURFACE wHEmEVER FEASIBLE Im 70 La CR LESS PER FACEACE. nam. 233 LSS. TOTAL ALL PACEACES. FREIGHT InvCICES MILL SE SEnf to CPPD. 5623 HAumEv 51.. Cuana, mE E8102. ATTM: pu3. CALL LCCAL CFFICE FOR PICEUP. RECutRED FOR mR-FC-84-203 ATuS RULE MCOIFICATION A - CRITICAL QuALITV ELEMENT FILE x - APGR3vED VENDCR hCTES: 1. REFEREhCE F0mBCRO QuCTATICM NO. C308-2C51 DATED 9/t6se6 FRED AveES (FCmSORO) TO STEVE u!LLER (OPPO). 2. THE ASOVE ITEuS SMALL MEET CR ERCEED GSEE SPECIFICATIDM SETS-cos. 3. A CERTIFICATE cr LouPtIANCE Is RECUIRED w!TH THE SHIPuthi FOR EACH umIf FURNISHLD. 1HL CLRTItICAIL CF CCmPLIAhCE 5 HALL REFEREMCE THE APPLICABLE FCmBORO TEST REPCRT. 4 ALL CERTIFICATES AMD TEST REPCRTS ASSOCIATED mITH THE ITEmi FURNIS*tED SMALL BE SHIPPED PRICR TO CR WITH THE SHIPufMT CF THE N4TERIAL. s I 5. THIS MATERIAL IS NUCLEAR SAFETv RELATED. CuALITY PR3v!SIONS OF 5 HIP FREIGHT COLLECT STATE SALES TAX 3.5% Cor4T INeED

g-S (O ) ) 3 ~ s 10/IC/86 $013194

      • REPRINT ***

10/93/86 2 27360021 FOm3ORO CO FORT CALHouN STATICN 86 NEPONSET AVE FORT CALHouN. NE8RASEA 68023 e 'FORSORO MA 02035 BOS POLICE 402-536-4353 DESTINATION DEST wAv U.00% o NET 30 306 FRASEk 5330/ MILLER 10CFRSO APPENDIX B OR DISTRICT APPROVED EQu! VALENT SMALL BE APPLIED. 6. NONCONFORMING ITEMS NOT IN ACCORD-ANCE w!TH THE PROCUREMENT SPEC. SHALL BE REVIEWED AND APPROVED BY THE DISTRICT PRIOR TO SHIPMENT. 7. OPPO* S PURCHASE ORDER NUMBER IS TO BE REFERENCED ON ALL DOCUMENTS FOR TRACEADILITY PUNPOSES. 8. THE CURRENT REVISION OF F0x00kO'S OA/QC MANUAL ON FILE IS REVISION -C. IF YOUR LATEST REVISION DIFFERS. CONTACT OPPO PROCUREMENT QA. (402) 536-4622. wl99446600 306/1 1994 07 324200 465.00 5930.00 I 2.00 EACH 888 MODEL N-257H-l-K CODE CS-N/SRC INDICATOR WITH SINGLE POINTER w!TH TERMINALS FOR CONNECTION OF 0-tov 0C. SCALE PRINTED 1900-2900 PSIA. NEED DATE : 11/28/86 PROMISE DATE : 11/28/06 SHIP FREIGHT COLLECT SHIPPING POINT TO DESTINATION: MORE THAN 600 MILES USE PIE NATIONWIDE OR VELLow. LESS THAN 600 MILES USE ANA OR AMERICAN. CALL LOCAL TERM-INAL FOR PICNuP. FOR INTRASTATE OR INTRASTATE INTER-LINE CALL R&R APRESS 402-341-8300. SEND INVOICE TO OPPD-MMD. 162J HARNEW ST.. OMAHA. NE 68102. FOR FREIGHT ROUTING OutSTIONS CALL 402-536-4343. DOS CLAv80RNE. EXCEPTION TO THE ABOVE FOR INTRACITY DELIVERIES. w199446600 306/1 1994 07 324200 110.00 5220.00 2 2.00 EACH 888 SHIP FREIGHT COLLECT STATE SALES tax 3.5% CONTINUED l I

^ L. _ j h ~ l,. _ \\ & f (,, ,;,I E.. ? I ~ -:,~*-'.-- ;G,: e-y,,,- - ~st' ;Q. s a. ~ ,j, N. ,f. q_ e ,o 10/I4/88 .,4..Af - d

      • REPRINT ese

.. ;.. 5013194' ..e l; % ~ 10/13/86-3 27160021 s 'I e ,+ ~~ 'e0RT CALHOUN STATION FOXBORO CO -m. 86 NEPONSET AVE FORT'CALHOUN. HEBRASMA 68023 fox 80RO MA 02035

  1. ~

w 808 POLICE 402-536-4353 DESTIMATION BEL,T WAY -,, 0.00% 01, NET 3 L " 306 FRASER 53 3 0 / MI LI. E R s _ ~.. s' .s., MODEL N-2AX*H096 CODE C5-N/SRC HOUSING g. FOR MOUNTING ONE INDICATOR NEED DATE : 11/28/86 PROMISE DATE : 11/28/06 3 2.00 EACH 888 'W109146600 306/1 1994 07 324200-26.00 152.00 MODEL N-2Ax*RMCI CODE CS-N/SRC RETAINING ~ BAR FOP EACH-PANEL CUTOUT WITH A N-2AK*llO96 HOUSING NEED DATE : 11/28/06 PROMISE DATE : 11/28/86 w ) v e I e $ HIP FREIGili COLLECT . STATE SALES tax 3.5% 11202.00

~ O ATTACHMENT E O O l

[ GSE-B-2-2 Form l L PREPARED BY h/oh d l CHECKED BY enL & ' l APPROVED BY %Tieur. l SH. 1 CONT. ON SH. 2 Rev. 10/85 REV. a DATE iO!1/F6 l MR No. FC-84-203 l OMAHA PUBLIC POWER DISTRICT I d I IGENERATING STATION ENGINEERING SPECIFICATION FOR 3-VALVE MANIFOLDS CQE TABLE OF CONTENTS 1.0 SCOPE

2.0 REFERENCES

3.0 DESIGN REQUIREMENTS d 4.0 QUALITY ASSURANCE 5.0 HYDROSTATIC LEAK TESTING 6.0 CLEANING 7.0 PACKAGING, HANDLING, STORAGE & SHIPPING 8.0 DOCUMENTATION ll 4

  • &s}-

RANDEL E. $tn:: tEwis / g* [ is%, E5018 e \\' k. y ,il..V..i.... '*kk? w v

I V, 1.0 SGOPE This specification establishes the design, fabrication, inspection, testing, cleaning, packaging, documentation, and shipping requirements for 3-valve instrument manifold to be installed on the Diverse Scram System being implemented to comply with the " Anticipated Transient Without Scram" (ATWS) requirement. The vendor shall furnish N stamped valves in accordance with ASME B and P.V. Code, Section III, Subsection NC Class II, 1983 Edition through the Summer 1985 Addenda. 2.0 EfEFfE_RENCES The design, construction, materials, and accessories for all valves shall be in accordance with, but not limited to, the following codes and standards. American National Standards Institute (ANSI) 2.1 B16.11 (1980) Forged Steel

Fittings, Socket Welding &

Threaded 2.2 B16.34 (1981) Valves, Flanged and Buttwelding Ends 2.3 N45.2.1 (1980) Cleaning of Fluid Systems and Components During Construction Phase of Nuclear Power Plants. 2.4 N45.2.2 (1978) Packaging,

Shipping, Repairing, Storage and Handling of Items for Nuclear Power Plants.

American Society of Mechanic Enoineers (ASME) 1983 Edition through Summer 1985 Addenda ASME Boiler and Pressure Vessel Code 2.5 Section II, Part A Ferrous Material Part C Welding Rods, Electrodes, & Filler Metals 2.6 Section III, NCA General Requirements 2.7 Section III, NC Nuclear Power Plant Components, Class 2 2.8 Section V Non-Destructive Examination 2.9 Section IX Welding and Brazing Qualifications O 2 L '

3 i Manufacturer's Standardization Society (MSS) 2.10 MSS SP-61 (1985) Pressure Testing of Steel. Valves Nuclear Reaulatory Commission '2.11 10CFR50 App. B Quality Assurance Criteria for Nuclear Power Plants 2.12 10CFR21 Reporting of Defects and Non-Compliance 3.0 DESIGN REOUIREMENTS 3.1 Eauipment 3.1.1 Form: 3 Valve Instrument Manifold ANSI B16.34, 2500 lb. class 3.1.2 Body Material: Stainless Steel ASME SA479 Gr. 316

3.1.3 Bonnet

ASME SA479 Gr. 316 Stainless Steel 3.1.4 Plug: Stainless Steel ASME SA479 Gr. 316 i 3.1.5 Stem Assembly: ASTM A276 Gr. 316 3.1.6 End Connections: Inlet (Process) - 3/8" 0.D. tube stub (SA213 Gr. 316SS) Outlet (Instrument) - Nipples with mounting Adapters (SA479 Gr. 316SS) 3.1.7 Seat: Integral Stainless Steel

3.1.8 Packing

Grafoil GTR

3.1.9 Mounting

-Two(2) Mounting Adapters (" Footballs") 3.1.10 Handle: ASTM A47 Gr. 32510 3.1.11 Packing Nut: Stainless Steel ASTM A479 Gr. 316 l 4 t 3 l l - _ - =

.. - ~. ~ ~ c ' 3.2 Desian Conditions )

3.2.1 Pressure

2500 psia

3.2.2 Temperature

700*F 3.3 Service Conditions The valves are required for the Fort Calhoun Station and wil'1 be installed for the Diverse-Scram. System located inside the reactor containment building under.the following conditions: l 3. 3.1' Fluid Conditions:- i-(A) Fluid - Water Radioactivity - Yes i-Pressure - 2100 psia i Temperature - 642.8'F-(B) Water Chemistry-Boron 0 to 2500 ppm pH 4.5 to 10.2

~

Conductivity < 40.0 umhos/cm t i-Chlorides 5 0.15 ppm Oxygen 10.10 ppm Fluorides 10.10 ppm Lithium 1.0 to 2.0 ppm Hydrogen 25 to 50 cc STP H /Kg H 0 2 2 Ammonia 10.50 ppm Suspended Solids 10.50 ppm Activity 1100E l Hydrazine 1.5 x Measured 02 Conc. (<400*F) (max. 20 ppm) 3.3.2 Valve External Ambient Conditions: (A) Normal Operating Conditions Temperature 40 to 122*F Relative Humidity 15 to 100% Radiation IR/HR Pressure Atmospheric (subject to 60 psig [- test every 3 years) s 4 i ,a - - Le ^' .,,.,,_,-.,,_,-,,-.,---,,---,n.,-.---- .-v-m-,.7,,,,, ,-,,...,-,-,.-.--..--,,.-.,,,,,,,,_,,.---,--,-._,.~n,

i Service Conditions (Continued) (B) Accident Conditions These valves shall be capable of functioning for a minimum of 100 days under the following accident environment conditions which may happen once during the service life of the valves: Temperature 305'F Air. Partial Pressure 19 psia Steam Partial Pressure 55 7 psia 4 Radiation 10 R/HR These conditions will' exist for approximately 20 minutes and will then be continuously and slowly reduced. Under accident conditions, the containment may also be contin-uously sprayed with a boric acid solution containing at least 1700 ppm boron. 3.4 -Seismic loadinas The valve manifolds shall be capable of withstanding a seismic -(]" ' applied simultaneously with 3.0 g in the vertical direction acceleration of 4.5 g in each of two horizontal directions s applied at the pipe connections. This shall be considered as a design loading per ASME Boiler and Pressure Vessel Code, Section

III, Division 1,

Nuclear Power Plant Components. The lowest i natural frequency of vibration of each assembly shall be greater than 33 Hz. 3.5-Weldina Welding shall be in accordance with ASME Section IX and ASME II, Part C. 3.6 Service life Valves conforming with this specification shall be designed for a service life of 40

years, considering normal valve maintenance.

3.7 Identification 3.7.1 Each valve shall be furnished with a nameplate per NCA-8200. Code symbol and class shall be applied with the concurrence of the authorized nuclear inspector upon completion of the required examination and testing. p 3.7.2 . Vendor shall provide 1 1/2" stainless steel tags with purchase d order number, MR number (MR-FC-84-203), and tag number.(RC-392 ' to RC-395) stamped on the tag for each valve manifold. 5 i

t y 4.0 OUALITY ASSURANCE Valves furnished under this specification shall be subjected to the requirements of a Quality Assurance Program complying -with ASME III, NCA-4000 and 10CFR50 Appendix B. 5.0 HYDR 0 STATIC LEAK TESTING 5.1 The water used for hydrostatic testing shall be demineralized and have a chloride content less than 1 PPM. The water temperature shall not exceed 125'F. 5.2 A shell leakage test shall be performed per MSS SP-61. The test pressure shall be maintained for a minimum of ten minutes. There shall be no evidence of leakage except stem packing leakage during shell test shall not be cause for rejection. The valves shall not be disassembled prior to seat leakage test. 5.3 The seat leakage test shall be performed per MSS SP-61. The test pressure shall be for a minimum of one minute. The seat leakage shall not exceed the maximum allowable leakage specified in MSS SP-61. No stem packing leakage is allowed at this pressure. V i 6.0 CLEANING Parts which may be exposed to the flowing media shall be cleaned free of oil, grease,

scale, rust, organic matter, loose particles and other foreign material in accordance with ANSI N45.2.1, Class C.

J 7.0 PACKAGING. HANDLING. STORAGE & SHIPPING Valves shall be packaged for shipment and storage in accordance with ANSI N45.2.2, Level C. 8.0 DOCUMENTATION 8.1 The following documents shall be submitted to the District for approval prior to proceeding with work: Document Quantity 8.1.1 Outline Drawings 1 Reproducible, 2 Copies 8.1.2 Operating, Installation, & Maintenance 2 Copies 8.1.3 Procedures 2 Copies O-6

1 ,. C' 8.2 The following documents shall be submitted for " Record", " Files", or "For Information Only" and do not require District approval: Document Quantity 8.2.1 Final Certified Drawings 1 Mylar, 10 Prints (As-Built) 8.2.2 Final Operating, Installation, & Maintenance Manuals 8 Copies (As-Built) 8.2.3 NDE Reports 5 Copies 8.2.4 Seismic Analysis Report 5 Copies (Including Calculation and/or Test Report) 8.2.5 Hydrostatic Test / Seat Leakage 5 Copies Test Report 8.2.6 Certified Material Test Reports 5 Copies s 8.2.7 Code Data Report 5 Copies 8.2.8 Certificate of Conformance to This Specification and the 5 Copies QA Manual CERTIFICATE OF CONFORMANCE The Vendor shall include with any shipment, a Certificate of Conformance which contains the following information: 1. District's Purchase Order Number. 2. Identification of the material or equipment (e.g. name, catalog number, equipment tag number, serial number, etc.). i 3. Identification of the specific procurement requirements met, such as specifications, including any approved deviations. 4. Identification of any procurement requirements which have not been met, together with an explanation and the means for resolving the nonconformances. ( O 7 L

., 2.; '. _s i ~ 5. Approval by. an individual who is responsible for Quality Assurance ,and whose. function.and position.are described in the Vendor's QA Program. ~ All substantiating documentation such as CMTR's, inspection reports,- test reports, etc. shall be included with the Certificate of Conformance. All documentation. shall be accompanied by a letter of transmittal. The letter. of transmittal'shall include the following information: a. Purpose of transmittal ~b. List of documentation transmitted with the revision designation. All documentation including drawings shall contain the following information: a. Station name; Fort Calhoun Station b. bistrictPurchaseOrderNumber-c. Modification Request Number; MR-FC-84-203 1 i i i Il' !l0 8

  • GSEE-0803 Page 1 of 9 Revision 0 (J^')

Date 7-lo-80 N (This stipersedes our Specification # GSEE-0701) SPECIFICATION #GSEE-0803 General Requirements for CQE (Class IE) Electrical Equipment Required for Use Inside Reactor Containment FORT CALHOUN UNIT #1 O Prepared By [tJv /o _ /9fo Checked By M, ? teo I-c /pc . _. - -,g/,'//_#_/ 7- /M <;'e' Approved By [ [ Generating Station Engineering Section Omaha Public Power District 1623 Harney Street ] Omaha, Nebraska 68102 i \\

I REVISION SHEE,T NO. GGE-A-9-7 FORM DESIGN DOCUMENT NO. C' S E E - 0 9 0 3 REY. 3/79 [w PAGE f DESEN DOCUMENT TITLE : S PE C IF/c AT/04/ 65EE dGo3 y CONT ON PAGE PREPARED APPR OVED RE Y. DESCRIPTION / PURPOSE (flR #) Na BY BY ,l G]// CHANQED IU Y E Q sfA 'r'G O NRWARDN DOS 6 Fa4 A sassomsar Lomraa Assos rus Floon A.nast-FRotn 3 x IO& RAO$ 70 2 x10 ?AADS (PARAGRApti 3.02.s f.I* ~b ' 9 ~30-8f AJJcJ Rcf. c.a; des t o p.a.eng e.ph 2. 0 I. C onple t ely re vis cJ p.s.tr = gr*th 2. 0 2.=.* d

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GSEE-0803 Page 2 of 9 ,_ ~ Revision 0 I CONTENTS 1.00 SCOPE 2.00 CODES AND STANDARDS 3.00 SERVICE CONDITIONS 4.00 SEISMIC REQUIREMENTS 5.00 QUALITY ASSURANCE PROGRAM 6.00 QUALIFICATION REQUIREMENTS 4 7.00 IDENTIFICATION TAG 8.00 PACKING AND SHIPPING i 9.00 DRAWINGS AND DATA BY VENDOR 4 9.01 Drawings and Manuals For Approval 9.02 Certified as-built drawings and Q/A Documentation by the Vendor 9.03 Information to be furnished with the proposal 10.00 SHIPPING OF Q/A DOCUMENTATION AND DRAWINGS ATTACHMENT 'A' PROPOSAL DATA 4 i i e P !O ,a-- ---.n,,, ~...,,r --._r-

  • GSEE-0803 Page 3 of 9 Revision 3

[U 1.00 SCOPE 1.01 This specification details the general requirements applicable to all "CQE" (Class IE) items (equipment), so identified on their purchase orders / specifications. The scope of this document un-less noted otherwise on the purchase document is limited to "off the shelf" items required for use inside the reactor containment. 2.00 CODES AND STANDARDS 2.01 The following is a list of codes and standards referenced in this specification. If there is a conflict between any of the refer-enced documents and this specification, the matter shall be re-ferred to the District. IEEE 323-1971/1974 Standard for Qualifying Class IE Equip-ment for Nuclear Power Generating Stations IEEE 344-1971/1975 Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Station O \\~ / 10 CFR 50 Quality Assurance Criteria for j Appendix B Nuclear Power Plants ANSI N45.2.2 Packing, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants Appendix C IE Bulletin 79-01B Environmental Qualification of Class IE Equipment (issued by NRC) Reg. Guide 1.89 Qualification of Class 1E Equipment 2 for Nuclear Power Plants Reg. Guide 1.100 Seismic Qualification of Electric Equipment for Nuclear Power Plants O. ,m-

GSEE-0803 Page 4 of 9 Revision 2 O^- 3.00 SERVICE CONDITIONS The equipment is required for Fort.Calhoun' Nuclear Power Plant,. and will be installed inside reactor containment. The equipment shall be suitable for operation in normal and accident service conditions defined below. 3.01 Normal Service Conditions: Normal service conditions are as defined below: Temperature 40*F to 122'F Humidity 15 to 100% Radiation 1 R/HR Pressure ' Atmospheric (See 3.01.1) 3.01.1 The above temperature and pressure conditions will be maintained in the containment for.most of the time. However, once every three years the containment is subjected to leak rate test. During this test, the pressure is increased to 60 psig and is maintained at this level for three (3) days. The manu-facturer should provide information if this will have any impact on the equipment. 3.02 Accident Service Conditions: The equipment shall be suitable for the following accident environment conditions which may occur once during i the service life of the equipment. !~ _The testing shall be' done per IEEE-323-1974 (See Section 6.0 also) as modified by Reg. Guide 1.89. 3.02.1 Accident conditions for the equipment are as follows: a) Temperature and Pressure Per profile provided in Figure #1 b) Integrated Radiation Dose Expected dose for life of Plant 1 R/HR/40 years Accident dose Gama Radiation 2x107 Rads Beta radiation accident dose 2x10s Rads c) Boric Acid Spray 2500 ppm boron chemical i spray buffered with sodium hydroxide for a ph of 9.0 at 0.6 4 GPM per square foot i 4.00 SEISMIC REQUIREMENTS I 4.01 The equipment is required to be seismically qualified per IEEE-344-1975 and Reg Guide 1.100. 4.02 The manufacturer shall furnish copies of the test results and/or analysis showing test spectrum or ZPA level.

O-i

e-e e

.__..,.,,w._m.--., .-.--_y,--mm----y w--,-__.=_w,------

I r n u. N oo8d FIGURE 1 TEST PROFILE I I i i i i i i i i i i i e i I I i on i i i T ii ii i ii, i i ii END CHEMICAL SP, RAY-- t t i- - y - t 160 + -r - 1 - e -- 3 - r-l t I i i f I t 3 t I I I l l l l l 120 -- i F - i - r 1 - r -r t --r - 1 e l t f f f f A I I I I I I I I 80 + - i- - 4 F J-- F -F + --F - 4 J-- L - t - J I I I I I I I I ] I I I I I I i 4g .g .. 4 _ _.p .. 3 _ c 4 _ q _..p a.. p _s _ + .s _4 I i I I I I I I I I I i t t t t Ng gg glg E = 2500 PPM BORON mo mm m* BUFFERED WITH SODIUM Q oo oo HYDROXIDE P.H. 9.0 v 4. o8 m e c. oo

  • f ceam svarum UM b$

cgr TEST PROFILE FOR nm ELECTRICAL EDU3PMENT IN

  • t21 CCNTAINMENT a m.rilir P.f.

N Fit F titMFW 71474 OMA#M PUBLIC POWDI DISTRICT I OMAHA,f( BRA $KA i O O O

cr N O LL DO,bo FIGURE 1 TEST PROFILE i m d t.d i a i i i i i i i i i i i ao> i i O <L Lij i i i i i i i i i i i i i i i i i i i i

  • ) Q. T r

r r'- r- 'r-T- T- -' T- -' t-7- 7-7 -- 7-7- 7-2- a i i I 5 I 3 5 L I I I y 3 3 400 r r-T 2 -' t-360* F. 32.5 PSIG, --. f- - BEGIN CHEMICAL SPRAY *, 360 - r-r-r--r-r- -r-t 2-i i i i T--- -t---- i i i i e i . T-- T- T- "'- T'-' i i ~ 305* F. 60 PSIG 20 MIN. -- i i i 320 r\\ ---r---r---r---r-- -r r - -r -r- - r t-t - t - -- -r - -r - 5 1 E 3 5 5 I E I I I 5 5 I 5 g h 5 I ~'Y~'~Y h ~ h h 8 5 5 g h a j g Lij T MO- -r t t-S -l-r -t-- 240' F. 25 PSIG 30 MIN. i i 5 g ~' I h 3 I 5 h I T I 5 a y s 5 5 4 I e U E v v s a g g T 240 r - -r--- t t- - -r - - t-4- ih--t-200* F.100% RH E i i i i E 8 e a e gI I g I 3 3 1 p 200 r l l 5 I ~Y l F i 5 8 Y i a e 5 i-i r r - -r 5 g ) 3 I I I I~ T v v v e ENb CHEMICAL SPRd 160 r r r r - -r r---r- -r-- - t- -t- - +- 4-4- 4-4- 120 - -r r - -r r -r - -r -r t - +- +- 4-4- 4-4- s g g i g e 1 i +- i 80 - -r r - -r - -r - -r -+-- + + 4-4- 4-4- 4-i e ^ i ? 3 a 40 - -e r - -e - -r - -r -+ -+-- - +- + 4-4- d-d- - a- - a-i O. I NN NN N 2500 PPM BORON i mm mm BUFFERED WITH SODIUM o to e eo HYDROXIDE P.H. 9.0 O e to ee es 00 N LO MO MM 9.W $%'% W " ~~

- GSEE-0803 Page 6 of 9 Revision 2 O 5.00. QUALITY ASSURANCE PROGRAM (V 5.0111ThCeiLi'pment Tshalf 6e~ subject to.the requirement's of' Quality 1 , ~, .._.. --- Assurance program complying with 10 CFR 50 Appendix B. 63)0' QUALIFICATION REQUIREMENTS 6.01 [he equipment is to be qualified per IEEE-323-1974 as modified by Reg. Guide 1.89 and IEEE-344-1975 as modified by Reg. Guide 2 1.100. Alternatively, if agreed to between the Vendor and the District prior to issuance of the purchase order, the equipment may be qualified per -IEEE-344-1971 provided the following re-quirement is met. 6.02 If the equipment is not qualified per IEEE-323-1974 and IEEE-344-1975, or was not tested for any of the service conditions speci-fled in this specification, the vendor shall identify the mater-ials susceptible to aging effects and shall furnish a schedule for periodical replacement of the equipment and/or materials if applicable. If testing to meet this specification is in progress, .sn estimated date of availability of test reports should be pro-vided. 6.02.1 This may be done per the guidelines provided in Appendix 'C' of IE Bulletin #79-01B. O 7.00 IDENTIFICATION TAG V 7.01 Identification number assigned by the District shall be marked on the device or package. If no identification number is assigned, the package shall be marked with District's purchase order number and item number. 8.00 PACKING AND SHIPPING 8.01 Packing, shipping and handling of this equipment unless otherwise specified, shall meet Class "B" requirements of ANSI N45.2.2. 9.00 DRAWINGS AND DATA BY VENDOR 9.01 Drawings and Manuals Unless otherwise noted on the purchase order / specification, the vendor shall submit to the District, where applicable, one (1) direct reading sepia or three (3) copies of all prints, equipment drawings, diagrams, and catalog cutouts, etc., for Engi s ap-proval. The certified drawings and data shall be furnished in the follow-ing categories: a. ' Outline drawings of assembled equipment b. ' Schematic / Elementary diagrams c. Interconnecting wiring diagrams d. Installation, maintenance and operation instruction books - e. Testing and calibration procedures, wherp applicable. 1 ~

- GSEE-0803 Page 7 of 9 Revision 2 m The certified drawings for the Engineers approval shall be made' available to the District. as soon as practicable, but not later than thirty (30) days after the Purchase Order is issued. Each submittal shall be accompanied by a letter of transmittal containing the following information: 7 .a. Station name (Fort Calhoun Unit #1) b. Drawing. number 4 c. Title including equipment name, contract number, and i District task number t d. Purpose of drawing submittal The Vendor shall permanently note the District's contract number or purchase order number, description of equipment on all draw-ings. 9.02 CERTIFIED AS-BUILT DRAWINGS AND Q/A DOCUMENTATION BY VENDOR. i 'At the completion of the delivery, the vendor shall furnish the following documents, for District's permanent records. 9.02.1 Q/A DOCUMENTATION TO BE FURNISHED BY THE VENDOR l The manufacturer shall furnish documentation to prove valid-ity of the data published in manufacturers catalog and/or to i, O prove conformance with the requirements as specified in the purchase order / specification. 1 i The data shall be furnished in triplicate and presented in an organized and auditable form as required per IEEE 323-A 1974 or IEEE 323-1971 as modified by Reg. Guide 1.89. /2\\ \\ 4 As a minimum, the documentation shall contain the following: a. Type test report or analysis to verify parameters such E temperature rise of coils, operating characteristics 2 vs. ambient temperature and other known degrading in-fluences where appropriate. i b'. Production test report, to verify that the equipment 4 conforms to data published by the manufacturer and/or F as specified in the purchase order. i c. Statement regarding minimum qualified life or material analysis per the requirements of paragraph 6.02. j d. Maintenance requirements. e. Special installation and storage requirements. NOTE: If any of the above information was furnished to OPPD i against any other purchase order, the vendor may fur-nish a certificate of conformance and refer the docu-ment furnished with earlier purchase order. l t I

  • GSEE-0803 Page 8 of 9 Revision 2

.,_s) 9.02.2 DRAWINGS AND MANUALS: (-- \\_./ (a) One (1) wash off three mil mylar of all certified drawings. NOTE: This requirement is not applicable. for small devices such as relays and switches, etc. (b) Three (3) copies each of the handbooks instruction and maintenance manuals, etc. Handbooks shall possess suf-ficient details and. clarity to enable the owner's tech-nicians to understand, operate, and maintain the equip-ment and to identify replaceable parts, all in an effec-tive and an expeditious manner and without having to resort to extensive, unguided resea'rch through numerous other items of documentation. 9.03 Information To Be Furnished With The Proposal The bidder shall submit with the proposal a complete description of the equipment and devices offered and the information request-ed in Attachment 'A'. 10.00 SHIPPING OF Q/A DOCUMENTATION / DRAWINGS 10.01 One set of Q/A documentation and as-built drawings shall be ship-ped with the equipment. Remaining sets of Q/A documentation and

()

drawings unless noted otherwise shall be addressed to: Department Manager ( )* Generating Station Engineering Omaha Public Power District j 1623 Harney Street Omaha, Nebraska 68102 l i j O

  • Information to be provided by the Design Engineer.

l

s. - GSEE-0803 Page 9 of 9 D. Revision 2 -ATTACIDfENT 'A' D 'GSEE Specification //GSEE-0803 Bidder PROPOSAL DATA OPPD Inquiry Number a) Qualification status of the equipment offered.* [] Qualified per IEEE 323-1971 [] Qualified per IEEE 323-1974 [] IEEE-323-1974 Testing in progress [] IEEE-344-1974 Testing in progress [] Qualified per_IEEE 344-1971** [] Qualified per IEEE 344-1975** [] Not qualified Date at which test reports will be available b) Service conditions for which the equipment is qualified Temperature Pressure Humidity Radiation Level c) If the equipment is not qualified per IEEE-323-1974 and IEEE-344-1975 ~, attach an analysis on aging as required per para. 6.02 d) Schedule for furnishing Q/A Documentation. e) Promised delivery date. f) Qualified life. g) Any periodic maintenance required to maintain the qualified

life, h)

Catalog cuts _ (if available) i) Can the equipment function when submerged in radioactive water? j) Any adverse effect due to containment leak rate test? (See paragraph 3.01.1) k) Any exceptions taken to this specification or specifications out-lined in purchase order / specification and statements of explana-tions for the exception. Check the applicable blocks. Attach test response spectra, if available.

3 i - -s /(',,) GSE-B-2-2 Form l PREPARED BY lm L l CHECKED BY,-4 /m NWu -/i<- l APPROVED DY' 6 r rrt /, /A rs' SH. 1 CONT. ON SH. 2 Rev. 10/85 l REV. 6 DATE e/////'P/' MR No. l / OMAHA PUBLIC POWER DISTRICT I ' GENERATING STATION ENGINEERING ELECTRICAL TECHNICAL SPECIFICATION ETS-001 CQE ELECTRICAL EQUIPMENT LOCATED IN A MILD ENVIRONMENT TABLE OF CONTENTS 1.0 SCOPE 2.0 CODES, STANDARDS, & REGULATIONS 3.0 SERVICE CONDITIONS Os i 4.0 SEISMIC REQUIREMENTS 5.0 QUALITY ASSURANCE PROGRAM 6.0 QUALIFICATION REQUIREMENTS 7.0 IDENTIFICATION i 8.0 PACKAGING & SHIPPING l 9.0 DRAWINGS & DATA BY VENDOR ATTACHMENTS A. REQUIRED RESPONSE SPECTRUM (RRS) [] B. EQUIPMENT TECHNICAL REQUIREMENTS l [] C. SAMPLE CERTIFICATE OF COMPLIANCE 1 0 ed

i 74 U ETS-001 1.0 SCOPE 1.1 This specification details the general requirements applicable to all "CQE" (Nuclear Safety Related) electrical materials, components, and equipment purchased for use in a mild environment at the Fort Calhoun Station. 1.2 This specification also addresses the general requirements for environmental and seismic service conditions, documentation, quality assurance, packaging and shipping. Special technical requirements, where necessary are provided in Attachment 8. 2.0 CODES. STANDARDS AND REGULATIONS The equipment shall conform and be designed in accordance with the latest applicable standards of the American National Standards Institute, Inc., (ANSI), Institute of Electrical and Electronic Engineers, Inc. (IEEE), the National Electrical Manufacturers Association (NEMA) and the Instrument Society of America (ISA). In addition, the following standards shall be applicable: O oeeement Editien Titie IEEE 323 1974 IEEE Standard for Qualifying Class (as modified per IE Equipment for Nuclear Generating R.G. 1.89) Stations IEEE-344 1975 Recommended Practices for Seismic (as modified Qualification of Class IE Equipment per R.G. 1.100) for Nuclear Power Generating Stations R.G. 1.89 Qualification of Class IE Equipment for Nuclear Power Plants R.G. 1.100 Seismic Qualification of Electrical Equipment for Nuclear Power Plants ANSI-N45.2.2 Packing, Shipping, Receiving, Stor-age, and Handling of Items for Nuclear Power Plants 10CFR50 Quality Assurance Criteria for Appendix "B" Nuclear Power Plants and Fuel Reprocessing Plants-Note R.G.: Regulatory Guide O 2 REV 0 9/86 1

\\m-) ETS-001 3.0 SERVICE CONDITIONS 3.1 Environmental The equipment specified herein shall be suitable for operation under the following conditions: Temperature 40*F to 122*F Ambient Humidity 15 to 5% Radiation 1 x 10 Rads TID Electrical 1 x 10 Rads TID Electronic Pressure Atmospheric 3.2 Electrical Specific electrical requirements are provided where necessary in Attachment B. Where equipment is specified by manufacturer's catalog number, the manufacturer's published electrical ratings are acceptable. /'^ 4.0 SEISMIC RE0VIREMENTS d 4.1 The equipment shall be seismically qualified for Class IE use per IEEE 344-1975 as modified by Regulatory Guide 1.100. Seismic testing shall include: a. A low level resonance search to identify resonant frequencies. b. A multi-axis, multi-frequency shake test. The Test Response Spectrum (TRS) shall envelope the Required Response Spectrum (RRS) l as provided in Attachment A. 4.2 Exceptions to this test method may be acceptable provided they are justified by the vendor and approved by the District. 5.0 OVALITY ASSURANCE PROGRAM 5.1 The design, fabrication, and testing of the equipment shall be subject to the requirements of Quality Assurance Program complying with 10CFR50 Appendix B or District approved equivalent. 6.0 OVAliFICATION RE0VIREMENTS 6.1 The equipment shall be qualified for Class lE use per*the requirements of IEEE 323-1974 as modified by Regulatory Guide 1.89. ' O ~ 3 REV 0 l 9/86

4. i s V ETS-001 7.0 IDENTIFICATION 7.1 The identification number assigned by the District shall be marked on the device or package. If no identification number is assigned, the package shall be marked with the District's purchase order number and item number. 8.0 PACKING AND SHIPPING 8.1

Packing, shipping, and handling of this equipment unless otherwise specified, shall meet Class "B" requirements of ANSI N45.2.2.

9.0 DRAWINGS AND DATA BY VENDOR 9.1 Approved Drawings If requested on the purchase order the vendor shall submit to the District three(3) copies of equipment drawings, diagrams, and catalog information for engineers approval. The drawings and data shall be furnished in the following categories where applicable: a. Outline drawings of assembled equipment, b. Schematic / Elementary diagrams. c. Interconnecting wiring diagrams, d. Installation, maintenance and operation instruction books. e. Testing, and calibration procedures, where applicable. The drawings for the engineers approval shall be made available to the District as soon as practical, but no later than thirty (30) days after the purchase order is issued. 9.2 Drawings and Manuals Unless otherwise noted on the purchase order, the vendor shall furnish the following documents to the District on completion of delivery: a. One(l) wash off three-mil mylar of all applicable drawings. -outline drawings -schematic / elementary diagram -wiring diagrams b. Three(3) copies of all installation, maintenance, and operation manual s. O 4 REV 0 9/86

ETS-001 9.3 QA Documentation to be Furnished by the Vendor At completion' of delivery, the vendor shall furnish documentation to prove conformance with the requirements specified in the purchase order and this specification. The data shall be furnished in duplicate and presented in an organized and auditable form, as required per IEEE-323-1974. As a minimum, the documentation shall contain the following: 4. A Qualification Test Report documenting testing and analysis performed to verify seismic and environmental qualification. b.- A Certificate of Compliance confirming that the equipreent meets the requirements of the purchase order, this specification and the applicable Qualification Test Report (s). A sample Certificate of Compliance is provided in Attachment C. c. A statement regarding qualified life of the equipment and all maintenance, installation, or storage required to maintain qualification of the equipment. 10.0 SHJfPING OF OA DOCUMENTATION / DRAWINGS 10.1 One set of QA documentation, manual s, and as-built drawings shall be shipped with the equipment. Remaining sets of QA documentation, manuals, and drawings unless noted otherwise, shall be addressed to: Department Manager - Electrical Generating Station Engineering Omaha Public Power District 1623 Harney Street Omaha, NE 68102 8 O 5 REV 0 9/86

4 ETS-001 ATTACHMENT C CERTIFICATE OF COMPLIANCE VENDOR:- -0 PPD PURCHASE ORDER: VENDOR MODEL NO.(S): i VENDOR SERIAL NO.(S): h This Certificate of Compliance certifies that the above referenced material j meets the requirements of the referenced OPPD Purchase Order, Specification i ETS-001 "CQE Equipment-Located In A Mild Environment", and the following test report (s): l Test Report Number, l. Date, and Revision The vendor agrees that OPPD or its authorized representative can review the documentation upon which the qualification determination is based. Submittal of a test report with the vendor proposal is an acceptable method of allowing OPPD documentation review. OPPD will not divulge propriety vendor information l to sources other than OPPD contractors. l l Authorized Representative I 4 Title i Date io REV 0 j 9/86 g

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SUMMARY

OF DISTRICT'S POSITION 4.1'(Continued) CR Control Room EDG Emergency Diesel Generator Emergency Operation Facility EOF Emergency Operating Procedures l [. E0P EP Emergency Procedure Emergency Response Facility ERF Heated Junction Thermocouple HJTC High Pressure Safety Injection HPSI HX Heat Exchanger Low Pressure Safety Injection LPSI NPSH Net Positive Suction Head N/R Not Required PASS Post Accident Sampling System QT Quench Tank Reactor Coolant System RCS Regulatory Guide RG Reactor Vessel RV Shutdown Cooling Heat Exchanger SCHX SCMM Subcooled Margin Monitor S/G Steam Generator Safety Injection SI ! (n) SIRWT Safety Injection Refueling Water Tank Safety Injection Tank SIT Safety Parameter Display System, (synonymous SPDS with plant computer) [!- Technical Specifications TS. Updated Safety Analysis Report USAR 5.0 EXCEPTIONS TO REGULATORY GUIDE 1.97 REV. 2 AND STATUS UPDATE p General Table 1 provides a comparison of the Reg. Guide requirements with the available instrumentation. This table also notes compliance or non-com-pliance in the Comment section of the Table. No further review was deemed necessary upon determination that the instrument loop was qualified to the appropriate category requirements. This section addresses those loops which were not determined to be in compliance with the areas governed by the Reg. Guide. A majority of these areas were determined to be acceptable based on~ further analysis. This consisted of analyzing the existing equipment functions and design bases. Areas where analysis indicated that the intent of the Reg. Guide was not met were considered for upgrading. Equipment upgrade was identified in Table 1 and the actual design descrip-tion and upgrade schedule are discussed further in Section 6.0. The following justifications are the District's basis for deviations from the Reg. Guide. The intent of the guideline, which is to provide monitoring systems in the accident situation, is met in all cases. The analyses have been segregated into sections covering the specific variable types.

i . f% \\0 5.1 Type A Variables 5.1.1 Neutron Flux (CAT.1) The function specified above is performed by instrument loops N-001,002,003,004 made up of the excore detectors located in containment, amplifiers located in the Auxiliary Building and Wide Range Log Channel Drawers located in the control room. Four source range monitors (SRM's) and four wide range instrument monitors (IRM's) are provided for flux indication. All SRM and IRM detectors consist of dual fission chambers. The Excore detectors were replaced during the 1984 outage with fully qualified components. The detectors, amplifiers, and cable assemblies are qualified to Reg. Guide 1.89 and 1.100 and with the methodology described in NUREG-0588, CAT I. However, the balance of the equipment such as the Wide Range Log Channel Drawers, which provide signal processing and indication for neutron flux, have not been upgraded and are in compliance with the requirements applicable at the time of issuance of the construction permit. The District believes the above deviations from the requirements are justified as discussed in Section 2.3.3.A.1 of this report. Summary Position - The District believes that the existing ggJ instrumentation loops for neutron flux measurement are adequate to perform the intended accident monitoring func-tion. Thus, no modifications are proposed. 5.1.2 Reactor Coolant System Pressure (CAT.1) The function specified above is performed by pressurizer pressure instrument loops P-105/P-115 and by proposed loops P-120A and P1208 (scheduled to be installed during the 1987 refueling outage). These loops are in compliance with the f requirements of Reg. Guide 1.97 Rev. 2 except as noted herein: This function is performed by P105/P115 pressure loops for the LOCA/MSLB bounded DBA events, and by P120A/P120B pressure loops for the ATWS bounded Design Basis Events (DBE). O

1 (} v 5.1.2 Reactor Coolant System Pressure (CAT.1) (Continued) Range P105/P115 0 psia to 2500 psia P120A/P1208 1900 psia to 2900 psia An analysis of the pressure transient for Fort Calhoun A Station ATWS and assuming a Diverse Scram System (ATWS rule) reactor trip results in a peak pressure of 2600 psia. OPPD believes the range of 0 psia to 2900 psia is adequate for all DBE's. Seismic Certain portions of the P105/P115 instre 'nt loops have been upgraded to IEEE-344-1975. However, the e.. tire loops are not qualified to IEEE-344-1975. The sensors are qualified. Other components of the loop are qualified to the seismic requirements.which were applied at the time the construction permit was issued. Instrument loops P120A and P120B will be qualified to meet the requirements of IEEE344-19'i5. d:. O For further discussion with regard to seismic qualification, see Section 2.3.3.A.1. Summary Position The proposed additions to address the ATWS rule will resolve the Reg. Guide 1.97 RCS pressure requirement. A 5.1.3 Reactor Coolant System Hot and Cold Leg Water Temperature, Subcooled Margin Monitoring (CAT.1) Fort Calhoun Unit 1 is provided with redundant subcooled margin monitors which were designed and installed to the requirements of Reg. Guide 1.97 Rev. 2. The SPDS SMM's receive their inputs from the following temperature and pressure loops: 4 Hot Leg Temperature: T112H A/8 T122H A/B Cold Leg Temperature: T112C A/B T122C A/B Pressurizer Pressure P-105 P-115 Note, subcooled margin indication is not provided above 2500 psia. The ATWS event (trip occurring via the Diverse Scram (_} System) is a high pressure transient of brief duration, thus subcooling is of secondary concern. Performance can be d ~ i monitored via the loop RTDs, the CET's and P120A or P1208. OPPD considers the instrumentation adequate.. i

o DISTRICT'S POSITION: The SPDS' performs two additional subcooled margin calculations. These additional calculations are based on representative Core Exit Thermocouple (CET) temperature, and upper head temperature as sensed by the reactor vessel level Heated Junction Thermocouple'-(HJTC) probes. Both of the above mentioned temperature input (CET and HJTC) f loops are fully qualified to both 10 CFR 50.49 and Reg. Guide 1.100. Their temperature ranges of 32-2300"F far exceed those required by the Reg. Guide for SMM i.emperature inputs. All three calculations share the same pressure inputs (P-105 and P-115). These transmitters and loops are dis-cussed in Section 5.1.2.

SUMMARY

The District believes that adequate instrumentation is provided to perform the intended Accident Monitoring Function, and meets the requirements of Reg. Guide 1.97 Rev. 2. ) 5.1.4 Vessel Level Monitoring (CAT. 1) The function specified above is indirectly measured by the Reactor Vessel Level Monitoring System (loops Y-116A/8) comprised of the Heated Junction Thermocouples and the-Safety Parameter Display System (SPDS). The displays are provided in the control room, TSC and EOF through the SPDS portion of the ERF computer. These loops are in compliance with the requirements of Reg. f Guide 1.97. 5.2 Type 8 Variables 5.2.1 Containment Isolation Valve Position (CAT.1) Containment Isolation Valve Position is provided via the limit switches on the valves. These limit switches are environmentally qualified to 10 CFR 50.49 requirements. As noted in Table 1, limit switches provided on the follow-ing valves are environmentally qualified to 10 CFR 50.49 (00R Guidelines) but do not meet the Category I seismic requirements of Reg. Guide 1.97. =

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t. M. *). ' ' A-G-21-36 i Form A / y] (1 of 3) FORT CALHOUN ( ) NEBRASKA CITY (g ) s OHAHA STATION ( ) ~ ENGINEERING EVALUATION AND ASSISTANCE REQUEST ~' NO. FC-84-203 DATE 12-19-84 TITLE: ATWS Rule Modifications SYSTEN IDENTIFICATION: RPS, AR4, Turbine Trip C0!iPONENT: N/A LOCATION: Control Room REFERENCE - ORAWINGS: - PROCEDURES: - TECHNICAL MANUALS: - TECHNICAL SPECIFICATIONS: - UPDATED SAFETY ANALYSIS REPORT (FORT CALHOUN ONLY) - OTHER DETAILED STATEMENT OF PROBLEM: The ATWS rule requires installation of a redundant trip on high pressure, auxiliary feedwater actuation, and a reactor trip based upon anticipation of an ATWS event. These modifications must be installed by the second refueling outage after July 1984. PROPOSED SOLUTION (IF ANY): Determine if the existing AFW system meets the ATWS rule requirements. Prepare modifications for other two requirements. l EEAR NO.: FC-84-203 FORM A Page 1 of 3 FC/SO/OS R19 7-12-84 A

A-G-21-3 7 4-Fonn A b' / (2 of 3) RESTRICTIONS / LIMITATIONS: See ATWS rule. SPECIAL REQUIREMENTS: See ATHS rule. NRC has issued ATWS rule. REQUIRED BY/ COMMITMENT TO REGULATORY AGENCY: k M SUBMITTED BY: f J. K. Gasper (/ k -d. IM DIATE SUPERVISOR: R. L.'Jaworski FOR ADDITIONAL INFORMATION, CONTACT OPERATIONS ENGINEER J. K. Gasper RESOLUTION NEEDED: ( ) FOR CONTINUED OPERATION ( ) AS SOON AS PRACTICABLE ( ) OY NEXT REFUELING 1 ~ ( ) BY NEXT BUDGET PERIOD liust be opcrable prior to startup from the second refueling ( xx) OTHER (SPECIFY) outage following July 1984. This refueling is scheduled for the spring of 1987. f i EEAR NO.: FC-84-203 J FORM A I Page 2 of 3 i l R19 7-12-84 FC/SO/08 1 l i

\\ Al * * ^ 3,. A-G-21-38 i-Fom A - (3 of 3) SECTION MANAGER - TECHNICAL SERVICES ( ) COPY TO: SECTION MANAGER - GSE ( ) APPROVED BY PLANT MANAGER & 1. M DATE /- /o-e q f bf eVI.nk/'.*'t ' <//yk.: ~ 1 2 3 4 PRIORITY ( ) (X) ( ) ( ) 4 COMMENTS (IF ANY): i

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i + i EEAR NO.: FC-84-20 3. l FORM A Page 3 of 3 i .lO FC/SO/08 R19 7-12-84 , _ _,,, _,..-_ _,.m __?m.,_.,_.__.- C ' . - - -.. ~. -.. - -..

t A-G-21-36 Form Rev. 19 7/12/ Form B j (1 of 2) yCy FORT CALHOUN y NEBRASKA CITY . OMAHA STATIONS TECHNICAL SERVICES REVIEW AND EVALUATION MODIFICATION REQUEST N0: FC-84-203 DATE: July 26, 1985 REFERENCE EEAR N0: FC-84-203 NORMAL X OATE: 12/19/84 EMERGENCY PRIORITY TITLE: ATWS Rule Modifications 2 MINOR PRELIMINARY DESIGN REQUESTED: No REQUESTOR: DATE: REVIEW AND EVALUATION: q*; A' ' Technical Services recommends that GSE proceed with the redundant RCS high pressure trip modification and turbine trip modification. Technical Services will complete the Auxiliary Feedwater System review by January 1,1986 and supplement this Form B if modifications to the AFW system are required. 4 GSE noa n [ lRticaveo i Ni !O ritviet1/tvatu^Trori 8v: " c "eherrer o^'t: oe's 26 198s i FORll B Page 1 of 2 'R20 7-30-84 9

A-G-21-37 i Form B -/ (2 of 2) rv V IFN0DIFICATIONISREQUIRED,DESCRIBEBENEFITSOFPROPOSEDMODIFICATI0ft-Required to meet the ATWS rule. ..(., p - O I APPROVEDBYSECtIONMAtlAGER-TECHNICALSERVICES DATE 7/2.7 /ef / APPROVED BY DIVISI0tl MAtlAGER NUCLEAR PRODUCTION 7/3/ DATE lO EEAR No.: FC-84-203 fiODIFICATI0tl REQUEST No.: tt-ud-zuJ i FORll B R20 7-30-84 Fage 2 of 2

S.O.-G-21-42 O FORM REY. 19 7-12-84 Cl Form C FORT CALHOUN (X ) NEBRASKA CITY ( ) OMAHA STATIONS ( ) ASSIGN!ENT OF DESIGN RESPONSIBILITY REVIEW BY CTIO MANAGER - GSE 9 /A. / n DATE 08/02/85 W . /> A ,.y CC.MENTS: GSE DEPARTMENT ASSIGNED: CIVIL ( ) ELECTRICAL ( X) v) MECHANICAL ( ) t NUCLEAR ( ) DESIGN ENGINEER ASSIGNED: Sten' Milky DATE 81 & lFC GSE DEPARTMENT HEAD o,smo u o.s n.a m:m &i._ w-u ::o w v"m (K) $6tntt a $:nedule i( ) ted,eted f;r ( ) Ir.ctode This 11 fcer ( ) Patt stal 19 8 I 1987 _ sostius

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( ) $61..i t a e t s,v.re t1 (K) 1987 0;tase Job 5.nter's U.estfa*.st* p m ets ( )O h*C Ca==1t ent ( ) pregere set ! s'tti as Latit.tc tsr CJ.*:sstej ( ) in se teme+31cd ( ) plan to v rt.a 1 hts ( ) },"' ', 'J ':'.* ? ! YC, l'c: !!:st*te

  • P 4987

( ) Constructici Conp. ( ) pre:re an Af ter the Fa:t Lt::otsa raus. ( ) MODIFICATION REQUEST NO. FC-84-203 ( ) C.:reinit, this J.o.t tn ( i Ast for to p fra. l FORM C Page 1 of 1 FC/SO/08 l l R23 6-25-85 i

i. / / , Memorandum ~ ~ ~ _ed. _ud. Date: June 18, 1986 FC-783-86 From: PRC Subcommittee To: PRC Chairman

SUBJECT:

MR-FC-84-203, ATWS Rule Modifications, Preliminary Design Review The PRC Subcommittee has reviewed the preliminary design proposal. The design proposal is acceptable pending the satisfactory resolution of the following comment:

1) Will pressurizer high pressure provide adequate protection for all possible ATWS events? An uncontrolled heat extraction event would reduce system pressure initially. Does this type of accident need to be considered?

T L. T. Kusek H. R. Core Supervisor - Operations Supervisor - Maintenance SY, s [ K. R. Henry 7 . J. Fol upervis - I & C/ Electrical Senior Test Engineer Field Ma ntenance J.[iorTestEngineer . Bailey Sen FRC Reviewed LTK/MRC/JJF/KRH/JFB:dmw PRC Mtg. Minutes jdL 23 G86 \\ ~ O 44 %..e

. S.O. G-21-60 FORM REY. 21 09-26-85 L (- FORT CALHOUN STATION' MODIFICATION Form I DOCUMENT UPDATE REQUIREMENT (1of1) . MR(EEAR)/96R-NO. Fc-99-ZQ3 DATE: 12. 8G. TITLE: ATW5 b.E Mepin e ce NOTE: Symbol "*" indicates a new document. FILLE OUT - ITEM DOCUMENT TITLE AFFECTING SECTION NO. OR ID NO. BY 1. P and ID Dwg. Book E-Z30GG -210- 10 Md Design Engr. 2. EM Dwg. Book flNo5'-EM-f 2.0 sn.1, su.Z .l>C7tC4L Design Engr. 3. Operating Instruction 4 OI-D53 J/ d

===4. System Description=== 45 D.If Design Engr.

5.. Technical Specification 2.l5,1.?_

Jx R 6. U.S.A.R. 7 $35m usr, scews, Ecor.r, coma riue D sign En r. 7. E.E.Q. Manual /QLP

  • A/Pr-izo. B/ Pr-sto.c /p 7-,7_o,p/pr-,to 4

Desi.gn Engr. i 8. Engineering Data i Collection Forms

  • ( S EE ATT Ac wT) U ST)

Design En '9. Security Plan N/A Jf7haE.gr. Design Engr. i

10. Standing Orders OPS Engr.
11. Technical Data Book "9"*

j

12. Surveillance Test

{ Procedure "9 *

13. Calibration Procedure C.F-lZO
  • '"9"*

l

14. Operating Procedure OF-l O "9
15. Maintenance Procedure "9

16. P.M. Procedure for QLP "9

  • 17.

E.P./E.P.I.P./R.E.R.P.

  • '"9 "

f

18. Security Procedures rJ/A "9"*
19. Other OPS. Engr.

ISSUED FC/SO/03 R26 04-04-86 APR 041986

k Ar,tue.ER.we VARA btt.Ec_rto4 FoR%s YkG't YAG W A/PT-rzo A /Ts-T43 3/ Pr-12o A1[T5-PS3 c/PT-12.0 B /Ts-pss D/PT-120 31/rs-pss A /FM-izo ec.A/D55 B/FM-izo 8( A /D55) c/pM-17.o 94l-Al /D33 D/FM-11o 3-A I/D33 A/FA-1Z0-1 99-A?-/.DS.s A/PA-i20-2. 3-A2./D5s O s/e^-izo-i 5 3/oss S/FA-170-2 % B/D553 c/PA-rzp-t 99-EZ/ps3 c-/FA-iza-2. 3-B2./ Dss D/PA-110-I 9'+-BI /D5.5 9/PA-170-2. 3-Bl[D55 A /Ft-17 0 A/Dc3 / TRIP-ILR 3 /FC Ito AIDss /PRomP-ILR c/ PC-t1.0 B/Dse/ ram-ItR 'P/Fc-#7_o 5/D:55 /PRETRip-ILR. A/'F&110 c.[pss /TR m-ILR b /FI-110 C /D ss/' Mera m-ILR A/TS-Ito 'D/D55/TR iP-ILR O b/TS-\\20 D/pss/ PRcrR ue-1La c./'T.5-l Zo 9/T5-izo

TAG NUMBER: A/PA-120-1 D/PA-120-1 A/PA-120-2 D/PA-120-2 B/PA-120-1 B/PA-120-2 C/PA-120-1 -m C/PA-120-2 As SERVICE: CONTACT OUTPUT ISOLATOR (COE MILD ENVIRONMENT) MFR. AND MODEL NUMBER: FOXBORO N-2AO-L2C-R ( N-ECEP-{10273)M CONTACT OUTPUT ISOLATOR FOR SPEC 200 SYSTEM WITH OPOT CUSTOM OUTPUT RELAYS POWER REQUIREMENTS: +15Vdc 25% 40mA maximum per relag INPUT SIGNAL (S): M 10V minimum Q 550 ohms mansmum source impedance HIGH LOW: 0.5V maximum from 50 ohms maximum source impedance INPUT RESISTANCE: 500 ohms nominal (de) VOLTAGE OROP ACROSS OUTPUT TERMINALS: <0.5 ohms at rated load T I C 1 OUTPUT: 5 p Q OPOT relay contacts (Custom Design (N-ECEP-10273Q 82 LLI D A

  • E W

OUTPUT LOAO (MAXIMUM RESISTIVE): C A H 120 VAC: SA. 230 VAC: 2A, 28 Vde 5A. 40 Vde: 1A. 125 Vde: 0.5A lOE } y SUPPLY VOLTAGE EFFECT: r - ---- g No error within normal operating Inmits 7 e : l O AMBIENT TEMPERATURE RANGE: l d E y 5 to 50*C ( 40 to 120*F) s l N b [ O I q AMBIENT TEMPERATURE EFFECT: b. b No error within normal operating range FORT CALHOUN STATION osa N ~, )$ CHtCKED 3 g ,j t~ctaccR MISCELLANEOUS ' z civrt INSTRUMENT I $ $'c'['[ SPECIFICATIONS c $ d NUCLEAR g CSE FILE NUMBER 40233 u "U l SPEC No.497 g g l SHEET 1 0F 2 k

CONOUIT & CABLE ROUTING DWG.NO.11405-E-151 SHEET NO.11451-12 og CABLE SIZE & KINO TRAY SECTION NUMBER sament coot ) O EA11529 I CND,I2A I1A I2A I1A ( A)I1A I2A I2A I2A7, 7-1 CND, 13S,8S, 9S, 10S, 5-4, 6, EA11529A 'I CND,I2A I2A I2A I 7-1, 7, 8, 75 1A (B) 1A 48 4B I4B EB11530 I CND,22S, 5-4, 6, 7, 7-1.CND, EB11530A I CND'I4B I4B I4B I4B I4B I4 I4A 7-1, 7, 8, 15, 14, 28, 27, O f0h t CONSTauci g C n,. :.. IN E A REY.5H./NO. l (/) 12/86 TEB j l FOR CONSTRUCTION DRAWN hh Mj/{ MR-FC-84-203 CHECKED s ISSUE DATE DWN CHKD ENGR' CIVIL dLEC MECH NUC E I ER NO. DESIGN DRAFTING DESIGN VERIFICATION ELECTRICAL MECHA*lICAL GSE FILE NUMBER 43562 " a*

TAG NUMBER: A/PI-120, & B/PI-120 I o \\ ) SERVICE: PRESSURIZER PRESSURE I MFR. AND MODEL NUMBER: FOXBORO N-257H-1K GENERAL Funouon i Record O IndiceseM ControlO BlindO IntegO Deviation O Other Case 2 HFR STD H Nom Sare Color:HFR STD M Other Mounting 3 Flush u Surface O Rock O Mulu-Case M Other PANEL-MOUNTED IN INDIVIDUAL MOUSING For Multiple Case. See Spoo. Sheet Enclosure Class 4 General Purpose M Weather Proof O Explosion-Proof O Class For Use an Intrinsically Safe System. O Other Po-or Supply 5 117 Y 60Hz O Other ao do N 0-10 Volts Chart 6 Strip D Roll O Fold 0 Circular Time Marks Range Number Chars Orave 7 Speed Power Scales 8 Type LINEAR Range i 1900-2900 PSIA 2 3 4 CON Control Modes 9 P2Propt Gain).I= Integral ( Auto Roset).D=Derivativet Rotel. Subs s= Slo . st P O PI O PD O PID D If O Of O Is O Os O Other Actaon 10 On Mees. Increase Ince Georeeses O Auto-Mon Switch 11 None O MF Other Set Point Adj. 12 O External O Remote O Oth T Monuel R.g. 13 Non. O MFR Sio O Other Du 14 4-20 mA O 10-50 mA O 21-103 kPat 3-15 psig) O Other sp Q INPUTS Inputs Signals 15 4-20 mA O 10-50 mA O 21-103 kPa!3-15 psig) H Other 0-10VDC No.of Inputs 16 iM 20 30 40 ga (f) Power for XMTRS 17 Ex ternal N This Inst O No.of Independent Supplass @E For Transmitters. See Spoo. Sheet. 499. & 495 m atTRiss- -h r >,m Ret } W Aie,m S..ich.s Func tion 19 Meas.ver. O Mens z ) y =$ ~ n.c ~ ^ d E OPY Supply Gage O Charts O Int.Il D g IMilt S = Oth.c g H $ N 00UL O y - g s NOTES: HD. SHEET w FORT CALHOUN STATION og, y k

1. THE INDICATORS SHALL MEET OR CHECKED b

o e EXCEE0 QUALIFICATION REQUIREMENTS RECEIVER cuctuEEn M RPECIFIED IN ETS-001 civIt INSTRUMENT I -g a 5 yQ ELECTRIC

  • SPECIFICATIONS scCnan1 Cat In NUCLEAR 3

8 E GSE FILE NUMBER 43313 ~~ UCTrO\\ ". O 1 I y t SrEc No. s24 i l e e e Sen1 1 Or 1

CONOUIT & CABLE ROUTING DWG.NO.11405-E-151 SHEET NO.11451-10 op CABLE SIZE & KINO TRAY SECTION NUMBER [) EA11513 I

CND, g
f8C, EA11513A I

CND,TRAYRISER CND C 2C, 3C, C, SC, I2A I3A I2A I1A I1A I2 EB11514 I CND,21S,20S,26S 27S,86S,85S, I1A I1 I1 I1 Il EB11514A 61C,60C,7C, 9C 10C CND,ffS,8 .83S; EC11515 I EC11515A I 5 C,58C,30C,3 C,35C.CND CND,f f k g, ED11516 I E011516A I

50C, C.20C,2 C,22C.CND

} v EA11517 C CND'C1A C1A C1A C1A C1A C1A C1A C1A C1A RISTR ' C215S 7-1, 7, 6, 5-3, 5,

3. 24, 32, 31, CND,fg,CND EA11517A C

EA11517B C CND,2, gg, f2g,CND CND,ffg,CND EA11517C C h, f23,CND EA115170 C

CND, EA11518 C

CND.C1A C1A C18 C1A C1A 16, 14, 28, 38, 37, F0R l CO\\YTRUCToy jggyEj REY.5H./NO. l F 0 TR TION { 12/06 TEB V pq p, O SSUE DATE DWN CHKD ENGR CIVIL EI.EC MECH NUC M 'I"' 7, NO. l DESIGN ORAFTING DESIGN VERIFICATION ELECTRICAL l MECHANICAL l GSE FILE NUMBER 43560 " ^a

CONOUIT G CABLE ROUTING DWG.NO.11405-E-151 SHEET NO, 11451-11 0F CABLE SIZE & KINO TRAY SECTION NUMBER etMest CODE r^} CNDh01,hf6 22S,CND, EB11519 C CNDhfg,h0S, EB11519A C S. S.CND CND,hfg,CND EB115198 C CND,h6,OS, EB11519C C S. S.CND CND,hhg,CND EB115190 C ED11520 C CND C3A C3A C3A C3A C3A 16, 14, 28, 38, 37, ('NDh1_1,hf6 2, 32, 3, RISER, hfg,CND 11521 C 5-3,5 3 11521A CND 11522 C CND.C6A C6A C6A CGA C1A(B) C1A22S,CND, 16, 15, 8, 6, 5-4, [V 11522A CND \\ r- ... r p. CND,h[1.hf 6 24,32,31, RISER,hfg,CND 11523 C 3,5 3 11523A _O CND p. . C -) ,m CND C6A CGA C6A CGA C1A(B) C1A 21524 C O 16, 15, 8, 6, 5-4, 22S,CND-I 11525 I cNo.I1 12 I213A I3A 13A 13A I2A I2A I4A I4A I4A I4143, 5, 5-3,5-4,22s,2ts,2ss,2ss. 11 Il 12 I3 12 7s 59. 57,55, 53, 51, 49, 45, 44, 32, 24, I1A I2 I2 I2 I2 I2 I2 I1 I1 I1 Il 11526 I () CND'59, 19, 18, 14, 28, 38, 39, 40, 63, 60, 70,CND* cND'It I2 I213A I3A 13A 13A I2A I2A I4A I4A I4A I4 I43, 5, 5-3,5-4,225,21S,205,26S I1 11 I2 I3 I2 11527 I H 78,59. 57,55, 53, 51, 49, 45, 44, 32, 24, I1A I2 I2 I2 I2 I2 I2 I1 I1 I1 I1 11528 I CND'59, 19, 18, 14, 28, 38, 39, 40, 63, 60, 70,CND' aEv.ss.euo. I 12/86 TED g g[ hR TgC 5 ,p , 3 C EO ~~

  • E I ER ISSUE DATE DWN CHKD ENGR CIVIL E;.EC MECH NUC NO, DESIGN DRAFTING DESIGN VERIFICATION ELECmICAL MECHANICAL GSE FTl E NllMBER 43RR1

TAG NUMBER: ( ) a SERVICE: MFR. AND MODEL NUMBER: SEISMIC PERFORMANCE: Accuracy within *0.5% of upper range limit of ter o disturbance defined by a required response spectrum with a ZPA of 7 's. 9 OVERPRESSUR LIMITS: M00EL[154Gh4500 PSI HUMIDITY LIMITS: 0-100% RH A [RESPONSETIMEh M 0.2 SECONOS at 100*F ) NOMINAL FIXE 0 RESPONSE TIME Of ~ j RADIATION PERFORMANCE: q [ curacy within * (1.5% of upper range limit +i.0% of spon) during and li-after exposure to 55 x 10 RAOS total intergrated dose gamma in accident sequence M 6 h Q (ond5.5x 7 10 RAOS af ter accident for a total exposure of 1.1 x 108 RADS. 82 LLJ e / !E? 3 g7o W OUALIFICATION STANDAROS: IEEE 323-1974 fiROSEMOUNT REPORT 0840M } !OI IEEE 344-1975 (ROSEMOUNT REPORT 08400102) ) l pn g p-k g [p7 n g, UUl0 TUVI UIN g HYSICAL SPECIFICATIONS: \\ y ISOLATING DIAPHRAGMS AND ORAIN/ VENT VALVES 316SS. PROCESS FLANGES 316SS. Q ,k 8 [ PROCESS 0-RINGS 316SS. ELECTRONICS HOUSING 0-RINGS ETHYLENE PROPYLENE. \\ l FILL FLUID SILICONE OIL. FLANGE BOLTS PLATED ALLOY STEEL. PER ASTM A-540, \\ 3 g PROCESS CONNECTIONS %" SWAGELOK COMPRESSION FITTINGS 316SST. ) 3 o s gg g ELECTRICAL CONNECTIONS %-14NPT CONOUIT WITH SCREW TERMINALS / E @*b'PECIFICATIONGSEE-0803 APPLIES ING 316SS k ! ! FORT CALHOUN STATION ORAWN LL O CHECKED g g (*

  • ENGINEER MISCELLANEOUS C "I' INSTRUMENT z

I y 9 ')^S 9 S'C$'c[ SPECIFICATIONS i d NUCLEAR GSE FILE NUMBER 40238 g, 'nis:sism u g g g g SPEC No.499 l g g g SHEET 2 0F 2 H

TAG NUMBER: A/PT-120 8/PT-120 C/PT-120 0/PT-120 i i SERVICE: PRESSURIZER PRESSURE TRANSMITTER (COE INSIDE REACTOR CONTAINMENT) MFR. AND MODEL NUMBER: ROSEMOUNT M00E(115We\\ "1154GP9R%- CAPACITANCE MEASURE 0 OIAPHRAGM SENSOR v PRESSURE RANGE: 0-3000 PSIG ACCURACY: 10.25% of calibrated span. Includes combined effects of linearity, hysterists and repeatability -( STABILIT A

  • 0.25% of upper range limit for 6 mon s

v OUTPUT: 4-20mA de 1 { p POWER SUPPLY: 3 External power supply required, up to 45Vdc. ( )k ~ O MB Llj $7 D SPAN AND ZERO: v> < (f) y (f) Continuously adjustable externally l 'i-H aog [ ELEVATION and SUPPRESSION: MaxNum Zero Elevation: 600% of calibrated span, 6 f Maximum Zero Suppression: 500% of calibrated span. ws 1 6 Zero Elevation and Suppression may not exceed 100% of the upper range limit. $ wU ) %d M g$ TEMPERATURE LIMITS: I+40' to 200*F NORMAL OPERATING OESIGN s PO VRT. 71 IPT. n \\, -40 to 120*F QUALIFIED STORAGE

w w

y ~~ w ww v y' [9 NOTES: REv.SHLET p g g G CHECKED $ lE EmimEn MISCELLANEOUS 5 CI'R INSTRUMENT { ['c[','c[ SPECIFICATIONS e o urum g3 GSE FILE NUMBER 40237 ~ ~ g g g g SPEC No.499 l g g l SHEET 1 0F 2

TAG NUMBER: s s,. _/ SERVICE: MFR. AND MODEL NUMBER: RESPONSE TIME: 10 milliseconds typical VIBRATION: Operating Basis Earthquake (OBE) and Safe Shutdown Earthquake (SSE) OUALIFICATION STANDARDS: IEEE STD 323-1974 IEEE STD 344-1975 LL O m w d? D Cn $;a W r+ H 2E \\ Y x 5 d) @ D R M M 3d E P A \\lO T 31ID_T_ U T I'i N 3 W vu,Tv \\ v\\ e 1 ) n5 u $ _ v e 4 $w NOTES' g ag MM GWWN MMEN og,,y 3 50 ' l, CHECKE0 tucincts MISCELLANEOUS

  • h h

I - U Civro INSTRUMENT 6 5 ['[c'['c" SPECIFICATIONS R N$ NUCLEAR { GSE FILE NUMBER 40234 { I g g g g SPEC No.497 g9 ~~

  • ~'

l g g l SHEET 2 0F 2 w j

TAG NUMBER: SERVICE: MFR. AND MODEL NUMBER: VIBRATION: OPERATING BASIS EARTHOUAKE (OBE) and SAFE SHUT 00WN EARTHOUAKE (SSE) 00ALIFICATION STANDARDS: IEEE STO 323-1974 IEEE STD 344-1975 I ea LL s = a Ma to e a p m o m m t H h I W n = 1 8 ~ x U H f"* O 9 p*g y RUT d col \\RTRl CT ON I s t -u s E g E m m NOTES: RE v. SHE E T FORT CALHOUN STATION .w g g on,, 5 0 c"tcxto cmtwin MISCELLANEOUS P jg cart INSTRUMENT 5 ItcM[ SPECIFICATIONS m R W m nncan 1 8 a cSE FILE NUMBER 4023G

  • '~'

g2 l seEc No.49a l a SHEET 2 OF 2 g g g

TAG NUMBER: AI-196-N6-11 AI-197-N6-11 ~, x i. SERVICE: POWER DISTRIBUTION COMPONENT (MILD ENVIRONMENT COE) MFR. AND MODEL NUMBER: FOXBORO N-2AX+DP10 POWER DISTRIBUTION COMPONENT FOR SPEC 200 SYSTEM INPUT +15Vdc from rack supply. System common from rock supply. -15Vdc from rock supply OUTPUT: +15Yde to component bus, system common to component bus. -15Vdc to component bus. 30Vdc to field bus OVERVOLTAGE PROTECTION: Maximum field bus output of 40 22Vdc REVERSE VOLTAGE PROTECTION: { Any voltage of the opposite polarity will be clamped to 0.7Vdc (one diode drop) g above common in the direction of the input voltage 5 O O ' Q LLJ SHORT CIRCUIT PROTECTION: N Dg Both +15 and -15Vdc inputs are fuse limited to 3A DO W t H TEMPERATURE LIMITS: 5' to 60*C ( 40 to 140*F) l RELATIVE HUMIDITY LIMITS: H 50 and 95% at 30*C ( 86*F) maximum wet bulb temperature 3 I o W h ~ t $ 5 1 \\ ~d UUINb 1UU UA 5 u m h d

  • b.

NOTES: H v.sHu r g FORT CALHOUN STATION on ^ CHECKED mma MISCELLANEOUS e m z idg o CIVI' INSTRL' MENT y ml 5 ['< j" c'1 SPECIFICATIONS cJ h y Q w cttAn w a i GSE FILE NUMBER 40235 I I SPEC No.498 hE g g SHEET 1 0F 2 I

TAG NUMBER: A/PM-120 B/PM-120 C/PM-120 D/PM-120 m ( ) v SERVICE: CURRENT TO VOLTAGE CONVERTER (COE MILD ENVIRONMENT) MFR. AND MODEL NUMBER: FOXBORO N-2AI-I2V+P (N-ECEP-90011) Current to Voltage Converter for SPEC 200 System with Custom termination hJoch L ) h POWER REQUIREMENTS: +15 and -15 Vdo *5% ot 80mA maximum when totally powered by system via nest bus, or 45mA maximum when output as connected to on external supply in series with the load, i INPUT SIGNALS: TWO EACH 4 to 20mA de OUTPUT SIGNALS: TWO EACH 0 to 10V de with minimum load resistance of 2000 ohms. TEMPERATURE LIMITS: l b 5' to 60*C ( 40 to 140*F) O w. 3 RCLATIVE HUMIDITY LIMITS: p Q g W 50 and 95% ot 30*C ( 86*F) maximum wet bulb temperature. ~? D Pro W h3 W VIBRATION: 't H h Operating Basis Earthquake (OBE) and Safe Shutdown Earthquake ( SSE) r l QUALIFIED STANDAROS: m3 h 3 V \\ IEEE STO 323-1974 CO \\ S I RUC I O ;! ' h IEEE STO 344-1975 d h 5 y

  • Positive and (0) leads are switched open when testM is inserted ll 5

n l y (One module per converterl /_B_\\ y% Es % w NOTES: HE W. SHE E T g FORT CALHOUN STATION og,,, 5 0 cHr.c co "d Encintra MISCELLANEOUS 8 civr' INSTRUMENT ar g $ $$*1 I SPECIFICATIONS c y h { tartt an ) GSE FILE NUMBER 40230 . e4 0 o g g SPEC No.495 g g CHEET 1 0F 1

TAG NUMBER: A/PC-120 B/PC-120 C/PC-120 D/PC-120 (v SERVICE: NEST ALARMS (COE MILD ENVIRONMENT) l MFR. AND MODEL NUMBER: FOXBORO N-2AP+ ALM-AR 4 NEST ALARMS FOR SPEC 200 SYSTEM t i POWER REQUIREMENTS: l +15Vdc 15% at 80mA maxtmum. -15Vdc 25% at 60mA maximum. INPUT SIGNALS: 0 to 10 Vdc INPUT RESISTANCE: l Absolute alarm: in Deviation, Dif ferencek50 man A OUTPUT SIGNALS: Contacts closed, will switch 100mA at 28Vdc maximum resistance load. ADJUSTMENTS: g Setpotnt: 0.5 to 99% of input span Q Lij Lockup: 0.5 to 10% of input span (uncalibrated) i e7 3 i $5 U l 00 W ACCURACY ( ALARM SET POINT): h' Q 22% of input span H zal ) Y REPEATABILITY: 7 I o ) M y Setpoint: Less than 0.5% of input span i I <r M Lockup: Less than 0.1% of input span y3 4 u V\\ Alarm Potnt: Less than 0.1% of input span d i F(1 UUNS 1UC~~ O \\ l n ~. ~ w 9 o M w NOTES: REV. M ET g5 g 9 FORT CALHOUN STATION

ogo, 6 U
f) cntcwto j

cscruttR MISCELLANEOUS Ei civit INSTRUMENT 't y l Itc['cI SPECIFICATIONS h M NUCLEAR \\ -U O d GSE FILE NUMBER 40231 1 1 0 1 SPEC No.496 1 u E g l g g l SHEET 1 0F 2 sem e-m ma m ea m

l TAG NUMBER: s a f~ g i O SERVICE: MFR. AND MODEL NUMBER: RESPONSE TIME: 15 si3 milliseconds. based on input originally at 25%, step changed to 75% with alarm setpoint at 50% of span SUPPLt 10LTAGE EFFECT: Alarm setpoint shif t less than 0.25% of input span for a 5% change in supply voltage unhan normal operating lamats. AMGIEh! TEMPERATURE LIMI7S 5 and 50T, ( 40 and 120*F) AMBIENT TEMPERATURE EFFECT: Alarm point shif t less than 0.5%h anput span for any 25*C ( 50*F) change with normal operating limaxs. b 1 RELATI(E HUH 10ITY LIMITS: z 50 and 95% at 30*C ( 86*F) maximum wet bulb temperature S O w82 LIJ !E? D g (f) VIBRATION: Oh j Operatang Basis Earthquake f 00E) and Safe Shutdown Earthquake (SSE) Ee mz OUALIFICATICN STANDARDS: IEEE STD 323-1974 z I O d ? IEEE STD 344-1975 x <r CAD 8 UI \\ w e s$ C O N S T R U C T O N. i o ye M b g y FORT CALHOUN STATION NOTES: REV M ET o,

  • O h 3 1 '**

CHECKED ', t, 3 ? '. u EuczwcER MISCELLANEOUS m z itJU C 2, w 2 o CIvrt INSTRUMENT 5 'd'c['1c. SPECIFICATIONS A E $ NUCLEAR U O F GSE FILE NUMBER 40232 u C3 g l SPEC No.496 $Z g g SHEET 2 OF 2

(~ j~ I } \\ ( LJ wJ \\ CDou1T & Caste SCEDuLE DwG. eso. 11405-E-151 peggee_11451-11 er CaeLE Cacuff N WIRE OR CasLE easern um a unas FROM 70 "JJ8 Dan rams g,*F gg stes a E811519 CONTROL RM.PNL AI-668 JB-673A i 12/C *12 600v 100 W42

  • DSS
  • CHANNEL
  • B-MATRIX EB11519A JB-673A AI-196 1

4/C *12 600V 130 W40

  • DSS
  • CHANNEL
  • B* MATRIX EB115190 JB-673A AI-197 1

4/C *12 600V 20 W40

  • DSS
  • CHANNEL
  • B* MATRIX E811519C JB-673A AI-198 1

4/C *12 600V 130 W40

  • DSS
  • CH#NNEL
  • B* MATRIX EB115190 J8-673A AI-199 1

4/C *12 600V 25 W40

  • DSS
  • CHANNEL
  • B MATRIX ED11520 CONTROL RM.PM, Al-668 CONTROL RM.PNL. AI-57 1

2/C *12 600V 100 W38

  • DSS
  • TRIP SIGNAL CHANP(L
  • B" 11521 CONTROL RM.PNL.AI-66A AI-196 1

4/C *12 600V 280 W40 TEST INDICATION CH. A OR C/P-120 11521A AI-196 AI-198 1 2/C *12 600V 15 W38 TEST INDICATION CH. A OR C/P-120 11522 CONTROL RM.PNL. Al-668 AI-197 1 4/C *12 600V 140 W40 TEST INDICATION CH. 8 OR D/P-120 11522A AI-197 AI-199 1 2/C *12 600v 15 W38 TESI INDICATION CH. 8 OR O/P-120 11523 CONTROL RM.PNL.AI-66A AI-196 1 '/C *12 600v 280 W40

  • 0SS* CHANNEL A AND C ANNUNCIATION 11523A AI-196 AI-198 1

7/C *12 600v 15 W41 'OS$* CHANNEL A AND C ANNUNCIATION I 11524 CONTROL RM.PNL. Al-668 AI-197 1 4/C.12 600V 140 W40

  • DSS
  • CHANNEL B AND O ANNUNCIATION 11524A AI-197 AI-199 1

7/C *12 600v 15 W41

  • DSS
  • CHANNEL B AND D ANPJUNCIATION 11525 JB-696A AI-196 1

2/C *14 STP 600V 300 W57 ERF COMPUTER S.O.E. INPUT 11526 JB-696A AI-197 1 2/C *14 STP 600V 150 W57 ERF COMPUTER S.O.E. INPUT 11527 JB-696A AI-198 1 2/C *14 STP 600V 300 W57 ERF COMPUTER S.O.E. INPUf f p p L* 11520 J8-696A AI-199 1 2/C *14 STP 600V tb8 "o rRF COMPUTER S.O.E. INPUT FOR ...s.. i Q kb26g. testage 2'423"" CONSTRUCTION QL - = u mn G11Ed2/ETa$dk312 1ssum roiy_ _ _ g:11 cse nu. & = m

!q f ( s / (- i V L/ TAG SPEC. FUNCTION / VENDOR / P. O. LOCATION SET NUMBER SH. DESCRIPTION MANUFACTURE 1 NUMBER POINT LHF COMPuiER T P1208 SE Q.-OF -E VE NT S PC-14 j INPoi [ OSPOS \\ P01200 INPUT AI-2988 ] W /b PRE SSUFiE '5812%1l C/PT-120 499 TRANSMITIER fl0SEpomi CONI. CtHENT 10 WOLI AGE FOXBORO 5811618 C/PM-120 495 CONVERTER SPEC 290 AI-198 CONTACT OUTPUT FOXBORO $s11618 C/PA-120-1 497 ISOLATOR SPEC 290 AI-198 CONIACI OUTPUI FOA8m0 $811618 C/PA-129-2 497 ISOLATOR SPEC 20s AI-198 FOR SKETCH REFER TO 11405-EM-120 .m BISTABLE ALAHM FOX 8m0 5811618 l N TRIPE] SHEET 1 C/PC-120 496 DUTPUT SPEC 280 AI-198 / b? " FILE NUMBER 40239 i / 24ss PSIA ERF COPfuTER V / ~ P120C SE Q. -OF-E VE N T S PC-14 / m INPUT _ ns SSUHE 5012551 f D/PT-120 499 TRANSMIITER ROSE MOUNT CONI. CUREN! 10 WOLIAGE FOXBORO S811618 D/PM-120 495 CONVERTER SPEC 289 AI-1% CONTACT OUTPUT FOX 8ORO 5911618 0/PA-120-1 497 ISOL ATOR SPEC 298 AI-1% CONIACI OUTPUT FOX 80R0 5011618 0/PA-120-2 497 ISOL ATOR SPEC 298 Al-1% t 81SIABLE ALAHM FOXSORO $811618 PHE I8' 0/PC-120 496 OUTPUT SPEC 200 AI-1% 7, ( 2454 e ('M' yp; P1200 SEO.-OF-Evt,, [A FOR CONSTRUCTION g ERF COMPUTER ~ C 12/80 TED WJ MR-rc-84-283 8 10/80 TES FINAL DESIGN PC-14 we-FC-e4-2e3 IWUT M" ~- J , yg g a BS/06 RSK pyg _ 3 fO l If*TI A Pf gg y DATE DwN CoorD INCR CIVIL ELEC MFCH NUC vv E b# \\# 8 3 (/ I 4 k NO. nfSIGN ORAFTINr, DESIGN Vf RIFICAT]ON I(NI CALNIN SIOIIEN REFERE NCE DRAWINGSe w,,, I. CE DwG E 2386G 210-Its n,7,1 EQUIPPENT LIST .m _,m 4 g7 -{} 8 Eft f M h . {7 r.v s :rnaeveR eores ld 1. ll l A2 niess too-

== {' %_J O G coeuTr a CasLE sC><tuE own se. 11405-E-151 setETse_11451-19 or CasLE CONDUIT Is REACTOR COOLANT INSTRUMENTATION & CONTROL WIRE OR CASLE esa sza a sie rn0M 70 NN ens gorga m,3, tgemy gsg ne,, EA11513 PNL.AI-196 PENETR. All 1 2/C *14 STP 600V 78 W57 PRESSURIZER PRESS. *0SS* CH. A/P-129 EA11513A PENETR. All TRANSMITTER A/PT-120 1 2/C *14 STP 600V 270 W57 PRESSURIZER PRESS. " DSS

  • CH. A/P-129 EB11514 PNL.AI-197 PENETR. A4 1

2/C *14 STP 600V 205 W57 PRESSURIZER PRESS. 'OSS* CH. B/P-129 EB11514A PENETR. A4 TRANSMITTER B/PT-120-1 2/C *14 STP 600V 150 W57 PRESSURIZER PRESS.

  • DSS
  • CH. B/P-129 EC11515 PNL.AI-198 PENETR. D-5 1

2/C *14 STP 600V 60 W57 PRESSURIZER PRESS.

  • DSS
  • CH. C/P-129 EC11515A PENETR. 0-5 TRANSMITTER C/PT-120 1

2/C *14 STP 600V 165 W57 PRESSURIZER PRESS.

  • DSS
  • CH. C/P-129 E011516 PNL.AI-199 PENETR. Die 1

2/C *14 STP 600V 115 W57 PRESSURIZER PRESS. 'OSS* CH. 0/P-129 ED11516A PENETR. 010 TRANSMITTER D//T-120 1 2/C *14 STP 600V 265 W57 PRESSURIZER PRESS. "0SS* CH. D/P-120 EA11517 CONTROL RM.PNL. AI-66A J8-672A 1 12/C *12 600V 200 W42

  • DSS
  • CHANNEL
  • A*

MATRIX EA11517A JB-672A AI-196 1 4/C *12 600V 60 W40

  • 0SS* CHANNEL *A*

MATRIX EA11517B JB-672A AI-197 1 4/C *12 600V 135 W40

  • 0SS* CHANNEL
  • A* MATRIX

/ EA11517C JB-672A AI-198 1 4/C *12 600V 70 W40

  • 0SS* CHANNEL
  • A* MATRIX EA115170 J0-672A AI-199 1

4/C *12 600V 130 W40

  • DSS
  • CHANNEL *A*

MATRIX EA11518 EONTROL RP4.PNL. AI-66A CONTROL RM.PNL. AI-57 1 2/C *12 600V 90 W38

  • DSS
  • TRIP SIGNAL CHANNEL *A*

rus fLMIFA~ C'Q'E' -~ n, M, ,hus_" "' ,mw-CONSTRUCT \\oN 5 y m ~~ < uei.ii m. IssuEo ron =.l.0. i mL in sir.= m<< n ur. m sir.m w att ica"'" GSE FILE NUMBER 435G3 -u

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oo uu ....____,__________.......a.______. 8.g g 55 .________.____,r...___.._________,.... -_____..,r___ 4.. gg 55 qswg( m=uml i Y.: l e aswg l -eg 5.. i i u w'en l w$.on l 5 60 o5. oI;e q 5tss e-~ c 4. og;r c .i o m l -u-- -u-- -u-- -u-5 u_ . _ _ _ _ _ g _, -.... _ _ 3. - -. -.4 l 4 l l 4 l m _ _ - - -. - p - - - 3. g _.. agg c a a~ -~ 2 ,~ ~ ? ji H !~ 2 l1 l? l1 lh t i o ' ? l? l? O! O! Oi < d O! O! 6! nnn S s_ l lt ,t t u .t ,t t lt = ,o io i sj lu = E ge m p, _* _ _ _'i _ _ _ _ _ 4'___ 4 ~m i___--4 '...._4 3 m.a i g l v rw ww l OV p$ Gv l O_W !' Ro Io g 61. ._ m u m, i ~ i ~ y y 7 ~ E lE lE .E 'E fe c l2 D 2 l3 gg._.;._._._._._._._;_._._._._._._.'c._.-.-._.-._..;.._._._._. 4 j! 'a '2 2 2 t 3 g ? ? ? ? o h -G t E k E ( s e V ( ,lj c 2 3 e u

  • !ii sdvi unrunss3ad wovJ

p ,m. (m) N') Y' _,li i %,.} Copou!T & CAeLE SCEtu K ~%- . N DW. NO. 11495-E-151 wt se_11451-12 y CaaLE CDout? II WINE OR CasLE saaean sza asuo FROM 70 '**g*f,gM waavans g,y g,, seeso. EA11529 AI-196 CONTROL RM.PNL. AI-66A 1 2/C *14 STP 600V 255 W57 PRESSURIZER PRESS. CH. A/PI-120 INDIC. EA11529A CONTROL RM.PNL. AI-66A (OSPOS) AI-208A 1 2/C '14 STP 600V 100 W57 PRESSURIZER PRESS. CH. A/PI-120 OSPOS I N EB11530 AI-197 CONTROL RM.PNL. AI-668 1 2/C *14 STP 600V 140 W57 PRESSURIZER PRESS. CH. B/PI-120 INDIC. EB11530A CONTROL RM.PNL. AI-668 iOSPOS) AI-208A 1 2/C *14 STP 600V 125 W57 PRESSURIZER PRESS. CH. B/PI-120 OSPOS INPUT FOR CUNSTRUCTION Iceur. -n C. Q. C. '*0UL R an.i. A 12/86 TES

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[ m-I E ,g[IA e rese ISM G W NN CmD N rtwh Lif WCH MC ISSUED FOR n yt tng. No. tusha inw fiw. twstra u nir icar rm GsE FILE NUMBER 43565 u-n a ni.

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